ML20005H333
| ML20005H333 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/15/1990 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-90011, NUDOCS 9001250026 | |
| Download: ML20005H333 (310) | |
Text
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Log # TXX 90011 File # 10010 Z C ; MlELECTR/C Ref. # 10CFR50.34(b) January 15, 1990 ) Wimam J. Cahill, Jr. , Entwavr Vus hrsdent l l U. S. Nuclear Regulatory Commission j l Attn: Document Control Desk i Washington, D. C. 20555
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SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) l DOCKET NOS. 50 445 AND 50 446 i FSAR AMENDMENT 78 DESCRIPTION ! l Gentlemen: l Amendment 78 to the CPSES FSAR was transmitted to you under a separate cover letter TXX 90010, dated January 15, 1990. The attachment to this letter ' provides line by-line descriptions of the the changes in Amendment 78. FSAR pages which do not have technical changes but are included in the amendment ; (because they are the opposite side of the sheet from a page that was changed. [ because the change shifted the existing material to another page or because ; only editorial charges were made on these pages) are not discussed in the attachment. All changes described in the attachment have been evaluated for relative - significance (i.e., the group number 1, 2, 3 or 4 following each change 1 justification) as discussed in TU Electric TXX 88467 dated June 1, 1988. In j addition, for Amendment 78, all changes catergorized as group 2 (there were no group 1 changes) have been evaluated under the TU Electric 10CFR50.59 process l as described in TXX-89718, dated September 28, 1989, and found not to include ! any "unreviewed safety questions." ! As discussed with the NRC staff, the transmittal date for this amendment was intentionally chosen near to the expected fuel load date because the amendment 2 was intended, as best as can reasonably be achieved, to match the FSAR to the ,! Technical Specifications and the as-built plant,.and to_ minimize the number of changes that are not captured in this amendment, which is expected to be the ! last prior to fuel load, Consequently the amendment package is large. I However, less than 10% of the changes in the amendment are categorized as ; group 2 (changes of relatively greater significance). Based on the extensive ; reviews performed by TU Electric'and the relative insignificance of the l majority of the changes, the impact on the NRC's review is expected to be- l minimal, i Included in this amendment are:
- 1. Numerous minor clarifications, corrections and updates to text, tables and a large number of figures.
.l 9001250026 900115 1 PDR ADOCK 05000445 ,
i DQ : K PDC - 4 g( 400 North Olive Street LB. ti Dallas Texas 75201
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TXX 9001'. January 15, 1990 1 Page 2 of 2 1 l 1
- 2. A small number of changes previously provided to the NRC as advanced-FSAR submittels. The revised pages end descriptions in advance i
submittals TXX 89692, TXX 89803, TXX 89809 -TXX 89810 and TXX-89815-are identical to the corresponding changes provided-in Amendment 78 and the descriptions <in the attachment except for page numbering, minor editorial changes and the followings o Revised group classification-(from 3 to 2) for= changes appearing on current FSAR pages 15.6 38.and 39 (TXX 89692) o Added statement.regarding performance of a 50.59 evaluation. , in several group 2 change descriptions (TXX 89692. TXX 89809- , and TXX 89815) o Revised several descriptions to cross reference location of ; detailed justification (TXX 89815)
- 3. Revised Chapter and Master-Table of Contents.- All changes to the Table of Contents are considered to be editorial ~and are not identified by revision. bars or included in the amendment. description attached.
- 4. A revised Effective Page List updated through-Amendment 78.
Sincerely, g. William J. C ill, Jr.
/ ;
BSD/bsd ; c Mr. R. D. Martin, Region-IV Resident Inspectors CPSES (3) t [ t i s
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' Attach:ent to TXX 90011 . .
January 15. 1990- 1 Page 1 of 304 CPSES FSAR AMENDMENT 78 1 DETAILED DESCRIPTION FSAR Page (as amended) Descriotion , 1A(N)-34 Description (Correction) , Discussion in response to regulatory guide 1.60 is cor-
.rected to be consistent with critical damping value !
criteria presented by previous amendments to section . 3.7N and 3.78. ; Justification: ' Correction is consistent with critical damping criteria presented in FSAR sections 3.7N and'3.78. Groups 3 FSAR Change Request Number: 89-713.4 , Related SER Section: 3.7.1 SSER21 3.7.1 i SER/SSER Impact: No 1A(N) 35
Description:
(Update) ' Delete " Grey and Green Books" at the last-line. Justifications- ' The NRC Gray and Green Books are no longer used. Group: 4 ' FSAR Change-Request Number: 89 603.1 SER/SSER-Impact: No 1A(N) 63
Description:
(Revision) Justification: " Revises the steam generator tube plugging criteria to indicate that it is.not based on Regulatory. Guide 1.121 A more conservative approach is used to determine the plugging limit.-This' approach'is consistent withithe plugging criteria accepted by the staff as noted in Appendix H of SSER $4. Groups 3 . - l FSAR Change Request Number: 89 696 Related SSER Section: SSER4 App. H SER/SSER 1mpact: No l 1A(N)-77 Description (Update) 1 Add subsequent revisions of Westinghouse QA Plan-(WCAP 8370).- Justification: , To recognize evolution of Westinghouse OA plan. Group: 4 " FSAR Change Request Number: 89-603.2 SER/SSER.!apact: No t:(L ..- -- . . . . . _ _ _ _ _ _ _ _ _
AttachQent to TXX-90011 Januar'y 15. 1990 1 Page 2 of 304 FSAR Page + las amended) Descriotion I A(B) 4 Description (Correction) NRC Request for Additional Information. Aug. 1, 1989 ' Justification: i Change addresses response to NRC request for-additonal information dated Aug. 1. 1989 pertaining to Chapter 13 issues on training and qualifications. The NRC request contained'11 questions. This change makes the.FSAR' consistent with responses to questions given to the NRC on Aug. 29 and Sept. 5. 1989. Group: 3 . FSAR Change Request Number: 89 649 i Related SER Section: 1A(B) SER/SSER Impact: No 1A(B) 23
Description:
(Correction) t l Corrects number of Primary Plant Ventilation. System E'SF. filtration units.. -' i Justifications i Corrects number of Primary. Plant Ventilation System ESF filtration units from two to four to be consistent with as built conditions as submitted in a. previous FSAR Amendment. Group: 3 , FSAR Change Request Number: 89-628.1 Related SER Section: 9.4.2 SER/SSER 1mpact: Yes SER indicates that 'there are two 505 capacity ESF exhaust filtration units when there are currently four ESF exhaust filtration' units which make up the Primary Plant Ventilation System. .This-is consistent with information submitted inLa. previous FSAR Amendment. 1A(B)-23
Description:
(Correction) . Corrects system. FSAR by deleting reference to hydrogen purge Justification: Corrects FSAR by deleting reference to hydrogen purge system to be consistent with as-built' conditions. As L submitted in a previous FSAR Amendment, the hydrogen
- l. purge system is no longer an ESF system.
Group: 3 . FSAR Change Request Number: 89-628.2 Related SER Section: 6.2.4 SER/SSER Impact: No t, 1A(B)-24 Description .(Correction) Corrects FSAR by deleting Reg. Guide 1.52 quantitative-leak testing requirements. Justification: Since the hydrogen purge system is no longer an ESF - M -- ,
Attache:nt to TXX 90011 l January' 15, 1990 , Page 3 of 304 , 1 4 4 i FSAR Page ! (as amended) Descriotion p 1A(B) 25 Descriptions (Correction) i Clarifies exception to Reg. Guide 1.52. . Justification: Clarifies exception to Reg. Guide 1.52 to show that the HEPA filter and charcoal adsorber efficiency for l the Primary Plant Filtration Units is 95% which - corresponds to an acceptance criteria of less than 1% for in-place penetration and bypass leakage at rated flow. The value for efficiency.is consistent with-information submitted in FSAR Amendment 76. The -! in place penetration and bypass leakage value is addressed in Technical Specification 3/4.7.8. Group: 3 FSAR Change Request Number: 89-628.10 Related SER Section: 6.5.1 SER/SSER Impact: Yes SER 6.5.1.1 identifies' that an- efficiency of 99% was assigned for the evaluation-of the Fuel Handling , Building Ventilation System versus the current- , valua ~~ 95%. This is consistent with information sul, '
> In a previous FSAR Amendment.
IA(B)-35 Desci ' Clarification) . Clat(': s pendix 1A(B) Reg Guide 1.68. Item 2 e < with tne removal of; the reference to Section 14.2.7. Justifications ! l Section 14.2.7 states that exceptions to provisions of l RGs are discussed-in Appendix 1A(B). The deleted sentance under Section IA(B). RG 1=.68. Item 2. removes the cross reference back to Section 14.2.7 and eliminates any confusion of meaning.- Group: 4 FSAR-Change Request Number: 89-576~ Related SER Section: 14 l SER/SSER Impact: No' 1A(B)-43
Description:
(Update) Revises Appendix 1A(B) for RG 1.68. ' Item 20 to include 10% load transient at approximate 1y'30% power following completion of 50% power plateau testing. ' i Justification: Appendix 1A(B). RG 1.68. Item 20 has been: revised per NRC request to provide consistency with previously provided information. Group: 3 FSAR Change Request Number: 89-662.1 Related SER Section:-14 SER/SSER Impact: No
Attache:nt to TXX 90011=
~ January 15, 1990 '
Page 4 of 304 -;
)
FSAR Page (as amended) pescription
- 1A(B) 61 Descriptions (Revision) [
Revise the discussion on Regulatory Guide 1.88. - Justification:- i This change is required to provide for the adequate protection of quality related documentation once the I work activity has been completed and to require the timely submittal of quality related documentation to [ the records storage facility forLretention. ! Group: 3 FSAR Change Request Numbers 89 745-SER/SSER Impact: 1h> 1A(B)-70. 71
Description:
(Addition) . . Adds text re: Regulatory Guide l.108. . clarifying ,the number of required diesel generator starts. Justification: Text re: Regulatory Guide 1~.108 is added to clarify the - number of required diesel generator starts. A total of - 69 (but no less than 23 per Emergency Diesel Generator) valid start and' load tests on the Emergency Diesel l Generators (EDG) is-conducted from cold ambient condi-tions to at least'50 percent continuous rating for at least one hour with no failures.: .This addition /clari- ' l fication is provided as a result of the construction / operation delay of Unit 23 Unit 2 EDG's cannot be counted for the total reliability of the EDG. since-they are not tested at present.' Also, the addition / clarification indicates' that the testing'is not required to be performed during the- < pre-operational testing period of the EDG. but may be performed at any time prior to the required' operability I of the EDG. Group: 3 FSAR Change Request-Number: 89 738 Related SER Section:'14 SER/SSER Impact: No-1A(B)-70. 71'
Description:
(Revision) Provides clarifications and exceptions to several ' Regulatory Positions in Reg. Guide 1.108. Justification: l The justification for the clarifications / exceptions i is listed below the Regulatory Position ~it applies to:- Regulatory Position C.2.a.5: Regulatory Position C.2.a.5 requires the. demonstration of proper operation for design-accident-loading - sequence to design-load requirements. Based on meetings with the NRC to discuss and agree on the final ' Unit 1 Technical: Specifications, the NRC stated that CPSES will be required to demonstrate the proper operation for shutdown-loading-sequence to shutdown-F w , - -
Attachacnt'to TXX 90011 January 15, 1990 Page 5 of?304 FSAR Page (as amended) Description load requirements. Demonstration of the' shutdown ; l loading-sequence is the more conservative- of the' two since the diesel generator will be subjected to its maximum expected loading requirements (See Technical Specification 4.8.1.1.2f.7) which references the shutdown-loading-sequence testing requirement of-Technical Specification 4.8.1.1.2f.4)b)). Regulatory Positions C.2.a.3 and C.2.c.2 Since the intent of the testing requirements is to ensure that the diesel generator can carry its maximum-expected load. 6300 KW (90% of rated load) was selected as the minimum-loaded ccndition. The 6300 KW g value exceeds the maximum expected diesel generator
- loading requirements (see FSAR Tables 8.3-1A 8.3-1B. _&-
8.3-2). and still allows a margin in case loads need to be added at a later date. The 2 hour test requirement (C.2.a.3) will bel conducted at a minimum of 6900 KW which is-approximately 110% of the maximum expected loading requirements. .This change will prevent unnecessary-running of the diesel in-excess of the normal maximum rated-load (7000 KW). Diesel loading is ' accomplished in accordance with l vendor recommendations as suggested in NRC Generic-Letter 84-15. dated July 2. 1984.:'These changes-are consistent with the current Unit 1 Tech. Specs, as
---Continued on-next page---
Group: 3 FSAR Change Request NumDer: 89-770 i Related SER Section: 8. 3 .1 - ' SER/SSER Impact: No 1A(B)-87
Description:
( Addi ti on) Adds exception to Reg. Guide 1.140, ij Justification: ' Adds exception to Reg. Guide _1.140 regarding Regulatory ! Position C.3.h. water drains. which was deleted from - i Reg. Guide 1.52. Since the hydrogen purge system is- ; no longer an ESF. system. the. requirements of Reg. Guide ; 1.140 now apply. 1 Group: 3 ' FSAR Change Request Number: 89-628.7 j Related SER Section: 6.2.4' SER/SSER' Impact: No , i 1A(B)-89
Description:
(Correction) Clarifies exception to Reg. Guide 1.140 Justification: Clarifies exception to Reg. Guide 1.140 to show that I the HEPA filter and charcoal adsorber efficiency for j all non-Engineered Safety Features (ESF) Filtration j i i i k -
.. .~ . _ - , .. -
Attach 2ent to TXX 90011. January 15, 1990 ! Page 6 of 304 ;
-FSAR Page j (as amended)
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Eg3cription Units is 90% which corresponds to an acceptance criteria of less than 15.for in-place penetration and > bypass leakage at rated flow. The value for efficiency is consistent with information submitted in FSAR Amendment 76. Although these are non ESF Filtration > Units, the value for in-place penetration and bypass leakage is conservatively established consistent with - the ESF value. Group: 3 ; FSAR Change Request Number: 89-628.11 ; Related SER Sections-6.5.1 H SER/SSER Impacts'No } 1A(B) 70,71 See Page No(s): Continued from previous page Description (Revision) ' Justification: < Continued from previous page, submitted in TXX-89035, dated January 24, 1989. Regulatory Positions C.2.d and C.3.b: These clarifications and exceptions resulted from the recommendations provided by the NRC in Generic Letter 84-15 dated July 2,.1984, and from direction provided by the NRC during meetings to discuss.and agree.on the final Unit'l Technical Specifications. - Group: 3 FSAR Change Request Number: 89-770. Related SER Section: _8.3.1 SER/SSER 1mpact: No IA(N) 34
Description:
(Correction) Discussion in response to regulatory guide 1.60 is -cor-rected to be consistent with critical damping value , criteria presented by. previous amendments to.section 3.7N and 3.78. Justification: Correction is consistent with critical damping criteria presented in FSAR sections 3.7N and 3.78. Group: 3-FSAR Change Request Number: 89-713.4 Related SER Section: 3.7.1: SSER21 3.7.1 SER/SSER Impact: No 1A(N)-35
Description:
-(Update) Delete " Gray and Green Books" at the last line. ' Justification: The NRC Gray and ' Green Books are no longer used. Group: 4 FSAR Change Request Number: 89-603.1 SER/SSER Impact: No I a i
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' Attach::ent to TXX 90011 '
January 15. 1990 l Page 7 of 304 - FSAR Page (as amended) Descrintion Units is 901 which corresponds to an acceptance criteria of less than 11 for in place penetration and bypass leakage at rated flow. The value for efficiency is' consistent with information submitted in FSAR Amendment 76. Although these are non ESF Filtration " Units, the value for in place penetration and bypass- , leakage is conservatively established consistent with: ' the ESF value. 4 Groups 3- ! FSAR Change Request Number: 89 628.11' " Related SER Section: 6.5.1 SER/SSER Impact: No { i 1A(8) 70.71 See Page No(s): Continued fros' previous page '$ j Description ,( Revision). i I Justification Continued from previous page. l i submitted in TXX 89035, dated January 24.:1989. } Regulatory Positions C.2.d and C.3 b:' These' clarifications and exceptions resulted from the recommendations.provided by the NRC in-Generic Letter 84 15. dated July 2. 1984. and from direction provided . by the NRC during meetings to discuss and agree on the final Unit'l Technical Specifications. Groups 3 FSAR Change Request Number: 89 770 Related SER Section: 8.3.1 2.3 30 Descripticn: (Clarification) Clarifies elevation.at the primary meteorological towe:- base. Justifications i A recent plant survey has indicated that the~ elevation. of the primary meteorological tower to be 838' - 9" in- , lieu of'835' - 0". Group: 4 FSAR Change Request Number: 89 566.1~ Related SER Section: 2.3 SER/SSER Impact: No 2.4 48, 49 See Page No(s):74 Description (Update) Updates source terms for the. liquid radioactive waste holdup tank' accident analysis for releases to surface , water and provides comparision of analysis results with the MPC of radionuclides in s'urface water permitted by 10CFR20 Appendix 8. Justification: The accident scenerio in thettext has been. updated to-reflect the. computer code used in the analysis. Also, results'for Lake Granbury and Lake Whitney.have been deleted since they do not qualify as the nearest potable water supply (SRP 15.7.3). and the concen-trations in those lakes would be insignificant. Releases to those-lakes are also administrative?g i controlled, such that a deliberate long term transt;- of relatively high concentration of radionuclilas is most unlikely. : Reference is made to Appendix D A in
'I
_ Attach ent to TXX 90011 . : January 15, 1990 1 Page 8 of 304 I FSAR Page (as amended) psscriotion order to illustrate the capability of those bodies of l water to further dilute concentrations originating fron Squaw Creek. Reservoir.(SCR). The updated analysis L reflects the most limiting case for surface waters ' discussed in the DBD. and serves:to envelope the analytical guidelines discussed.in SRPs.15.7-3 and . 2.4.13. ' Tables 2.4-20 and 21 have been~ revised to reflect the latest results. ! The updated FSAR text-provides the conclusion-that " the. volume of SCR provides sufficient dilution and the concentration of the radionuclides do not exceed the-maximum permissible concentrations (MPC)'for i unrestricted areas given-in 10CFR20' Appendix B. ; Reference 42 has been deleted to provide-consistency; , with the text-update. . This change has been evaluated under TV Electric's 10CFR50.59 process as discussed in TXX-89718 dated September 28, 1989. Group: 2 , FSAR Change Request Number: 897707 L Related SER Sections-15.4.9 l SER/SSER Impact:<Yes In the current SER.?the stafffconsidered a radionuclide-l inventory assuming 15 failed fuel. however, the updated analysis utilized a radionucitoe; inventory based on ' O.12% failed-fuel.which is consistent with the current , SRP 15.7.3-(NUREG-0800. Rev. 2). 2.4-56
Description:
'(Update) . . Updates Section 2.4.13.1.5 reference to' piezometer installation to-indicate that the groundwater monitors : have been installed. Justification: Revises text to indicate that the groundwater monitors have been installed and'to provide consistancy with Section 2.5.4.13. Group: 4 FSAR Change Request Number: 88-381 Related SER Section: 2.4.6 SER/SSER Impact: Yes. . This information should be included in a supplement to SER'2.4.6. 2,4-63
Description:
(Update) Updates Section 2.4.13 to provide a new table' reference for the initial contents = of the floor drain tank for the accident analysis. Justification: Sectiers 2.4.12 and 2.4.13 provide the results of the analyses pertaining to the failure of.the floor 1 drain ' tank which releases its contents to surface water and groundwater, respectively. The original analyses were I w -. , . - - .
Attach:ent to TXX 90011 3 January 15. 1990 i Page-9 of 304 j FSAR Page (as amended) Descrintion performed by Dames and Noore and -the initial _ contents. of the tank were reflected in Table 2.4-20.- Subsequently. Stone and Webster performed an new analysis just for surface water consequences'and- , Table 2.4-20 was' revised in Amendment 68 to reflect ~ these new inputs. However,-the groundwater _ analysis was not revised and thus Section 2.4.13 incorrectly ' references Table 2,4-20. Table 2,4 20A-has.been added correct this inconsistency. The inputs on Table 2'.4-20A-were originally reviewed by the NRC as Table 2.4 20 . prior to.its update in Amendment 68.. Group: 3 _. FSAR Change Request' Number: 89 642.1
- Related SER Section: 2.4.7 SER/SSER Impact: No l l
Table 2,4 20 See Sheet No(s):01, 02 and 03
Description:
(Update) .
- Updates source terms'for the-liquid radioactive waste holdup tank' accident analysis for releases to surface' !
water. Justification: See Description for pp. 2.4-48 and 49. Group: 2 FSAR Change Request Number: 89 707c .{ Related SER Section: 15.4.9 l SER/SSER Impact: Yes _ i See SER/SSER Impact-description'for p. 2.4-48'and 49. Table 2,4-20A See Sheet No(s):01 and 02
Description:
(Update) Justification: See Description for p. 2.4-63= Group: 3 FSAR Change Request Number: 89-642.1 1 Related SER Section: 2.4.7 SER/SSER Impact: No , i Table 2.4-21 See Sheet No(s):01, 02 and 03 ;
Description:
(Update) ' Updates results for revised liquid radioactive waste holdup tank accident analysis for releases to surface # water.and provides comparision of analysis results with' the MPC of radionuclides in surface-water permitted by , 10CFR20 Appendix B. 4 Justification: See Description for pp. 2.4-48 and 49. ' Group: 2-FSAR Change Request Number: 89-707 Related SER Section:-15;4.9 SER/SSER Impact: No W ' w w
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7 _ Attach ent-- to TXX 90011 1 January 15, 1990 Page 10 of 304 FSAR Page-(as_ amended) Descrictiog Table 2.4-28 Descriptions,(Editorial) Justification: , Provides a typograhical correction to Table 2.4 28'with- l the correction of "CS-135" to " CS-134". f Group: 4 t FSAR Change Request Number: ,89 642.2 Related SER'Section: 2.4.7 ' , j SER/SSER Impact: No , Figure 2.4 9
Description:
(Clarification)- Justification: Corrects typographical errors on F2.4-9 to provide ; consistency between the Figure - and Sections 2.4.3' 3.1, 2.4.8.2.1 and T2.4-17._ Group: 4 FSAR Change Request Number:. 88-558.3 Related SER Section: 2.4.3 ., SER/SSER Impact: No , 2.5-149, 229 See Page-No(s): Figure 2.5.4 54 Descriptioni (Clarification)- Clarify terms for Figure 2.5.4-54 Justification: More clearly defines-the terus used to describe the magnitude of? lateral forces on subgrade walls for_both static and dynamic conditions as graphically depicted -' on Figure'2.5.4-54. Adds references from which these' ; terms were developed. .: Group: 4 _ d FSAR Change-Request Number: 89-543 Related SER Section: 2.5, SER/SSER Impact: No 2.5-151, 153
Description:
(Update) - Revises the number and location of piezometers used to monitor groundwater-conditions and specifies the time period for groundwater _ data collection. Justification: Updates the FSAR-to show the exact' number and* location of the installed permanent piezometers, to indicate that groundwater data was collected.forLone year and that the-perch water condition around the plant structures has been evaluated ~and~no remedial actions - were necessary. , Group: 4 FSAR Change Request Number: 88-381 , Related SER Section: 2.5.4.1 y
~ Attach ent< to TXX-90011- :
January 15. 1990 i (Page 11 of 304 1 I . _ FSAR Page i L l- fas. amended) Deserintion SER/SSER Impact:-Yes This information should be included in a supplement to
- a. SER 2.4.6.
Description:
(Update) Figure 2.5.4 55 Revises the number and location of piezometers_used to-monitor groundwater conditions. < Justification: ; See Description for~pp. 2.5-151 thru 2.5-153. l Group: 4 -' FSAR Change Request Number: 88-381 Related SER Section: 2.5.4 ; SER/SSER Impact: No. Figure 2.5.5-78 See' Sheet No(s):and Figures 2.5.5-79 thru 2.5.5-94
Description:
(Update)- i' l Provides boring logs generated during'the'pieometer' l installation. Justification: See Description for pp. 2.5-151'thru 2.5-153. Group: 4 ~ FSAR Change Request Number: 88-381 Related SER Section: 2.5.4 SER/SSER' Impact: No 3.1-17
Description:
(Editorial) i Justification: i _ewords R the GDC 19 discussion.to remove reference te l control' room chlorine detectors. This change-was in-advertently not_ included in' Amendment 76 although des - cribed in FSAR description' letter TXX-89201 dated May_1. 1989-(Page 14 of Attachment).LThis change is , consistent with FSAR Appendix 1A(B) for Regulatory Guide 1.95, i Group: 4 3 FSAR Change Request Number: 89-673 Related SER Section: 6.4-SER/SSER Impact: No Table 3.2-1 See Sheet No(s):02-
Description:
.(Revision) - Remove "ASME B&PV Code. Section VIII.and" from NNS class column for pumps on Sheet 2 of Table 3.2-1. Justification: 1974~ Edition of ASME B&PV Code. Section VIII.l Paragraph U-1 Scope states that this--section covers requirements for pressure vessels and does not address any requirements for pumps. . Summer 1975' Addenda for Sec. VIII Paragraph U-1 Scope (C)-(3) clarifies this by-stating that pumps are not considered to be within=the scope of Division 1 of.Section VIII. Group: 3 ,
, m ,- '
li
. Attach:ent to TXX-90011.' ~ January 15, 1990 Page 12 of 304 FSAR Page (as amended) Description FSAR Change Request Number: 89-712 SER/SSER Impact: No Table 3.2-3 See Sheet No(s):01 thru 11
Description:
(Correction) Replace current Table 3.2-3 with the updated and ! reformatted table corresponding to the flow' diagram changes.in FSAR.- Justification: The table incorporates flow diagram changes which have added/ deleted / changed the corresponding FSAR figures. Group: 4
.FSAR Change Request Number: 89-357 SER/SSER Impact: No-Table 3.2-3 See Sheet'No(s):02-
Description:
(Editorial)- Justification:
~This table is-updated to-correspond to the redrawn diesel generator figures;-
Group: 4-FSAR Change Request Number: SA-89 710 Related SER Section: 9.5.4 SER/SSER Impact: No !
'\ -Figure 3.2-1
Description:
(Update) ! Minor Figure updates Justification: No justification necessary. These figures contain changes of the following type: ,
- 1. Manual vent or-drain valves -' addition, removal, re- 1 location, valve number. '
- 2. Manways or-handways - addition, removal, or~re-location. '
- 3. Editorial - spelling', editorial or draf ting errors whie.h'cannot impact technical _ meaning-of the diagram
- 4. Line numbers or line sizes.
- 5. Flanges or reducers - addition . removal or re-location.
- 6. Piping.or instrumentation - physical' interconnection j changes which have no impact on the. operation /func- l tion of system and equipment. ]
- 7. Manual valves - valve numbers or physical location -
1 changes which have no impact on the operation /func- { tion of system and equipment. {
- 8. Elevation changes, l Group: 4 !
FSAR Change Request Number: 89-732 SER/SSER Impact: No !
Li l- Attach:ent' to TXX 90011 , January. 15, 1990
- Page 13'of 304 ;
FSAR Page (as. amended) Description 3.6B 7
Description:
(Revision) Break propagation criteria in thel event of aLsmall , branet line rupture that results in a LOCA is revised to state specifically the extent to which the prop'agat-- ; ion of the break to a high head safety injection line . must be limited to. x Justification: . The revised small branch line rupture, that results in -
-a.LOCA. break propagation criteria. delineates that. loss. ,
of high head safety injection capability.due to a . spilling 1-1/2= inch diameter ' injection line for- a cold leg break in the same-loop, but not overall= Safety'In-jection System failure. The effects of the potential-loss of high head safety injection is bounded by the small break LOCA analysis in that.it is. limited to a total break area of 12.5 square = inches and-the analysis ' is for l' square foot and smaller'. This revision is. con-sistent with Westinghouse Standard Design Criteria and has been evaluated under the TU Electric 10CFR50 '59' l procedures per TXX-89718 dated September 28,'1989. J l Group: 2' , j FSAR Change. Request Number: 89 700 Related SER Section: 3.6.1 .SSER21 6.3.5 SER/SSER Impact: . No-3.6B-18
Description:
(Correction) ; Break postulation criteria for ASME Section III. Code Class 1 piping is corrected'to reflect that break loca-tions are no~ longer arbitrarily selected based upon the highest stress' although ASME Code allowables and usage factors, as provided by the SRP are not. exceeded. , Justification: i The correction to Classti piping break postulation is. .i I incorporated consistent with-the= provisions specified l by NRC letter dated October 13 J1987 which provided ap- . proval.for implementation of Generic Letter 87-11. Group: 4 ' FSAR Change Request: Number: 89-521. Related SER Section: 3.6.2: SSER21 3.6.2' SER/SSER Impact:'No 3.68-29
Description:
(Revision) !
- Provide alternative computer program (STEHAM) for analyzing the dynamic effects of postulated high energy line breaks in the Main Steam Line.
Justification: Revised provision to allow the usage of an alternative computer program facilitates a division in engineering work scope but-does not effect the-equivalency of the-results to existing CPSES computer programs for analyz-ing the dynamic effects of a. postulated high energy
~
line break. n
t Attach:Gnt to TXX 90011 ' January. 15,1990 Page 14 of 304' FSAR Page -l
-(as amended) Description l
[ i l Group: 3 ,-> FSAR Change Request Number: 89-794.1 ~! Related SER Section: 3. 6.1 :- SSER17 4.5.2 : SER/SSER Impact: No' d 3.6B 30 Description (Revision) [ Provide alternative computer program (REPIPE).for de- ) veloping break- force time-history plots as a post pro - cessor program to RELAP for use in analyzing the con - sequences of a high energy line break , Justification: Revised provision to allow the usage of an alternative. computer program-facilitates a division in engineering- : work scope but does not effect the equivalency of-the j results to existing CPSES" computer programs forfanalyz-- ; ing the dynamic effects of a psotulated high energy line break. Group: 3 FSAR Change Request Number: 89-794.2 Related.SER Section: 3.6.1: SSER17 4.5.2 SER/SSER Impact: No l 3.6B-31 Descriptions (Revision) Provide alternative computer program (CHPLOT) for: deve-' ' loping break force time-history plots as a post pro-cessor-program to LIMITA3 for use irr analyzing the con- ' l sequences of a high energy line break.: L Justification: l Revised provision to allow the usage of an alternative , l computer program facilitates a. division in engineering l work scope but does not effect the' equivalency of the- ; l results.to existing CPSES computer programs for analyz-ing the dynamic effects of a postulated high energy line break. Group: 3 , FSAR Change Request Number: 89-794.4 l Related SER'Section: 3.6.1: SSER17 4.5.2 SER/SSER Impact: No 3.6B-31, 32
Description:
(Revision) ' Provide alternative computer programs -( ANSYS & LIMITA3) for' determining the piping dynamic response resulting from a postulated pipe rupture. Justification: Revised provision to allow the usage of an-alternative
~
computer program. facilitates a division in. engineering work scope but does not effect the equivalency of the results to existing'CPSES computer. programs for analyz-ing the dynamic effects of=a postulated high energy , line break, s Group: 3 FSAR Change Request Number: 89-794.5'
Attachn nt to-TXX 90011 , January 15. 1990 l Page 15 of 304 i FSAR Page i (as amended) Descrietion R? lated SER Section: 3.6.1: SSER17 4.5.2 SER,SSER Impact: No 3.68-31
Description:
(Revision) Provide description of alternative computer'pr'ogram (STEHAM) utilized in the analysis of postulated high energy line breaks in the Main Steam Line. Justificationt Revised provision to allow the usage of an alternative computer program facilitates a division in engineering. ' work scope but does not effect the equivalency of the- ' results to existing CPSES computer programs.for'analyz-- ing the dynamic-effects of a postulated high-energy. line break. Group: 3 . FSAR Change Request Number: 89-794.3 ; Related SER Section:.3.6.1: SSER17 4.5.2 SER/SSER Impact: No 3.6B 33
Description:
(Editorial)' i Reinserted introductory paragraph to FSAR section ! 3.6B.2.3.2A that was inadvertently deleted during the final processing of amendment 76. Justification: The editorial correction provides accurate and complete discussion of jet impingement discussion. Group: 4 FSAR Change Request Number: 89-453 l Related SER Section: 3.6.2: SSER17 4.5.2. I SER/SSER Impact: No i l 3.6B-38
Description:
(Correction) l' Editorial correction.is made to'the equation for "f(h)" by replacing the expression under the square-root. stagnation enthalpy plus(+) saturated-liquid enthalpy !' with stagnation enthalpy minus(-) saturated liquid en-thalpy. Justification: During the final processing of amendment 76, an edi-torial error resulted in~the insertion of a plus sign instead of the desired minus sign. ~i Group: 4 l FSAR Change Request Number:'89-686 i Related SER Section: 3.6.2: SSER17 4.5.2 l SER/SSER Impact: No- , i 3.6B-51, 52
Description:
(Correction) . I The discussion on' Main Loop break postulation is-re- ; moved consistent with the Main Loop reanalysis'that no I longer includes these breaks in the piping design bases . as a result of implementing " broad scope" GDC-4 leak- ' before-break methodology. I
Attach ent to TXX 90011 January 15, 1990 .Page 16 of 304 FSAR Page (as amended)- Description Justification: Implementation of leak-before-break methodology support the elimination of- Main Loop pipe breaks in compliance with " broad scope" GDC 4. Group: 3 FSAR Change Request Number: 89-452.1 Related SER Section: 3.6.1: SSER21 3.6.1 SER/SSER Impact: No 3.6B-71 Description (Editorial ~) Residual Heat Removal- (RHR) system general description section is corrected to accurately reflect that the RHR suction lines are branch lines of the-Reactor: Coolant system hot leg loops 1 and 4. Justification: Corrected a inadvertent. typographical error of the RHR general system description section consistent with CPSES design bases documents and drawings. Group: 4 FSAR Change Request Number: 89-728 Related SER Section: 3.6.1; SSER21 3.6.1 SER/SSER Impact: No 3.68 79, 80
Description:
(Addition) References are added to section 3.6B list of references-for computer programs STEHAM, REPIPE,'ANSYS.'LIMITA3. and CHPLOT. Justification: The addition of references for computer programs being. utilized for analyzing the consequences of a high energy line break provides the supporting documentation of their acceptability. Group: 3 FSAR Change Request Number: 89 794.6 Related SER Section: 3.6.1: SSER17 4.5.2 SER/SSER Impact: No Table 3.6B-1 See Sheet No(s):11
Description:
(Correction) High Energy Line List Table is corrected by incorporat-ing reference notes. consistent with the line configur-ation and the. corresponding. flow diagram. Justification: Corrections are incorporated to ensure high energy line list is complete, accurate and consistent with.CPSES design bases documentation. Group: 4 FSAR Change Request Number: 89-742.1 Related SER Section: 3.6.2: SSER6- 3.6.2.2 SER/SSER Impact: No
1: : 0 Attach;ent to TXX-90011 l January 15.11990
-Page 17 of-304 FSAR Page ~!
(as amended) Description Table 3.68 1 See Sheet No(s):16
Description:
(Correction) High Energy Line List Table'is corrected by incorporat - ' ion of line number *2CS 1-092-2501R-2 that was inadver- t tently ommitted from the table. Justification: _ ; Corrections are incorporated to. ensure high energy line L list is complete, accurate and consistent with CPSES , design bases documentation. [ Group: 3 FSAR Change Request Number:'89 742.2 Related SER Section: 3.6.2: SSER6 3.6.2.2 . SER/SSER Impact: No Table 3.68-1 See Sheet No(s):16.
Description:
(Correction) High Energy Line List Table is corrected by incorporat-ing reference notes consistent with the line configur-ation-and the corresponding flow diagram. l Justification: Corrections are_ incorporated to ensure high energy line l list is complete, accurate and consistent with CPSES ' I design bases documentation. Group: 4 FSAR Change Request Number: 89-742.3 Related SER Section: 3.6.2 SSER6 3.6.2.2 SER/SSER Impact: No Table 3.6B-1 See Sheet No(s):20. *
Description:
(Correction) High Energy Line ' txt-Table '.s corrected by changing the -line numbe; desigi.ated 11W-128" to "1FW-128" con-sistent with the flow diagram. Justification: Corrections are incorporated:to ensure high energy line list is complete, accurate 1and consistent with CPSES > design bases documentation. . Group: 4 FSAR Change Request Number:' 89-742.4 Related SER Section: 3.6.2: SSER6 3.6.2.2 SER/SSER Impact: No Table 3.6B-1 -See Sheet No(s):22, 24, 27 and 29-
Description:
(Correction) High Energy Line List Table.is corrected by .incorporat-ing reference notes andLasteriks (*) consistent with= < the line configuration and correspond N #1nw diagram. Justification:
' Corrections are incorporated to ensure high energy line' ,
list is complete, accurate and consistent-'with CPSES
- design bases documentation.
Group: 4
'Attachm nt to TXX-90011 ' January . 15, 1990 Page 18 of 304 l
L FSAR Page ' (as amended) Description l FSAR Change Request Number: 89-742.5 l Related SER Section: 3.6.2: SSER6 3.6.2.2 SER/SSER Impact: No i l Table 3.68-1 See Sheet No(s):38 l
Description:
(Correction) l l High Energy Line List Table is corrected by incorporat- ' ion of line number *6-2003-2 that was inadvertently;om-mitted from the table. - Justification: . .
' Corrections are incorporated to ensure high energy line '
list is complete, accurate and consistent with CPSES , design bases documentation. ! Group: 3 ' FSAR Change Request Number: 89-742.6 Related SER Section: 3'. 6. 2 ; SSER6 3.6.2.2 : SER/SSER Impact: No Table 3.6B 3 Descriptions (Correction) . The removal of the table which provided the bases for Main Loop break postulation criteria (e.g., cumulative usage factors, OBE moments, thermal expansion moments). l Main Loop breaks are no longer considered part of the L piping design bases. Justification: The removal of this table'of Main Loop break postula-tion criteria corrects the FSAR consistent with the im- : pienentation of leak-before-break into the plant design i bases. , Group: 3 FSAR Change Request Number: 89-452.2 Related SER Section: 3.6.1; SSER21 3~.6.1 SER/SSER Impact: No . Figure 3.6B-11, 12 See Sheet No(s): Figure- 3.68-13, 14 and 15 l-
Description:
_( Addition) . . High energy line break stress node break point and re - l straint figures are clarified by the~ addition of a-note. that delineates the, status of~the pipe whip restraint . for mitigation / restraint of the postulated break. Justification: , ~ Addition of the note reflects the final as-built status-of postulated break locations. The inactive pipe whip restraints are left in place and serve no function in mitigating the consequences of the whipping pipe. Group: 3 ' FSAR Change Request Number: 90-004.1 Related SER Section: 3.6.1: SSER12 3.6.1 SER/SSER Impact: No 1 -- .
i Attach 2snt. to TXX-90011 ! January 15, 1990- 1 Page 19 of 304 . 4 FSAR Page l Cas amended) Description 3 Figure 3.6B-16, 17
Description:
(Correction) High energy line break stress node break _ point and re- ' straint figures are changed to reflect the correct pipe whip restraint number designations.- Justification: The. correction is consistent with the pipe whip re- . straint numbering methodology for this type of. pipe whip restraint. ] . Group: 4 i FSAR Change Request Number: 90-004.2 Related SER Section: 3.6.1; SSER12 3.6.1 SER/SSER Impact: No Figure 3.68-18, 19. See Sheet No(s): Figure 3.6B-20, 21 and 22 s
Description:
(Addition) High energy line break stress node break point and re-straint figures are clarified by the addition of a note that delineates the status of the pipe whip restraint ' for mitigation / restraint of the postulated break. Justification: Addition.of the note reflects-the final as built status of postulated break locations. The inactive pipe whip 4 restraints'are left intplace and serve no function in ; mitigating the consequences of.the whipping pipe. ' , Group: 3 i FSAR Change Request Numbers- 90-004.4 ,, Related SER Section: 3.6.1; SSER12 3.6.1 SER/SSER Impact: No l Figure 3.6B-23 See Sheet No(s):1 and 2
Description:
(Correction) i High energy line break stress node break point and re-straint figures are_ changed.to reflect the correct pipe whip restraint number' designations. Justification: The correction is consistent with the pipe whip re- . straint numbering methodology for this_ type:of pipe - whip restraint. < Group: 4 FSAR Change Request-Number: .90-004.5 Related SER Section: 3.6.1; SSER12 3.6.1 SER/SSER Impact: No' s Figure 3.6B-23 See Sheet No(s):1 and 2 i Descriptions (Addition) High energy line break stress node break point and re- , straint figures are clarified by the addition of a note that delineates the status of the pipe whip restraint for mitigation / restraint of the postulated break. ' Justification: Addition of the note reflects the ; final as-built status of postulated break locations. The-inactive' pipe whip ~
, ~.
F Attach ent to TXX 90011 January- 15, 1990c ; Page 20 of 304- t
-FSAR Page (as amended) Description ;
restraints are left in place'and serve no function in l mitigating the consequences-of the-whipping pipe. Group 3' FSAR Change Request Number: 90 004.6 Related SER Section: 3.6.1: SSER12.3.6.1 ; SER/SSER Impact: No: Figure 3.6B-24 See Sheet No(s):1 (
Description:
(Update) High energy line break stress node break-point and re- 1 istraint figures are-updated to reflect final as-built break locetions' and break designation nomenclature changes ~. Justification: Update of the figures.is predicated upon the,implemen-x tation of HELB postulation criteria delineated by.FSAR sections 3.6B.1 and 3.68.2. Group: 3 FSAR Change Request Number:-90 004.3 Related SER Section: 3.6.1: SSER12'3.6.1 SER/SSER Impact: No Figure 3.6B-27, 28
Description:
(Addition) High energy line break stress node break po' int and re-straint figures are clarified by the addition of a note : , that delineates the status of the pipe whip restraint i i for mitigation / restraint of the postulated break. E ' Justification:
- Addition of the note' reflects the final as-built status 2
'of postulated break ^1ocations.:The* inactive pipe whip restraints are left in place and serve no function'in'-
i mitigating the consequences of the whipping pipe. Group: 3 FSAR Change Request = Number: 90-004.7 , ! Related SER Section: 3.6.1 SSER12-3.6.1-l SER/SSER Impact: No-Figure 3.6B 30 See Sheet No(s): Figure 3.6B-35 t
Description:
(Update) High energy line break stress node break point and re-straint figures are updated to' reflect final as-built break locations and break designation nomenclature ' changes. Justification: Update of the figures is predicated upon the implemen-tation of HELB postulation criteria delineated by FSAR
~
sections 3.6B.1 and'3.60.2. Group: 3 FSAR Change' Request Number: 90-004.8 4 Related SER Section: 3 . 6.'1 : SSER12-3.6.1 SER/SSER Impact: No 4
Attach:ent to TXX 90011 -i I
. January 15. 1990-Page 21 of 304 ;
1 FSAR Page (as. amended) DescriDtion Figure 3.68-36 See Sheet No(s): Figure 3.68-41 '
)
Description:
(Addition) High energy line break-stress node break point and re - l straint figures are clarified _by the addition of'a note that delineates the. status of the pipe whip restraint 1 for mitigation / restraint of,the postulated break. I Justification: Addition of the note reflects'the, final.as-built status. of postulated break locations..The inactive pipe whip restraints.are left in place and serve no function'in mitigating the consequences of the whipping pipe.- ' ' Group: 3 . FSAR Change Request Number: 90-004.9, , Related SER Section: 3.6.1: SSER12 3.6.1 i SER/SSER Impact: No Figure 3.6B-43, 44
Description:
(Update) _ . High energy line break stress node break point.and re-straint figures are updated to reflect final as built break-locations and break designation nomenclature changes. Justification: - i Update of the figures is' predicated upon the,implemen- '! tation of HELB postulation criteria delineated by FSAR j sections 3.68.1 and 3.6B.2. j Groups 3 ! FSAR Change Request Number: 90 004.10 l Related SER Section: 3.6.1: SSER12 3.6 1 . SER/SSER Impact: No l Figure 3.68-44'
Description:
(Addition) l_ . l High energy line break stress node break point and re- l straint figures are clarified by the addition of a note. that delineates the status of the pipe whip restraint-for mitigation / restraint of the postulated break. l Justification: Addition of the note reflects the. final a's-built status i of postulated break locations. The inactive-pipe-whip 3 restraints are.left in place and serve no function in ' mitigating the consequences of the whipping pipe. Group: 3 i FSAR Change Request Number: 90-004.11 : Related SER Section: 3.6.1: SSER12 3.6.1 { SER/SSER Impact: No i Figure 3.68-48 See Sheet No(s):1 :
Description:
(Update) ! High energy line break stress node break point and re- 'l straint figures are updated to reflect final'as-built break locations and break designation nomenclature changes. Justification: LE , i
Attach:cnt to TXX-90011 1 January 15, 1990- l Page 22 of 304 j FSAR Page . (as amended) Description Update.of the figures is. predicated upon the.implemen-tation of HELB postulation criteria delineated by FSAR sections 3.6B.1 and.3.68.2. ; Group: 3 . i FSAR Change Request Number: 90-004.12-Related SER Section: 3.6.1: SSER12 3.6.1 SER/SSER Impact: No i Figure 3.6B 49
Description:
(Correction)- . High energy line break stress node break point and re-straint figures are changed to= reflect the correct-pipe- - whip restraint number designations'.:
~
Justification:
- The correction isfconsistent with the pipe whip re- !
straint numbering methodology for this type of pipe whip restraint. Group: 4 ; FSAR Change Request Number: 90-004.13 Related SER'Section: 3.6.1: SSER1213.6.1 SER/SSER Impact::No i Figure 3.68-52 See Sheet No(s):1
Description:
(Update) L High energy line break stress node' break point'and re- I straint figures.are updated to reflect final es-built-break locations. and break designation nomenclature changes.. - Justification: Update of the figures-is predicated upon the'implemen-tation of HELB postulation criteria delineated by- FSAR sections 3.68.1 and 3.68.2. Group: 3- . . FSAR Change Request Number: 90-004.14 t
-Related SER Section: 3.6.1: SSER12 3.6.1 SER/SSER Impact:-No Figure 3.6B-52 See Sheet No(s):1
Description:
(Addition) High energy line break stress node break point and re- ,! straint figures are clarified by the addition of a note q' that delineates the status of the pipe whip' restraint for mitigation / restraint of the postulated break. Justification: Addition of the-note reflects the final as-built status of postulated break locations.-The inactive pipe whip restraints are left in place and serve no function in - mitigating the consequences of the whipping pipe. Group: 3 FSAR Change Request Number: 90-004.15 Related SER Section: 3.6.1: SSER12 3.6.1 SER/SSER Impact: No
q Attach:ent to TXX 90011 i, January 15, 1990 1 1 Page 23 of 304 I FSAR Page l (as amended) Descrintion j ! Figure 3.6B 53, 54 See Sheet No(s): Figure 3.6B 55'and 58 (sheet 3)
Description:
(Addition) High energy line break' stress node break point and re- ' I straint figures are clarified by,the addition-of_a note-that delineates the status of the pipe whip restraint for mitigation / restraint of the postulated break. Justification: =! l Addition of the note reflects the final as built' status { of postulated break locations. The inactive pipe whip = l restraints are left in place and serve no function in mitigating the consequences of the whipping pipe. [ Group: 3 FSAR Change Request Number: 90-004.16 'i Related SER Section: 3.6.1: SSER12 3.6.1 ( SER/SSER Impact: No ! Figure 3.6B See Sheet No(s):1 :- [-
Description:
(Update) High energy line break stress node break point and re-straint figures'are updated to reflect final as built-break locations and break designation nomenclature , changes _ Justification: Update of the figures is predicated upon the implemen-tation of HELB postulation criteria delineated by FSAR , l sections 3.6B.1 and 3.6B.2. l Group: 3 . . I FSAR Change Request Number: 90-004.17 Related SER'Section: 3.6.1: SSER12 3.6.1 SER/SSER Impact: No l Figure 3.6B-64 See Sheet No(s):1 and 2
Description:
(Addition) High energy line break stress. node ~ break point and're-straint figures are clarified' by the addition of a note that delineates the status-of the pipe whip restraint for mitigation / restraint of the postulated break. _ Justification: Addition of the note reflects the final as-built status of postulated break locations. The' inactive pipe whip restraints are left in place and serve no function in mitigating the consequences of the whipping pipe. Group: 3 FSAR Change Request Number: 90-004.18 Related SER Section: 3.6.1: SSER12 3.6.1 SER/SSER Impact: No , Figure 3.68-64 See Sheet No(s):2
Description:
(Update) High energy line break stress node break point and re-straint figures are updated to reflect final as-built break locations and break designation nomenclature I _
. .- . ~ . . . -- - .... . --
0 Attach:3nt to TXX 90011 1 January 15, 1990 Page 24 of 304 1 0 FSAR Page~ ! Descrintion-
~
(as amended) changes. , Justification. .c Update of the figures is' predicated upon the implemen- 4
.tation of HELB postulation criteria _ delineated.by FSAR-sections 3.6B.1:end 3.68.2. t Group: 3 FSAR Change' Request Number: 90 004.19 Related SER Section: 3.6.1: SSER12 3.6.1-
- SER/SSER' Impact: No Figure.3.6B-65 '
Description:
(' Addition) . . . . High energy line break stress node break point and re - .
,straint~ figures are clarified;by the addition of a note.
that delineates the status of the pipe' whip restraint
~
for. mitigation / restraint of the postulated break. }' Justification: Addition.of the note reflects the~ final'as-builtEstatus- i of postulated- break locations. The' inactive pipe whipi restraints are left in place and serve no function in mitigating the consequences of the whipping pipe. ; Group: 3 3 FSAR Change Request Number: 90-004.20 i Related SER Sections 3.6.1: SSER12 3.6.1
- l. SER/SSER Impact: No
' Figure 3.6B-67_ See. Sheet No(s):1
Description:
(Update)- High energy line break stress node break. point and re-straint figures- are updated to reflect: final as-built - break tlocations and' break designation nomenclature changes. Justification: Update of the' figures is predicated upon the implemen-
- tation of HELB postulation criteria delineated by FSAR '
sections.3.6B.1 and 3.68.2. "
.iroup: 3 FSAR Change Request Number: 90-004'.21 Related SER Section: 3.6.1; SSER12 3.6.1 SER/SSER Impact: No J l ..
Figure 3.6B-68 See Sheet No(s):1
Description:
(Update) High energy line break. stress node break point and re - ' stroint figures are updated to reflectLfinal as-built break locations and break designation nomenclature i changes. Justification: Update of the figures is predicated upon the implemen-tation of HELB postulation criteria delineated by..FSAR sections 3.6B.1 and 3.6B.2. Group: 3 FSAR Change Request Number: 90-004.22 a-
.%.- .,. - . - - s _ _ _ _.____m s- --w -_ _ . -___ - _
Attach:ent to TXX-90011 ~ j f January 15. 1990 Page 25 of'304 . I FSAR Page . X (as amended) Descriotion Related SER Section:~3.6.1: SSER12 3.6.1 SER/SSER Impact: No 1' Figure 3.68 74 See Sheet No(s): Figure 3.68 80 and 82 (sheet 1) Oescription: (Update) ' High energy line break stress node break point and re-straint figures are updated to reflect final as built i break locations and break designation nomenclature changes. I Justifications ! Update'of the figures is predicated upon'the implemen- $ tation of HELS postulation criteria delineated by FSAR sections 3.68.1 and 3.68.2.. Group: 3 FSAR Change Request Number: 90 004.23 Related SER Section: 3.6.11 SSER12 3.6.1 ' SER/SSER Impact: No 3.7N 2 Descriptions (Clarification) I Clarified that Table 3.7N 1 provides damping values utilized within Westinghouse equipment and original ' Westinghouse analyses. Justification: Table 3.7N 1 provides. critical damping values utilized. I by Westinghouse in the analysis of equipment and piping L systems that are consistent with the provisions of ( Regulatory Guide 1,61 and Code Case N 411'.as required. Group: 4 FSAR Change Request Number: 89-454.1 Related SER Section: 3.7.12 SSER21 3.7.1' SER/SSER Impact: No " 3.7N-2, 3
Description:
(Update)- An update is provided that details the scope of systems utilizing ASME Code Case N 411. within the scope of ' NSSS, and that in all cases it was used for reconcilia- ' tion of NSSS piping stress analysis. Justification: This update is provided to comply with the provisions *
~
specified by the NRC in granting the approval for usage-as stipulated by SSER 21. Group: 3 {- FSAR Change Request Number: 89 454.2 Related SER Section: 3.7.1: SSER21 3.7.1 SER/SSER' Impact: No 3.7N 3
Description:
(Update) An update is provided that ASME Code Case N-397 is'not used for NSSS scope piping analysis and that any future use will, be detailed in the FSAR and in compliance with NRC requirements.for' usage at CPSES. Justification: This update is provided to comply with the provisions specified by the NRC 'n granting the approval for usage
! as stipulated by SSER 21.
Group: 3 FSAR Change Request Number: 89 454.3 < Related SER Section: 3.7.1: SSER21 3.7.1'
.SER/SSER Impact: No- ,.
o
a Attach:ent to TXX-90011 January 15, 1990 ! Page 26 of 304 FSAR Page j (as amended) Descrintion 3.7N 35
Description:
-(Addition) . . Incorporation of NRC eva?uation of request to use'ASME. Code Case N-411 and N 397'into th? -list of references for section 3.7N. Justification: Added NRC evaluationTof'the acceptability of utilizing. ASME Code Case-N 411 and N-397 into the list of refer ' ' ences, that provides the requirements for acceptable usage of the subject ASME. Code Cases in analysis. , Group: 4 , FSAR Change Request Number: 89 454.4 Related SER.Section: 3.7.1 SSER21.3.~7.1 SER/SSER !apact: No l 3.7B 4 Cescription:-(Update) An update is provided that details the~scopeLof Balance l of Plant systems usage of ASME Code Case N 411, with- > the exception of. piping stress analysis problem number-l 1-061, all non-NS$$ safety related stress analysis- ' utilize Code Case N 411. Justification: This update is'provided to comply with the provisions specified by the NRC in granting the approval for usage ,, as stipulated by SSER 21. The use of Code Case N 411 ' was utilized for new piping and. support optimization work and pipe stress reconciliation work. Group: 3 FSAR Change Request Number:- 89-586.1 Related SER Section: 3.7.1: SSER21 3.7.1 SER/SSER; Impact: No . 3.78 4 Descriptions (Clarification) Clarified that damping values utilized in the Westing-house piping analysis are shown in section 3.7N. Justification: Damping values- utilized in the performance of Westing- -i house piping analysis are provided'in:section 3'.7N.< Groups 4 ' FSAR Change Request Number: 89-586.2 3 Related SER Section: 3.7.13- SSER21 3.7.1 i SER/SSER !apact: No-3.78 40
Description:
(Addition) . Provides reference for typical response' spectra _ Figures' < 3.78-41 through 3.78-50C for Category 1 Buildings.. !' Justification: This LDCR will resolve concerns identified during the NRC structural audit at CPSES during Sept. 6 7, 1989. l
~. .
Attach 2ent'to'TXX 90011 -[ January,15, 1990 ; Page 27 of 304 , s FSAR Page ' (as amended) Descrintion Figures 3.78 41 through 3.78-50C are being placed in L the FSAR forjinformation only. No technical changes are involved.. ; Group: 3 i FSAR Change Request Number: 89-651.2 ? i: Related SER Section: 1 3.7.2 I l SER/SSER Impact: No 3.7B 42
Description:
(Clarification) o Corrects sentence describing how structural. failure of A the Turbine-Building.in the direction of the adjacent ~! Seismic Category I buildings is~ prevented. .The phrase- :
"the horizontal brtcing internal to the steel frame" is i
removed'to eliminate misinterpretation. Justification: ; This LDCR will resolve concerns identified during the ! NRC' structural audit'at CPSES during Sept.: 6-7. 1989.- 4
- The primary. mechanist preventing f ailure is the bearing . ,
of the mezzanine and operating floor ~ slabs on the tur-- bine generator _ pedestal. -The phrase "the horizontal. I bracing internal to the steel, frame" is removed to- ' eliminate the misinterpretation that the horizontal- , bracing shares the load transfer mechanism.. -> Group: 4 _ j FSAR Change Request Number: 89-651.1 Related SER Section: 3.7.2 SER/SSER Impact:'No-3.78 68
Description:
(Addition) _ Adds " enveloping methods" to_the methods which may be~ used to analyze the-effects of failure of non Category. I piping on adjacent Category I piping. . , Justification:- It was found-that the: nomograph method;and simplified dynamic analysis were inadequate for certain-applica - tions.- Resolution'and documentation of.this inadequa- , cy.' including use of: enveloping. methods.- are discussed-in TXX letters related to SDAR CP-87-062.. For the en-
) ,
veloping methods, a rigorous analysisLis performed for= 1
" worst case" piping / support configurations = -i This change has been evaluated under the TU Electric- l 50.59 procedures per TXX-89718. dated -I September 28, 1989. -i Group: 2 FSAR Change Request Number: 89-701 Related SER Section: 3.7.2; SSER14 App. A .!
SER/SSER Impact: No ' d a 1 l
i 4ttachment to TXX 90011 - January 15, 1990 Page 28 of 304 FSAR Pepe ! (as amended) Descrintion , Table 3.78 1 Description (Clarification) Table is clarified to explicitly delineate that damping values for Balance of Plant (BOP) piping is in accor+ dance with the provisions of Reg. Guide 1.61 or ASME Code Case N 411. Justification: This change provides consistency with other FSAR text discussions concerning the applicable critical damping values and compitance with Reg. Guide 1.61. Group: 4 FSAR Change kequest Number: 89 600.4 Related SER Section: 3.7.1; $$ER21 3.7.1 SER/SSER Impact: No Figure 3.78 41 Descriptions (Addition) Removes Figure 3.78 50A. which was for 2% damping and replaces it with typical response spectra for 3% damp - ing for Category-! buildings. Figures 3.7B 41 through 3.78 500. Justification: See justification for page 3.78 40 (#89 651.2). Groupt 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER Impact: No i Figure 3.78 42 Descriptions (Addition) Removes Figure 3.78-50A which was for 2% damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through 3.78 50C. Justification: See justification for page 3.78 40 (#89 651.2). Groups 3 FSAR Change Request Number: 89 651.3
'Related SER Section: 3.7.2 SER/SSER Impact: No Figure 3.78 43
Description:
(Addition) Removes Figure 3.78 50A. which was for 2% damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through 3.78 50C. Justification: See justification for page 3.78 40 (#89 651.2). Group 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER Impact: No I 1 l
Attachment to TXK 90011 ; January 15, 1990 , Page 29 of 304 , l FSAR Page (as amended) Descrintion l Figure 3.78 44 Description (Addition) Removes Figure 3.78 50A which was for 21 damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through 3.78 50C. Justifications i See justification for page 3.78 40 (#89 651.2). I Group 3 l FSAR Change Request Number: 89 651.3 l Related SER Section: 3.7.2 i SER/SSER Impact: No i Figure 3.78 45 Descriptions (Addition) i Removes Figure 3.7B 50A. which was for 25 damping, and replaces it with typical response spectra for 3% damp-j ing for Category I buildings. Figures 3.78 41 through 3.78 50C. Justification: See justification for page 3.78 40 (#89 651.2). Groups 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER Impact: No Figure 3.78 46 Description (Addition) Removes Figure 3.78 50A. which was for 2% damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through i 3.7B 50C. Justification: See justification for page 3.78 40 (#89 651.2). Group: 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/3SER Impact: No Figure 3.78 47
Description:
(Addition) Removes Figure 3.78 50A..which was for 25 damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through 3.78 50C. Justificaticit: See justification for page 3.78 40 (#69 651.2). Group: 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER Impact: No
AttachmeQt to Txx 90011 : January 15, 1990 i Page 30 of 304 i FSAR Pete f as . ascended) Descrintion j Figure 3.78 48 \ Descriptions (Addition) ' Removes Figure 3.78 50A, which was for 2% damping, and < replaces it with typical response spectra for 3% damp- l ing for Category I buildings Figures 3.78 41 through i 3.78 50C. Justification: See justification for page 3.78 40 (#B9-651.2). ! Group 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 _t
- SER/SSER Impact
- No l
Figure 3.78 49 Descriptions (Addition) Removes Figure 3.78 50A, which was for 2% damping, and replaces it with typical response spectra for 3% damp - ing for Category I buildings, Figures 3.78 41 through 3.78 50C. Justification: See justification for page 3.78 40 (#89 651.2). Groups 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER 1mpact: No Figure 3.78 50
Description:
(Addition) Removes Figure 3.78 50A, which was for 2% damping, and replaces it with typical _ response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through 3.78 50C. Justification: See justification for page 3.78 40 (#89 651.2). Group 3 FSAR Change Request Number: 89 651.3 - Related SER Section: 3.7.2 SER/SSER 1mpact: No Figure 3.78 50A Description (Addition) Removes Figure 3.78 50A, which was for 2% damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings, Figures 3.78 41 through 3.78 50C. Justifications - See justification for page 3.78-40 (#89 651.2). Groups 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SERISSER 1mpact: No
Attachment to TXX 90011 January 15. 1990 Page 31 of 304 FSAR Page 111_seended) DescriDtion Figure 3.78 508
Description:
(Addition) Removes Figure 3.78 50A. which was for 2% damping, and replaces it with typical response spectra for 3% damp. ing for Category I buildings. Figures 3.7B 41 through 3.7B 50C. Justification: See justification for page 3.78 40 (#B9 651.2). Groups 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER Impact: No Figure 3.7B 500 Descriptions (Addition) Removes Figure 3.7B 50A, which was for 2% damping, and replaces it with typical response spectra for 3% damp-ing for Category I buildings. Figures 3.78 41 through 3.7B 50C. Justification: See justification for page 3.7B 40 (#89 651.2). Groups 3 FSAR Change Request Number: 89 651.3 Related SER Section: 3.7.2 SER/SSER Impact: No 3.8 11 Description (Addition) Adds electrical penetration ultrasonic examinations to the list of specific examinations which are performed to the specifications of ASME B&PV Code. Section V. 1974 Justification: Groups 3 FSAR Change Request Number: 89 561.1 Related SER Section: 3.8.1 SER/SSER Impact: No l 3.8 20 Description (Revision) Allows the use of non pressure retaining plates attach- i ed to the containment liner without charpy impact tests ' provided the ellowable loads are established by frac-l ture mechanics analysis and/or the-temperatures during loading are above the N!L Ducitility Transition Temp. Justification: Significant Deficiency. Analysis Report 87 22 and NCR's 89 6559, 89 6807. 89 6718, 89 6719, 89 6721, 89 7045 89 7211. and 89-11616 identified plates attached to the Unit I containment liner which do not have Charpy Impact Tests as required by ASME III. Division 2. Sub-section CC 4543.1. These plates have been evaluated l 9
( l Attachment to TXX 90011 i January 15, 1990 i Page 32 of 304 i
.I FSAR Page f
(as. amended) Descrintion and are technically adequate for the following reasons: f
- 1) Fracture mechanics Calculation 16345 CS(B) 007, R-0, i has established allowable loadings for these plates based on the priciples of fracture mechanics. The gov- t erning normal operating and accident load conditions i are enveloped by these allowables. Test conditions are i addressed below. ;
- 2) Later editions of ASME !!!, Division 2, providt ex- i emptions to impact testing requirements for pressure [
, and non pressure retaining materials provided the serv- ! l ice temperatures are above the Nil Ductility Transi- , l tion Temperature (NDTT) by a prescribed amount. Sub- L section CC 4543.1 of the 1986 Code refers to Subsection ' CC 2500 which. specifies the lowest service temperature ! to be 70 degrees F for A36 plates of the thicknesses ! identified by the above NCR's. The mean temperature during the 1983 SIT /ILRT was 69.0 ; I degrees F. The 1 degree F temperature difference is l l deemed negligible. The 1989 Integrated Leak Rate Test : was conductued at temperatures in excess of 80 degrees F which satisfied the above criteria; future tests will
- be procedurally controlled to maintain temperatures in ;
excess of 70 degrees F. l
. i This FSAR change request has bsen evaluated under the i Td Electric 50.59 procedure per TXX-89718 dated i September 29, 1989.
Group: 2 FSAR Change Request Number: 89 764 : Related SER Section: 3.8.1 SER/SSER Impact: No 3.8 23 Descriptions (Addition) > Adds an exception to the ASME ACI 359 document for lig- , uid penetrant or magnetic particle examination of full r l penetration attachment welds (section CC 5523.1). Justification: The insert plates for the containment liner, which con- [ tain the full penetration attachment welds, were fabri-cated by CB&! in their shop to the requirements of 1 Gibbs & Hill Specification 2323 SS 14. Although CB&l j complied with the specification requirements, the welds ; i were not inspected in accordance with the code as spec- ; ified in the FSAR. ASME ACI Section CC-5523.1, stater
- that all full penetration welds shall be examined by either NT or LP and that all linear indications shall be removed and repaired. This condition was noted in l NRC inspection report 50 445/89 33:50 446/89 33. Add- !
tionally, Amendment 68 of the FSAR stated that only in-dications with major dimensions greater than 1/16" are considered relevant.
Attach ent to TXX 90011 January 15. 1990 Page 33 of 304 FSAR Page (as amended) Descrintion As a corrective action for the deficiency, a program , was established to assess the acceptability of the welds. The program consisted of performing an-inspec- i tion of a portion of the accessible welds to establish an assessment of the overall quality of the welds. i Approximately 107 of the 304 CB&I insert plates are lo-cated below the spring line (E1. 1000' 6) with the re-mainder located in the dome region of the containment liner. Of the 107 plates below the spring line, approx- ; imately 18% of the total length of welds on the plates remains accessible due to completion of fabrication and I other construction activities. Since the welds for the ! 304 plates were made in a shop environment using the . ! same welding procedure and were visually by CB&I's OA Welding Supervisor the welds would have a similar ; quality. Therefore, the inspection of the accessible i' I portions of the welds below the springline (E1. 1000'- 6") provides a reasonable assessment of the overall quality of the welds. The accessible welds (approxi-mately 18% of the total length of welds for the plates located below the springline) were examined by the MT method. The examinations found three relevant indica- ; tions (1/8", 1/4", and 1/2"). A fracture mechanics ~ evaluation established that (Continued on 89 587.2) , Group: 2 FSAR Change Request Number: 89 587.1 , Related SER Section: 3.8.1 ' SER/SSER Impact: No i 3.8 23 Descriptions (Addition) Continued from FSAR Change Request Numer 89 587.1. Justification (Continued from 89 587.1) linear indications in the insert plate full penetration attachment welds less than or equal to 1/2" long are acceptable based on the weld joint configuration, materials. stress state, cyclic loading, and worst lo-cation-of postulated defects. The MT inspection and results were discussed in NRC inspection report 50 445/ 89 48:50 446/89-48. NRC inspection report 50 445/89-;3: 50 446/89 53 verified that GA was involved in the orig-inal' visual inspections for the insert plate attachment welds. The Structural Acceptance Test and the Integrated' Leak Rate Test provide additional evidence that the welds are free of in11 cations that could affect the liner's structural and leak tight functions. The results of the above analysis'and inspections re-solves the deficiencies regarding the subject CB&I in-
Attachment to TXX 90011 January 15, 1990 Page 34 of 304 FSAR Pepe (as amended) Descrintion sert plates. All present and future modifications to the liner plates (including CB&! plates) will be per-formed in accordance with the existing licensing com-mitments. This FSAR change request has been evaluated under the TV Electric 50.59 procedure per TXX 89718 dated September 28, 1989. As a result of subsequent discussion with the NRC staff a calculation has been performed to provide a statisti-cal confidence level that no unacceptable cracks are in unexamined portion of plant. Also an evaluation has determined a critical crack length of 1" for the insert plate full penetration attachment welds. Group: 2 FSAR Change Request Number: 89 587.2 Related SER Section: 3.8.1 SER/SSER 1mpact: No 3.8 55 Description (Revision) Changes the number of startup/ shutdown cycles from 120 to 200 during the 40-year life of the plant. Justification: As a result of design validation activities it was determined that the plant is likely to experience 5 startup/ shutdown cycles per year, or 200 cycles during a 40 year life. Group 3 FSAR Change Request Number: 88 936 Related SER Section: 3.8.1 SER/SSER Impact: No 3.8 72 Descriptions (Clarification) Clarifies that ANSI /ANS 56,8 1987 is utilized only to calculate the leakage rate using the mass-point method with the exceptions as noted in the FSAR. Justification: This LDCR will resolve concerns identified during the NRC structural audit at CPSES during Sept. 6 7, 1989. Group: 4 FSAR Change Request Number: 89 651.4 Related SER Section: 3.8.1: SSER12 6.2.5 SER/SSER Impact: Yes CPSES calculates the leakage reates for the ILRT using the mass / plot method of ANSI /ANS 56.8 1987, the 1987 version (for mass / plot method) has been accepted by the NRC in the _ Federal Register. Volume 53. l No. 220, page 43890. l i i 1 l j
Attachment to TXX 90011 January 15, 1990 i Page 35 of 304 l l l FSAR Page l j (as. amended) Asscrintion !
- 3.8 78
Description:
(Addition) i Adds statement to clarify that a full penetration butt l weld in the electrical penetration assemblies may be examined by ultrasonic plus liquid penetrant methods i instead of radiography. ' Justification: NE 5231.1 states that ultrasonic. examination plus i liquid penetrant method may be used in lieu of radio- i graphy for inacce.ssible non category welds. NE 5211 specifies radiographic testing for Category A&8 welds, , so the exception for non category. welds is not applic- T able strictly according to the Code. However, the use : of the exception was accepted for this particular app- ! lication by IR 89 38. This change has been evaluated under the TV Electric f 50.59 procedures per TXX-89718, dated : September 28, 1989. 1 Group: 2 i FSAR Change Request Number: 89 561.2 ; Related SER Section: 3.8.1 SER/SSER impact: No ; 3.8 82 Descriptions (Correction) [ Deletes sentence concerning local plastic deformation. [ Justification: [ This LDCR will resolve concerns identified during the NRC structural audit at CPSES during Sept. 6 7, 1989. : Due to hardware modifications, the statement describing ' local plastic deformation is no longer applicable. + Group: 7. FSAR Change Request Number: 89 651.5 j Related SER Section: 3.8.2 SER/SSER 1mpact: No . 3.8 138
Description:
(Editorial) # Corrects tne document identification number from r
" TID 7021" to TID 7024" for reference 21 at the end of !
Section 3.8. Justification: Ninor editorial change to correct a typographical ! error, Group: 4 ; FSAR Change Request Number: 89 752.1 ! Related SER Section: 3.B.3 SER/SSER Impact: No , Table 3.8-1 See Sheet No(s):03 -
Description:
(Editorial) ; Corrects the allowable stress from "126" to ".126" for l the Refueling Water Storage Tanks and the Condensate , Storage Tanks. Justification i
?
Attachment to TXX 90011 . ! January 15, 1990 ' Page 36 of 300 l l FSAR Page I (as amended) DesertDtion i 3,9N 26, 27 Description (Correction) ) NASTRAN and STRUDL computer codes are utilized for J modeling the reactor vessel supports and steam generat- l or lower beam support respectively. j Justifications e Correction is incorporated to reflect the computer code , utilized for analysis of reactor vessel supports and ' steam generator lower beam. The results of these l analyses have been provided by previous FSAR amendments ! 76 and 77. i Group 3 FSAR Change Request Number: 89 713.1 Related SER Section: 3.9.1: SSER12 3.9.1 SER/SSER Impact: No 3.9N 41, 42 Description (Correction) NASTRAN and STRUDL computer codes are utilized for modeling the reactor vessel supports and steam generat-or lower beam support respectively. Justification: Correction is incorporated to reflect the computer code 1 utilized for analysis of reactor vessel supports and l steam generator lower beam. The 'results of these analyses have been provided by previous FSAR amendments 76 and 77. Group: 3 FSAR Change Request Number: 89 713.2 Related SER Section: 3.9.1; SSER12 3.9.1 SER/SSER Impact: No 9 d 4
t Attachment to TXX 90011 i January 15, 1990 ? Page 37 of 304 ! FSAR Page * (as amended) Description l l 3.9N 107 Description (Revision) f I Installation of wear sleeves on reactor vessel bottom ! mounted instrumentation columns to minimize BMI flux [ thimble utar. ; Justifications ; This modification addresses concerns raised by NRC i Bulletin 88 09. A Westinghouse study con:1uded that i reducing the clearance between the flux thimble and Lower Internals Instrumentation Column reduces Thimble ! Noise and reduces wear rate of the thimble. ! Groups 3 i FSAR Change Request Number: 89 556 ; SER/SSER Impact: No ! l 3.9N 120 Descriptions (Addition) ! NASTRAN and STRUDL computer code references are incor-l' porated into section 3.9% list of references.. Justifications ; References added provide supporting documentation for computer code versions and apppropriate technical in-structions. Group: 3 FSAR Change Request Number: 89 713.3 - Related SER Section:-3.9.1: SSER12 3.9.1 ! SER/SSER Impact: No Table 3.9N 10 See Sheet No(s):1 and 2 f Descriptions (Correction) ' Corrected valve types for-tag numbers 8100. 8110. 8111 . 8112 and 8351 A/8/C/D to globe valves consistent with the equipment specification. Justification: Table is corrected to accurately reflect active valve information as provided in the equipment specification. Group: 4 FSAR Change Request Number: 89 646.1 : Related SER Section: 3.9.6 $$ERI 3.9.6 ; SER/SSER Impact: No j Table 3.9N 10 See Sheet No(s):3 l
Description:
(Correction) , Corrected table listing of valves FCV 610 and FCV-611 '; valve sizes from 2" to 3" consistent with the equipment specification. Justification: Table is corrected to accurately reflect active valve '; information as provided in the equipment specification. Group: 4 i FSAR Change Request Number: 89 646.2 Related SER Section: 3.9.63 SSER1 3.9.6 SER/SSER Impact: No -
, _ _ _ . _ . . _ . _ _ . _ . . ._ ,. _ , _ _.._.- ~,
Attachmont to TXY 90011 Jan3ary 15. 1990 Page 38 of 304
)
i FSAR Page t (as amended) Description l This change corrects a typographical error from the l amendment 77 process and resolves an NRC question from : the CPSES structural audit during September 6 7. 1989. : i Group: 4 i FSAR Change Request Number: 89 752.2 Related SER Section: 3.8.3 fi SER/SSER Impact: No I i 3.98 26 .
Description:
(Update) An update is provided that details the usage of ASME ' Code Case N 397 is not used for non NSSS scope piping i analysis and that any future use will be detailed in , the FSAR and in compliance with NRC requirements for ; usage. ~ Justification ! This update is provided to comply with the provisions f specified by the NRC in granting the approval for usage ; as stipulated by SSER 21. Group: 3 i FSAR Change Request Number: 89 586.3 Related SER Section: 3.7.1 SSER21 3.7.1 SER/SSER Impact: No r 3.98 26
Description:
(Addition) ' Added the required details concerning usage of ASME l Code Case N 318 by reference to a new table. Justification: In accordance with the provisions of Regulatory Guide 1.84. the required details are provided by reference to a new table. Group: 3 i FSAR Change Request Number: 89 682.1 Related SER Section: 3.9.3 SER/SSER Impact: No 3.9B 43 Description (Clarification) Instrument impulse tubing support design criteria is clarified to explicitly state that only in a seismic category I structure are tubing supports seismically designed. , 1 Justification: J Instrument tubing in a non seismic building can not be , seismically supported since no floor response spectra I exist for the structure and no credit is taken for the i structure to survive an SSE. Group: 4 FSAR Change, Request Number: 89 549.1 Related SER Section: 3.9.3: SSER14 4.3.1 SER/SSER Impact: No l I i J l
__ . .__ _ ._ . ~ _ _ _ _ _ _ _ _ _ _ ___ _ _ Attachment to TXX 90011- ; January 15o 1990 Page 39 of 304 , t l FSAR Page I (as amended) Descrintion 3.9B 43, 44
Description:
(Clarification) l The design requirements for the analysis of instrument l tubing and the design of support tubing as previously ' l delineated by item c is corrected to specifically ad-dress the design requirements for the tubing and tubing ! l supports separately. Justification: l The correction is made to explicitly establish, in note :
- 1. that the design' criteria for instrument tubing anal- '
ysis is in accordance with the provisions of ASME III : ecuations 8 thru 11 and that instrument tubing supports , are in compliance with the provisions of AISC.-.The cor- ! rection is consistent with FSAR Table 17A 1 entitled, t
" List of Quality. Assured Structures. Systems And Com - i ponents" note 41 pertaining to instrument tubing and l-tubing support criteria. This change provides con- i j sistency with TU Electric specification entitled. ,
" Installation of Piping. Tubing and Instrumentation" which was reviewed by the NRC at documented by Supple-ment 17 to the Safety Evaluation Report section 4.3.2. l Group: 4 FSAR Change Request Number: 89 549.2 Related SER Section: 3.9.3: SSER17 4.3.1 SER/SSER Impact: No :
3.98 46 Description (Addition) Reference is added which provides NRC evaluation for the acceptability of CPSES. usage of Code Cases N 397 and N 411 along with requirements that must be satis ' . fied if the Code Cases are utilized. Justification: The reference is provided to explicitely denote the source of NRC acceptance and implementing requirements S that must be satisfied in order to utilize the Code Cases. Group: 4 ,. FSAR Change Request Number: 89 586.4 Related SER Section: 3.7.1; SSER21 3.7.1 i SER/SSER Impact: No Table 3.98 1F See Sheet No(s):1 and 2 Oescription (Addition) [ Added the required details concerning usage of ASME ,
. Code Case N 318 .
Justification: In accordance with the provisions of Regulatory Guide 1.84, the required details are provided in the table. . Groups.3 ' FSAR Change Request Number: 89 682.2 Related SER Section: 3.9.3 - SER/SSER Impact: No
. - . _ _ _ . - _ _ _ _ _ _ - . _ _ _ _ _ =
'Attachmont to TXX 90011 January 15. 1990 Page 40 of 304 i FSAR Page (as amended) Descrintion ;
Table 3.98-10 See Sheet No(s):14 l
Description:
(Correction) Corrections are made for valves HV 4708 and HV 4701 valve type listed to " Gate / Motor" consistent with the i equipment specification. ; Justifications i l Table is corrected to reflect complete and accurate in- ? i formation consistent with the equipment specifications, i I Group: 3 , j FSAR Change Request Number: 89 602.1 ' Related SER Section: 3.9.6; SSER1 3.9.6 l SER/SSER Impact: No I i Table 3.98 10 See Sheet No(s):16 and 17 . Descriptions (Addition) ! Eight Component Cooling Water 2" check valves are added , to the active valve list to ensure that the Reactor Coolant Pump Thermal Barrier Cooler is prevented from back flow to upstream piping upon' postulated thermal , barrier rupture. i Justification: . l Addition of the eight check valves reflects the active function that the component cooling water valves pro-l vide in the mitigation of radiological releases outside containment upon postulated rupture of the thermal bar-rier. Groups 3 FSAR Change Request Number: 89 602.2 i Related SER Section: 3.9.6; SSER17 4.4.2 i SER/SSER Impact: No i Table 3.9B-10 See Sheet No(s):17
Description:
(Addition) Four Component Cooling Water 1/2" check valves are ' added to the active valve list to ensure Instrument Air l Accumulator at the Safety Chiller regulating valve is not compromised. Justification: Addition of the check valves to the valves list reflect their active function in preventing the loss of air operated valves considering single failure criteria. t Group 3 FSAR Change Request Number: 89 602.3 ' Related SER Section: 3.9.6; SSER17 App. A SER/SSER Impact: No , Table 3.98 10 See Sheet No(s):17 4
Description:
' ( Revi si on) ! Removal of Station Service Water rectreulation line a control valves, associated piping and orifices. Justification:
- Deleted the SSW recirculation valves from<the active !
_ . - _ _ w#-- , < , - , . r_ y r -,
-. . . . . -. . _ - - .- -. ~
Attachmnt to TXK-90011 'l' January 15, 1990 Page 41 of 304 i FSAR Page (as amended) Descrintion i valve listing. Since the recirculation line has been blind flanged and prohibits flow, these valves no t longer have an active function. This change was ; evaluated under the TU Electric 50.59 process as ! described in TXX 89718 dated 9/28/89. ! Group: 2 FSAR Change Request Number: 89 782.5 l Related SER Section: 9.2.1 SER/SSER Impact: Yes ' SER section 9.2.1 indicates that the recirculation are , provided for testing of SSW components which is no longer true. : Table 3.9B 10 See Sheet No(s):21 Description (Addition) -i Four diesel generator fuel oil system check valves have ! been added to the active valve list to provide as- l surance that the starting air pressure boundary is not ! compromised. ' Justification: ' Valves are added to the active valve list that are de- l pended upon to provide.an active function, taking into
~
l account single failure considerations. ,. Group 3 . FSAR Change Request Number: 89 652 Related SER Section: 3.9.63 SSERI 3.9.6 SER/SSER Impact: No - Table 3.98 10 See Sheet No(s):24
Description:
(Correction) Corrects the valve type of two valves listed. Valves ; XHV 5579 and XHV 5580 are butterfly valves, not gate ' valves. Justification: ' The valve type of valves XHV-5579 and XHV 5580 is i corrected: they are butterfly. valves, not gate valves. ! The valve type of these valves is changed as a result of a review of the referenced specification. Group: 3 ,t FSAR Change Request Number: 89 536.3 Related SER Section:'3.9.6: SSER1' 3.9.6 SER/SSER Impact: No , Table 3.98-10 See Sheet No(s):24
Description:
(Addition) . Four Safeguards. Building Sump check valves are added to the active valve list to ensure that performance'of { sump pumps is not jeopardized while mitigating the con- l sequences of moderate energy cracks or high energy line l breaks. Justification:.
- Addition of the check valves to the active valve list +
-t
Attachment to TXX 90011 . January 15. 1990 , Page 41A of 304 ; FSAR Page (as amended) Descrietion ; reflect the active function of the valves, located on i the sump pump discharge side. in mitigating the conse-
- Quences of potential flooding.
Groups 3 : FSAR Change Request Number: 89 657 Related SER_Section: 3.6.2: $$ER6 3.6.2 SER/SSER 1mpact: No i Table 3.98 10 See Sheet No(s):24 Descriptions (Addition) Valve added to active valve list. Justification: ' Valve VD 0907 is added to the active valve list to re-flect that it may be required to perform pressure , relief during containment isolation. Groups 3 FSAR Change Request Number: 89 677 Related SER Section: 3.9.6; SSER 1 3.9.6 1 SER/SSER 1mpact: No I i
+
h t e
Attachment to TXX-90011 > January 15, 1990 l Page 42 of 304 i i l FSAR Page } (as amended) Descriction l 3.118 12
Description:
(Clarification) Periodic testing of control and electrical equipment
- Justification:
Clarification of the text by referencing the applicable [ FSAR sections which specifically define the scope ! of CPSES compliance to IEEE 279 and IEEE-338. Group: 4 l FSAR Change Request Number: 89 631 ! Related SSER Section: SSER6 3.11.3 ! SER/SSER Impact: No l l 3A-2 4 Descriptions (Correction) l Environmental Qualification Report CPSES Qualification Report CPSES Qualification Maintenance [ Program Justification: _ Revised the text to better describe the CPSES '. Procurement Program as it relates to Environmental ; Qualification. The explanation of " exact replacement part" was clarified to reflect that an acceptable , part is one that satisfies the original design basis. Groups 3 . FSAR Change Request Number: 89 622.1' , Related SSER Section: SSER6 3.11.3.3 l SER/SSER Impact: No
- Table 3A-4-1 See Sheet No(s):01 thru 36
Description:
(Update) Environmental Qualification Class.1E Equipment ' Located in a Potentially Harsh Environment
~ ,
Justification: r Deleted Table 4 1. The specific environmental details , are updated and controlled in CPSES documents, such as the E0 packages, E0 master list, and design basis ; document (s). Group: 3 , FSAR Change Request Number: 89 622.2 Related SSER Sectio-' SSER6 3.11.3.3 ; SER/SSER Impact: No Figure 3A 4 1 Description (Update) Environmental Qualification - Class-1E Equipment 3 Located in a Potentially Harsh Environment Justification: , Deleted Figure 41. The' specific environmental details are updated and controlled in CPSES documents, such as ; the-E0 packages, E0 master list, and design basis document (s). l Group: 3 . _ i FSAR Change Request Number: 89-622.3 Related SSER Section: SSER6 3.11.3.3 SER/SSER Impact: No- [
- - e w , - - - - -c,, --
Attachment to TXX 90011 : January 15. 1990 . Page 43 of 304 5 FLAR Page f (as amended) Description ; l Figure 3A 4 2 Descriptions (Update) Environmental Qualification Class IE Equipment l Located in a Potentially Harsh Environment ' (Appendix 3B is Justification: located at the- Deleted Figure 4 2. The specific environmental details end of Chapter are updated and controlled in CPSES documents, such as :
- 17) the E0 packages, E0 master list, and design basis document (s). !
Group 3 l FSAR Change Request Number: 89 622.4 ! Related SSER Section: SSER6 3.11.3.3 , SER/SSER Impact: No i 4.3 3, 10 Description (Editorial) i Editorial corrections ; Justification l During word processing. portions of sentences were
- inadvertantly omitted from the FSAR. The sentences ;
are restored to their original versions, i l Group: 4 l , FSAR Change Request Number: 89 685.7 i SER/SSER Impact: No & 4.3 28 Description (Clarification) i Nuclear Design Clarification of effect of fuel densification on linear power density. ! Justification: ' The linear power density including the effects of fuel densification is 5.45 kW/ft. The value without the effects of fuel densificativ,is 5.43 kW/ft. Group: 4 FSAR Change Request Number: 89 685.1 Related SER Section: 4.3 ' SER/SSER Impact: No 4.3-70
Description:
(Clarification) Nuclear Design Use of Hafnium in RCCA's Justification , Statement clarified to eliminate possible confusion. l The section states that Hafnium and An In Cd have apprstimately the same reactivity worth and is not j meant to indicate which particular material will be ' used in CPSES. Section 4.2.2.3.1 discusses the materials to be used in CPSES. Group 4 FSAR Change Request Number: 89 685.6 > Related SER Section: 4.3 SER/SSER Impact: No i i
Attuchment to TXX 90011 1
- January 15. 1990 ;
Page 44 of 304 { I I FSAR Pope 9 (as. amended) Description j l Table 4.3 1 See Sheet No(s):01 !
Description:
(Update) ! Nuclear Design Active Core Zircaloy Weight Justification: i Provide a more representative value for the weight of & Zircaloy in the core and clarify that it corresponds ! to the active core region, i Group: 4 ; FSAR Change Request Number: 89 685.3 ! Related SER Section: 4.3 ; SER/SVlR Impact: No : Table 4.3 2 See Sheet No(s):01 l Description (Clarification) ' Nuclear Design Clarification of effect of fuel ! densification on linear power density. [ Justification: ' See description for page number 4.3 28. Group 4 , FSAR Change Request Number: 89-685.2 ^ Related SER Section: 4.3 SER/SSER Impact: No Table 4.3-2 See Sheet No(s):03 '
Description:
(Correction) ' Nuclear Design - Boron Concentration j Justification: Update the zero power boron concentration at cold conditions with Rod Cluster Control Assemblies inserted , to a more representative value. Group: 3 FSAR Change Request Number: 89 685.4 ; Related SER Section: 4.3 SER/SSER Impact: No ' Table 4.3 3A See Sheet No(s):01 and 02 4 Description (Correction) Nuclear Design - Correct total control requirements ! Justifications The total reactivity control requirements should equal ( the sum of the individual control requirements: Ocppler. Noderator temperature. Redistribution, and ; Rod Insertion Allowance. End of-Life (Equilibrium Cycle) value corrected so that the sum is the correct value. Group: 4 FSAR Change Request Number: 89 685.8 l SER/SSER Impact: No i i a *- - _ m +ma -*. . _-_.-_m.- . _ _ _ _ _ _ . _
Attachment to TXXoC0011 I January 15, 1990 i Page 45 of 304 { i i FSAR Page (as amended) Description ; l Table 4.3 3B See Sheet No(s):01 and 02 i Description (Correction) ' Nuclear Design - Correct total control requirements Justification: The total reactivity control requirements should equal i the sum of the. individual control requirements; i ! Doppler, Nederator temperature; Redistribution, and Rod Insertion Allowance. End of Life (Equilibrium l Cycle) value corrected so that the sum is the correct i i value. t Group: 4 r FSAR Change Request Number: 89 685.9 i SER/SSER Impact: No ! Figure 4.3 5A
Description:
(Clarification) ! Justification: ! Referenco degrees 90 and 270 were inadvertantly left i off in the last update to this figure, ! Group: 4 ! FSAR Change Request Number: 89 685 Related SER Section: 4.3 SER/SSER Impact: No 4.4 5, 12 See Page No(s):35, 36, 42 i Description (Revision) i Remove references to three loop operation. i Justification: CPSES will not be licensed for three loop operation: I therefore, all references to three loop operation are ' removed. Group 3 FSAR Change Request Number: 89-690.1 SER/SSER Impact: No 4.4-57
Description:
(Clarification) Justification: , Cpses uses N 16 in place of delta T, therefore title was corrected to identify N 16 instead of delta T. Group: 4 FSAR Change Request Number: 89 690 Related SER Section: 4.4 l SER/SSER Impact: No Table 4.4 2
Description:
(Revision) Remove references to three loop operation. Justification:
~
CPSES will not be licensed for three loop operation; therefore, this Table is deleted. Group: 3 > FSAR Change Request Number: 89 690.2 SER/SSER Impact: No P 9
Attachment to TXX 90011 January 15, 1990 - Page 46 of 304 r FSAR Pepe (as amended) Description
?
l Figure 4.4 5A, 6A See Sheet No(s): Figure 4.4 7A , Description (Clarification) l Justification: [ Figures are applicable to Unit 1 only. Title block : corrected to reference Unit 1 only. ! Group: 4 FSAR Change Request Number: 89 690 t Related SER Section: 4.4 ; SER/SSER Impact: No : t Figure 5.1 1 See Sheet No(s):01 Descriptions (Correction) ; Add locked open notation (LO) to valve 1 8085 of the i figure. > Justification: : LO notation is being added to the valve to match the as built status of the system and to reflect the locked - valve criteria identified during a review of locked valve requirements.
- Group: 3 ,
FSAR Change Request Number: 89 619 Related SER Section: 9.3.4 SER/SSER lapact: No I i i Figure 5.1 1 See Sheet No(s):01 t Descriptions (Correction) Justification: ' Revises Fig. 5.1 1, Sh. I to reflect the installation of a pressure transmitter (PT 3616) for monitoring the the RCS pressure. The addition of a pressure ; transmitter meets the requirements of Reg. Guide 1.97. Group: 3 FSAR Change Request Number: 89 714 Related SER Section: 7.5.1 SER/SSER Impact: No
- Figure 5.1 1 See Sheet No(s):02
Description:
(Update) Minor figure updates. Justification: l No justification necessary. These figures contain i changes of the following type:
- 1. Manual vent or drain valves - addition, removal, re-location, valve number. ;
- 2. Manways or handways addition, removal, or re- 1 location.
- 3. Editorial - spelling, editorial or draf ting errors which cannot impact technical meaning of the diagram
- 4. Line numbers or line sizes.
- 5. Flanges or reducers - addition, removal- or re-location.
- 6. Piping or instrumentation - physical interconnection
[ Attachment to TXX 90011 ; January 15, 1990 : Page 47 of 304 . i FSAR Page ! (as amended) Description f changes which have no impact on the operation /func- i tion of system and equipment. l i 7. Manual valves valve numbers or physical location } changes which have no impact on the operation /func- l tion of system and equipment. .
- 8. Elevation changes.
Group: 4 ! FSAR Change Request Number: 89 732 I SER/SSER Impact: No 5.2 8 Descriptions. (Clarification) ! Justification: . i Modify the sentence describing COMS as being required i only during low temperature, water solid operation to = clarify that this is a design requirement, not an operations requirement Group: 4 ; FSAR Change Request Number: 89 656.1 t i
-Related SER Section: 5.2.2.2; SSER01 5.2.2.2 SER/SSER Impact: No 5.2 8 Description (Correction)
Justiffcations i correct the statement that COMS is manualy activated to
- state that it is automaticaly activated. This is -
consistent with the as designed, as-built status of the ! system. ! Groups 3 FRAR Change Request' Numbers- 89 656.2 L ;ated SER Section: 5.2.2.2: SSER01 5.2.2.2 ; SER/SSER Impact: No 5.2 52
Description:
(Clarification)- Clarifies the description of the RCPB leakage detection system capabilities to respond to one gpm leakage t increase in one hour' or less required by Reg. Guide i 1.45. May 1973. ! Justification: To provide a clearer description since the current " description may cause confusion or misinterpretation regarding the ability of the containment sump level , instrumentation to detect one gpm leak in one hour. Group: 4 FSAR Change Request Number: 89-441 Related SER Section: 5.2.5 SER/SSER Impact: No Figure 5.2-2 See Sheet No(s):01 and 02 Description (Correction) Revises RCS heatup curves. . Justification: The figures are updated to incorporate the Unit I heat-i I
Attach::nt to TXX 90011 January 15. 1990 t Page 48 of 304 l
)
FSAR Page '! (as amended) Descrintion j i' up and cooldown curves based on Regulatory Guide 1.99 Rev. 2. This revision was inadvertently omitted during printing of Amendment 76, although it was described / justified in TXX 89201 page 35 of 439. The Unit I curves form part of the Technical Specifications and were transmitted to the NRC in TXX-89134 on 3/10/89 Groups 3 FSAR Change Request Number: 89 634 Related SER Section: 5.3.2 SER/SSER Impact: No Figure 5.2-3 See Sheet No(s):01 and 02 Description (Correction) Revises RCS Cooldown curves. Justification: See justification under Figure 5.2 2. Group 3 FSAR Change Request Number: 89 634 Related SER Section: 5.3.2 SER/SSER 1mpact: No 5.3 24
Description:
(Revision) This change is required to clarify accessibility for examination of closure head of the reactor vessel during inservice surveillance. Justification: This change is to clarify that the closure head of the , reactor vessel is accessible for inservice surveillance examination during refueling. The high stress area of the head to flange transition is examined (ultrasonic, magnetic particle) in accordance with the requirements of ASNE Section XI. This change provides consistency with the rest of the section by indicating accessibility for examination. Group: 3 FSAR Change Request Number: 89 796 SER/SSER Impact: No 5.4-52. 64 See Page No(s):66 Descriptions (Clarification) Justification: Clarifles that one valve in each of the RHRS suction lines is de-energized to prevent spurious actuation. This clarification has been discussed on page 4 of 7 in TXX 6582 dated 8/4/87 and reviewed in Inspection Report 50/445/87 22 dated 1/12/88. This change is consistent with that discussed on page 9 9 in SSER #12. Group: 4 FSAR Change Request Number: 88 536.1 Related SSER Section: SSER12 9.5.1.4 SER/SSER Impact: No
AttachCent to TXX 90011 ! January 15. 1990 ! Page 49 of 304 ; i FSAR Page (as amended) Descrintion j f Table 5.4 8
Description:
(Correction) ! Justifications ! Corrects the Residual Heat Removal pump power from 400 ! 450 hp. This change is consistent with FSAR Tables ! 8.3.1A (Sheet 3) 8.3 18 (Sheet 3) 8.3 2 (Sheet 7) and , equipment specifications. l Group: 3 ! FSAR Change Request Number: 89 632 i Related SER Section: 5.4.3 ' SER/SSER Impact: No l Figure 5.4 6
Description:
(Correction) ! Deletion of locked closed (LC) and locked open-(LO) notation, addition of 1ccked open (LO) notation, and addition of notation indicating that a valve will be > sealed closed in modes 14. for selected valves in the , figure. I Justification: ' In response to en observation by INPO concerning i excessive numbers of locked valves, TV Electric i reviewed requirements for locked valves and identified valves which were not required to be locked. Locked - notation for these valves are being deleted. Locked -; notation is being added for selected valves to match the as built status of the system and to reflect the ; locked valve criteria identified during the review of the locked valve requirements. A valve which is sealed l closed is closed by' administrative controls using some methods to maintain in that position. ' Groups 3
- FSAR Change Request Number: 89 633 +
Related SER Section: 5.4.3 SER/SSER 1mpact: No I SA 7 Descriptions (Correction) Deletes specific volume related to the Condensate Storage Tank in Section 5A.!!.1 and references Section ' 10.4.7.2. Justification: ' Details regarding the_ Condensate Storage Tank are more appropriately discussed in FSAR Section 10.4,7.2. This change will eliminate any unnecessary future changes to - FSAR Section SA.i!.1. l Group 3 FSAR Change Request Number: 89 426.1 , Related SER Section: 5.4.3
- SER/SSER Impact: Yes ,
The statement in the last paragraph of SER page 5 19 discussing the minimum reserve volume in the Condensate ; Storage Tank should be clarified for consistency with FSAR Section 10.4.7.2. l I
Attachm:nt to TXX 90011 J ar.u a ry 15, 1990 , Page 50 of 304 l FSAR Pepe . (as amended) Descrintion ; SA 8, 9 Description (Editorial) Justification: The changes are made to provide minor editorial changes and correct typographical errors. Group: 4 FSAR Change Request Number: 89 474.1 Related SSER Section: SSER6 5.4.3 SER/SSER Impact: No 5A 15
Description:
(Editorial) Justification: Removes the words "from the control room" consistent with the changes described for pages 5.4 52, 64 and 66. Group: 4 FSAR Change Request Number: 88 536.2 Related SSER Section: SSER12 9.5.1.4 SER/SSER Impact: No i SA 17 Descriptions (Editorial) Justification: The changes are made to correct the typographical I errors associated with the valve numbers. Group: 4 l FSAR Change Request Number: 89 474.2 i Related SSER Section: SSER6 5.4.3 SER/SSER Impact: No Table 6.1B 4 Descriptions (Revision) RWST volume is revised to be consistent with revised calculation resulting from corrections in the calcula-tion for referenced levels. Justification: See justification provided for Table 6.5-3. Group: 2 FSAR Change Request Number: 89 683.01 Related SER Section: 6.5.2 SER/SSER Impact: No Table 6.18 4 Description (Revision) The upper limit for boron concentration in the RWST is increased from 2100 to 2200 ppm for operational-flexibility. Justification: See justification provided for Table 6.5 3. Group: 2 FSAR Change Request Number: 89 683.02 Related SER Section: 6.5.2
Attachment to TXX 90011 [ January 15. 1990 -! Page 51 of 304 l FSAR Page I (as amended) Description j t SER/SSER !apact: Yes The boron concentration described in SER section 6.5.2 page 6 22 is not consistent as a result of this change. { l; Table 6.1B 4 Description (Revision) & Corrects the boron concentration for the RCS as a i result of revised calculation. A more realistic boron
- concentration is used in the calculation in lieu of the '
bounding maximum concentration. i Justifications i See justification provided for Table 6.5 3. Group: 2 FSAR Change Request Number: 89 683.03 Related SER Section: 6.5.2 ' SER/SSER Impact: No l l Table 6.18 4
Description:
(Revision) The Safety Injection accumulator volumes are corrected to properly account for the low lower head water volume of the accumulator. ( Justification: - See justification provided for Table 6.5-3. ; Group: 2 ! FSAR Change Request Number: 89 683.04 ; Related SER Section: 6.5.2 SER/SSER Impact: No I Table 6.1B-4 Descriptions (Revision) Justification: The upper limit for boron concentration in the Safety Injection (SI) accumulators is increased from 2100 to
- 2200 ppm to correspond to the maximum boron concentra- i tion in the RWST. This increase will avoid unnecessary operator action for dilution since the 51 accumulators ;
are filled with water from the RWST. This change has been evaluated under the TU Electric 10 CFR 50.59 process as described in TXX 89718, dated 9/28/89. Group: 2
- FSAR Change Request Number: SA 89 803 Related SER Section: 6.3.2 SER/SSER Impact: No 6.2-59
Description:
(Revision) Revised Containment Spray System (CSS) piping design , i bases to conservatively consider the dynamic effects r r from fluid transients due to CSS operation. I Justification: The consideration of the dynamic effects of CSS opera-tion does not assume SSE evaluated loads bound CSS i loads due to normal operation. Group: 3 FSAR Change Request Number: 89 600.3
Attachment to TXX 90011 Ja2uary 150 1990 i Page 52 of 304 i e FSAR Page ; (as amended) Descriction i Related SER Section: 6.5.2 SSER3 3.9.3.1 ! SER/SSER 1mpact: No 6.2 59
Description:
(Clarification)
- Justification: .
The bases for determining the use of pipe whip ; restraints to protect the CSS from withstanding the ! effects of postulated pipe rupture is clarified to be consistent with FSAR section 3.68.1.3 and APCSB 3 1. Group: 4 l FSAR Change Request Numbert SA 89 864 i Related SER Section: 3.6.2 ! SER/SSER Impact: No , 6.2 60 Description (Clarification) . Justifications ! Adds " header discharge" to clarify the valves opened on ! a 'P' signal. , Group: 4 t FSAR Change Request Number: 89 504.01 ; Related SER Section: 6.2.2 + SER/SSER Impact: No l' 6.2 60, 61 Description (Editorial) Justifications
- Correct table referenced for CSS initiation parameters !
and rencves discussion of the chemical additive system ' from section 6.2.2. since it is more appropriately l included in section 6.5.2.2.1. ' Group: 4 FSAR Change Request Number: 89 504.02 Related SER Section: 6.5.2 SER/SSER Impact: No i 6.2 64 Descriptions (Editorial) Justification: - Adds a cross-reference for the description of spray -) header nozzles. , i Group: 4
- l FSAR Change Request Number: 89 504.03 ,
Related SER Section: 6.2.2- .i SER/SSER 1mpact: No 6.2-64 Descriptions (Editorial)- Justification: Deletes redundant design description of spray nozzles ' since this information is contained in Table 6.2.2-1. Group: 4 , FSAR Change Request Number: 89 504.04 l Related SER Section: 6.2.2 SER/SSER Impact: No
t Attachment to TXX 90011 January 15, 1990 Page 53 of 304 3 FSAR Pope (as_ amended) Descrintion 6.2 64
Description:
(Clarification) Justification: Add description of applicable standards for the spray nozzles, to make this section more complete. This information is consistent with FSAR section 6.5.2.2.3. Group: 4 FSAR Change Request Number: 89 504.06 Related SER Section: 6.2.2 SER/SSER Impact: No 6.2 72
Description:
.( Clarification)
Justification: Clarifies a design assumption used in implementing the regulatory guide. . This clarification is consistent with the regulatory guide. FSAR subsections 6.2.2.1 and 6.2.2.2.1 and SER section 6.2.2 and Appendix C. Group: 4 FSAR Change Request Number: 89 722 Related SER Section: 6.2.2 SER/SSER Impact: No 6.2 73 Descriptions (Clarification) Justification: Clarifies the amount of anti + sweat insulation calculat-ed to be able to reach the sumps as a result of a high energy line break. The previous description involved the total amount of anti-cweat-insulation contained in Containment. Group: 4 FSAR Change Request Number: 89 722 Related SER Section: 6.2.2 SER/SSER Impact: No 6.2 75 Descriptions (Clarification) Justification: Clarifies the examination methods to be used during inservice inspection of the Containment Spray System i and cross references the FSAR section which provide j further details, i Group: 4 FSAR Change. Request Number: 89 744 Related SER Section: 6.2.2 SER/SSER Impact: No 6.2-76. 77
Description:
(Correction) Justification: Remove reference to sequencing of valves and.for checking the order in which the motor operated valves (MOV's) open. This correction more accurately reflects testing methodology and system design. The MOV's which open on a "P" signal receive the signal simultaneously and are not sequentially operated.
Attach ;nt to TXX-90011 January 15, 1990 Page $4 of 304 FSAR Pope (as amended) Agg.criotion Group: 4 FSAR Change Request Number: 89 476 Related SER Section: 6.2.2 SER/SSER Impact: No 6.2-77 Descriptions (Correction) Justific6 tion: Corrects the description of the Containment Spray pump recirculation line design criteria to reflect the as-built conditions. Group 3 FSAR Change Request Number: 89 564.1 Related SER Section: 6.5.2 SER/SSER Impact: No 6.2 99 Descriptions (Correction) Justification: Deletion of incorrect reference to GDC 50. This correction is consistent with SER section 6.2.4 and S.R.P. 6.2.5. Group: 4 FSAR Change Request Number: 89 641.1 Related SER Section: 6.2.4 SER/SSER Impact: No 6.2 102 Descriptions (Correction) i Removes 10 CFR 100 radiological dose assessment for the l Hydrogen Purge System (HPS). ) Justifications i This change is made to conform with FSAR Sections 15.6.5 A and 6.2.5.2.2 previously made in Amendment 66. Dose assessment for HPS is'no longer a requirement in Section 15.6.5. Appendix C of the SRP. In addition, the HPS has been_ declassified in Am 76 to non safety as discussed in FSAR Section IAB. The HPS components, including the HEPA filters and-iodine adsorbers,-are described in Section 6.2.5.2.2. Group 3 FSAR Change Request Number: 89 499 Related SER Sections-15.4.5 SER/SSER Impact: No 6.2 102
Description:
(Correction) Deletes requirement for Hydrogen Purge Exhaust components to be designed for SSE loads and maximum temperature and pressure transients from a DBA. Justification: This change is consistent with the reclassification of the Hydrogen Purge Exhaust System from ESF, Safety-Related. Seismic Category I to Non ESF, Non-Safety and Seismic Category 11- as described in Amendment 76. Group: 3
Attachs nt'~ to TX'X 90011- ' January 15, 1990-- ; Page 55 of 304 FSAR Page-(as amended) , Descrintion FSAR Change Request Number: 89 461 j Related SER Section: 6.2.4 .
'SER/SSER Impact: No-6.2 106 Description s - (Correcti on) ;
-Justifications- ;
. Removes statement that.one train of the Hydrogen Purge System (HPS) is. required to be operable. This change is consistent with the de classification.of the HPS pre- .
~viously made in Amendment 76.
- Group: 3 FSAR Change Request Number: 89-440-Related'SER Section: 6.2.4 SER/SSER. impact: No-6.2-109
Description:
(Correction) The weight- of zirconium cladding is corrected from . i 43,204 to 43,375 lb. Justification: This change is made to be consisten'. with the. assumption of zirconium inventory ased in the hydrogen production and accumulation analysis. Group: 3~ FSAR Change Request Number- 89-703.01 Related SER Section: 6.2.4-SER/SSER Impact: No' 6.2 110
Description:
(Correction) . . . The' total hydrogen inventory and maximum concentration-within the primary coolant system are corrected from'- 1701.to 1191 scf and from 50 to 35cm3/kg respectively. A Justification: In FSAR amendment.66 these parameters were revised to be consistent with Westinghouse Chemistry Criteria and j Specification. However, the' revised parameters were not used in the hydrogen production and accumulation analysis to produce FSAR -figures 6.2.5A-5, -7 and 9. Therefore, this change is made to reflect the actual. assumptions, used in the analysis-.and thes update to these parameters per the Westinghouse Chemistry. Criteria is described in FSAR section 6.2.5A.S. Group: 3 FSAR Change Request Number: 89-703.02 Related-SER Section: 6.2.4 < SER/SSER Impact: No 6.2-114
Description:
(Editorial) Justification: Removes'a sentence which made reference to an FSAR .i figure +(6.2.5-3) which was deleted in-Amendment 36. Group: 4 FSAR Change Request Number: 89-703.03 - _ - - - - - =
- . ~ . - . -
Attach;ent to TXX 90011 f January 15. J990 : Page 56 of 304
't FSAR Page (as amended) Description Related SER Section: 6.2.4 SER/SSER Impact: No ,
6.2 118
Description:
(Addition) Adds requirement to quantitatively leak test the hydrogen purge system piping /ductwork. Justification: Since the hydrogen purge system is not an ESF system, Reg. Guide 1.52 testing requirements do not apply. Reg. Guide 1.140 does not have a requirement for quantitative leak testing, however, the hydrogen . .! purge system ductwork/ piping will be quantitatively j leak tested from the outboard containment isolation ' valves. ; Group: 3 ' FSAR Change Request Number: 89-628.8-Related SER Section: 6.2.4 ! l SER/SSER Impact: No l 6.2 120
Description:
(Editorial) , Justification: Corrects the Table number reference which list the materials for the Hydrogen Purge System. ' l Group: 4 FSAR Change Request Number: 89-505.1 Related SER Section: 6.2.4 SER/SSER Impact: No i 6.2-121
Description:
(Editorial) Justification: ., , Reference 4 is removed to be consistent with change on page 6.2 99. Group: 4 FSAR Change Request Number: 89-641.2 ' Related SER Section: 6.2.4 SER/SSER-Impact: No 6.2-124
Description:
(Correction) . The total hydrogen inventory and maximum concentration-within the primary coolant system are corrected from 1701 to 1191 scf and from 50 to 35cm3/kg respectively, Justification: In FSAR amendment-66. these parameters were revised to. be consistent with Westinghouse Chemistry Criteria and Specification. However. the revised parameters were not-used in the hydrogen production and accumulation analysis to produce FSAR figures 6.2.5A-5. -7 and -9. Therefore, this change is made to~ reflect the actual assumptions used in the analysis and the update to these parameters per the Westinghouse Chemistry Criteria is described 'in FSAR section 6.2.5A.S. Group: 3
JAttach;ent to TXX 90011 January 15, 1990 . Page 57 of 304 ! FSAR Page ! (as asettdad) Description FSAR Change Request Number: 89-703.02 , Related SER Section:'6.2.4 i
~
SER/SSER Impact:LNo
- 6.2 131
Description:
(Revision) Adds'a discussion regarding Post-LOCA hydrogen.produc-tion that may be produced inside Containment-as a-re ~ sult'of irradiation of cables, additional aluminum in-ventory, additional hydrogen in the RCS-and.of postula- , ted short-term out of range CSS' spray pH, i ! Justifications ; l The net impact of this revision-is the decrease in the -i time interval, from 16 to 12 days, to reach'the 3.5 -! volume percent concentration in Containment at_ which j _ operation of one hydrogen recombiner would be required.
- The impact of this change has been evaluated under the 10 CFR 50.59 process and determined to have no adverse-affect on the Combustible Gas Control System, since a f single hydrogen recombiner placed-in operation when the bulk containment hydrogen. concentration reaches 3.5
~
volume percent will maintain.the bulk hydrogen;concen-- tration well below the combustible limit of 4 volume percent. , Group: 2
- FSAR Change Request Number: 89-703.04 Related SER Section: 6.2.4-SER/SSER' Impact: Yes.
, SER 6.2.4 page 6-12 is not consistent as a result of ! this change. 6.2-133
Description:
L(Clarification) . !. The conclusion contained in this section is modified to l clarify that the operation 'of the hydrogen recombiner system is based on hydrogen- concentration-inside
- - Containment and not on a time-directed basis.
Justification: ' Hydrogen concentration in containment is displayed continuously (monitoring system is operational: 30, minutes following a LOCA) at the hydrogen analyzer 4 microprocessors located in the Control Room. In addi- i tion, a 3 volume percent hydrogen concentration-initiates an alarm in the Control Room, thereby. alerting an operator. This change is consistent with sections-6.2.5.2.3 and 6.2.5.5. Group: 4 FSAR Change Request Number: 89-703.05 Related SER Section: 6.2.4 l s
+ , . . - ~ - w <*e -* -
i Attach 22nt to TXX-90011 January 15, 1990 d l Page 58 of 304 'l
!i I
FSAR Page I tas amended) Description J l SER/SSER Impact: Yes { SER 6.2.4 page 6-12 is not consistent as'a result of - this change. ; 6.2-141
Description:
(Correction) ! Corrects-the description of the valve isolation tanks ' and associated piping for the containment recirculation lines. Justification: l This change reflects the removal of the manway covers
- from the valve isolation tanks to provide an_open vent path and also reflects the associated piping l configuration as shown in Figure 6.2.2-1;' Sh. 2.
Group: 4 t FSAR Change Request Number: 89-464 Related SER Section: 6.2.5 SER/SSER Impact: No l 6.2-142
Description:
-(Clarification) , Justifications Clarifies _that the test for the electrical penetration ' is conducted to determine leak rate rather than verifying _the maximum allowable-leak rate on the assembly. Group: 4 FSAR Change Request Number: 89-312.1 Related SER Section: 6.2.5 SER/SSER Impact:-No i Table 6.2.1-11, 12
Description:
(Editorial) ' Deletion of the. referenced tables from'the'FSAR was in- - advertently not performed in the final ~ processing of a-mendment 76, which incorporated revised _ design bases due to implementation of leak-before-break (Main Loop-piping and branch lines 10 inch and up). Justification: Deletion _of the tables'which are no longer applicable to the subcompartment design bases. Group: 4 FSAR Change Request Number: 89-629.1-Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No Table 6.2.1-13, 14 Descr* t tion: (Editorial) Deletion of the referenced tables from the~FSAR was in-advertently not performed:in the final processing ofon-mendment 76, which incorporated revised design bases < due to implementation of leak-before-break (Main- Loop piping and branch lines 10 inch and up). ! Justification: < Deletion of the tables which are no longer applicable-to the subcompartment design bases. l , . -_
Attach::nt. to TXX 90011 January- 15, 1990 Pege 59 of 304 FSAR Page (as amended) Descrintion Group: 4 FSAR Change Request Number: 89 629.1 Related SER Section: 6.2.1: SSER17 4.1-SER/SSER Impact: No Table 6.2.1-16. 17 Description (Editorial) Deletion of the referenced tables from the FSAR was in-advertently-not performed in the final processing of a-
-mendment 76. which incorporated revised design bases due to implementation of leak before break (Main Loop piping and branch lines 10 inch and up).
Justification: Deletion of the tables which are no longer applicable to-the subcompartment' design bases. Group: 4 FSAR Change Request Number: 89-629.1' Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No Table 6.2.1-18. 19 Descri pti on: -(Editori al ) Deletion of the referenced tables from the FSAR was in-advertently not performed in the final- processing of a-mendment 76.-which incorporated revised design bases due to implementation of leak-before-break (Main Loop piping and branch lines 10 inch and'up). Justification: Deletion of the tables which are no longer applicable to the subcompartment design bases. Group: 4 FSAR Change Request Number: 89-629.1 1 Related SER Section: 6.2.1: SSER17 4.1 ! SER/SSER Impact: No- , Table 6.2.1-20
Description:
(Editorial)
);
1 Deletion of the referenced table from the FSAR was in- ; advertently not performed in the final processing of.a- i mendment 76. which incorporated revised design bases due to implementation of leak-before-break (Main: Loop j piping and branch lines 10 inch and up). j Justification: ' Deletion of the table which is no longer applicable i to the subcompartment design bases. Group: 4 FSAR-Change Request Number: 89-629,1 Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No Table 6.2.1-22, 23
Description:
(Editorial) Deletion of the referenced tables from the FSAR was in-advertently not performed in' the final processing of a- , mendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main Loop
Attach 2ont- to TXX-90011 January 15, 1990 Page 60 of 304 FSAR Page (as amended) Descrintion i piping and branch _ lines-10 inch and up). Justification: Deletion of the tables which are-no longer applicable to the subcompartment design bases. Group: 4 FSAR Change Request Number: 89-629.1 Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No Table 6.2.1-24, 25 -Description: (Editorial) . . Deletion of the referenced tables'from the FSAR was11n-advertently not performed in the final processing of a- ' mendmentz76, which incorporated revised design bases due to implementation of leak-before break (Main Loop piping and branch-lines 10 inch and up). Justification: Deletion of-the tables wtich are no lon'ger applicable to the subcompartment design bases. Group: 4 FSAR Change Request Number: 69 629.1 Related SER Section: 6.2.1: SSER17-4.1 SER/SSER Impact:=No Table 6.2,1-27, 28
Description:
(Editorial) Deletion of the referenced tables from the FSAR was in-advertently not performed in the final-processing of a-mendment 76, which incorporated revised design bases .1 due to implementation of leak-before-break (Main Loop ! piping and: branch lines 10-inch and up). JL-stificati on: , .l ' Deletion of the tables which are no longer applicable y to the subcompartment design bases. ' Group: 4' FSAR Change Request Number: 89 629.1 Related SER Section: 6. 2 '.1 : SSER17 4.1' SER/SSER Impact: No Table 6.2.1-31, 32
Description:
(Editorial) . Deletion of'the referenced' tables from the FSAR was in-advertently not. performed in the. final processing of a s-mendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main Loop l piping and' branch lines 10 inch and'up). ,
)
Justification:~ ! Deletion of the. tables which are no longer applicable to the subcompartment design bases. j Group: 4 . FSAR Change Request Number:- 89-629.1 Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No 1 e
Attach 2snt to TXX-90011 January 15, 1990 Page 61 of 304 FSAR Page (as amended.) Descrintion L Table 6.2.1-33, 34
Description:
(Editorial), Deletion of the referenced tables from the FSAR was.in-advertently not performed in the final processing of a-mendment 76, which incorporated-revised design bases due to' implementation of leak-before-break (Main Loop. piping and branch lines 10 inch and up). Justification: Deletion of the tables which.are no longer applicable to.:the subcompartment design-bases. Group: 4 FSAR Change Request Number: 89-629,1 Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No Table 6.2.1-35
Description:
'(Editorial) Deletion of the referenced table from the FSAR was in- ) advertently not performed in the final processing of a-mendment 76, which incorporated revised design bases. due to implementation of leak before-break-(Main Loop piping and branch lines 10 inch and up). :; Justification: Deletion of the table which is no longer applicable i to the subcompartment design bases. ' Group: 4-FSAR' Change Request Number: 89-629.1 Related SER Section: 6.2.1: ~ SSER17 4.1 SER/SSER Impact: No Table 6.2.1-70, 71
Description:
(Editorial) .
-i Deletion of the referenced tables from the FSARLwas in-advertently not performed in the final processing of.a- ;
mendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main Loop piping and branch-lines 10 inch and up). i Justification: Deletion of the tables which are no longer applicable ' lI to the(subcompartment design bases. Group: 4 FSAR Change Request Number: 89-629.2 i Related SER Section: 6.2.1; SSER17 4.1 SER/SSER Impact: No Table 6.2.1-72, 73
Description:
(Editorial) Deletion of the referenced tables from the FSAR was in-advertently not performed in the final processing of a-mendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main Loop ; piping and branch lines 10 inch and up). ' Justification: Deletion of the tables which are no longer applicable to the subcompartment design bases. Group: 4 i
l p Attach ent to TXX 90011 : e ~ January 15, 1990 ~J Page 62 of 304 FSAR Page , (as amended) Description 1 FSAR Change Request Number: 89 629.2 ; Related SER Section: 6.2.1; SSER17 4.1 SER/SSER Impact: No , Table 6.2.1-74 75
Description:
(Editorial) . Deletion of the referenced tables from the FSAR was in-advertently not performed in.the, final processing of a - i mendment 76, which incorporated revised design-bases . due to implementation of leak-before break (Main Loop I
. piping and branch lines 10 inch and up).
Justification: l Deletion of th'e tables which are: no longer: applicable l to the subcompartment design bases. . Group: 4 y FSAR. Change Request Number: 89-629.2
~
Related SER Section: 6.2.1: SSER17 4.1 ., l SER/SSER' Impact: No
- Table 6.2.1-76
Description:
(Editorial) . ( Deletion of the referenced table from the FSAR was'in- ' advertently not performed in'the final processing of a-mendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main Loop
- piping and branch lines 10 inch and up).
Justification: - Deletes table which is no longer applicable to the sub.- < a 1 compartment design bases. L Group:: 4 l FSAR Change Request Number:L89 629.2 , Related SER' Sections 6.2.1; SSER17 4.1- " SER/SSER Impact: No Table 6.2.1-79. 80
Description:
(Editorial) " Deletion of the referenced.t' ables from the FSAR was in-advertently not performed incthe final: processing of_a-mendment 76, which incorporated revised design bases._ due to implementation of leak-before-break (Main Loop s piping and branch lines 10 inch and up)'. Justification: . Deletion of the tables-which are no longer applicable' to the subcompartment-design bases' . Group:.4 FSAR Change Request Number: 89-629.2-Related.SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No Table 6.2.1-81. 82
Description:
-(Editorial)
- Deletion of the referenced tables from the FSAR was-in-advertently not performed in the final processing of_a- 4 mendment 76, which incorporated revised design bases-due to implementation of leak-before-break (Main Loop piping and branch lines 10 inch and up). <
Attach 2ent to'TXX-90011l
- January: IS,- 1990 Page 63 of 304 FSAR Page (as amended) Descrintion Justification:
-Deletion'of the tables which are no longer applicable to the subcompartment design bases..
Group: 4 FSAR Change Request Number: 89-629.2. Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No-Table 6.2.1 83, 84
Description:
(Editorial) _ Deletion of the referenced-tables from the FSAR was in - advertently not performed 'in' the final processing ofl a-mendment 76, which incorporated. revised design-bases-due to implementation.of leak-before-break (Main Loop-piping and branch-lines 10 inch and-up). Justification: Deletion of the tables which are no longer-applicable to the subcompartment. design-bases.
-Gtcup: 4 FSAR Change Request Number: 89-629.2 Related SER Section: 6.2.1: -SSER17 4.1 SER/SSER Impact:.No I
Table 6.2.1 85, 86
Description:
(Editorial)-. Deletion of the referenced tables from the FSAR was in- ! advertently not performed in the final processing of a-- j mendment 76, which incorporated revised design bases due to implementation of leak-before-break.(Main Loop-piping and branch lines 10 inch and up). Justification: Deletion of the tables which are no' longer applicable to the subcompartment design bases. l Group: 4 . FSAR Change Requ'est Numt'er: 89-629.2 i Related SER Section: 6.2.1: 1SSER17 4.1 SER/SSER Impact: No-j Table 6.2.1-87, 88
Description:
(Editorial) l Deletion of the referenced tables from the FSAR was 1n- I' advertently not performed in the final processing of a- ' mendment 76, which incorporated revised. design bases. .; due to implementation of leak-before-break (Main Loop l piping and branch lines 10 inch.and up). < Justification: Deletion of the tables which are no longer applicable to the subcompartment design bases. Group: 4 FSAR Change Request-Number: 89-629.2 j Related SER Section: 6.2.1: SSER17 4.1 SER/SSER Impact: No i
h AttachMnt. to TXX 90011 -{ January 15, 1990 Page 64 of'304 l
-t FSAR Page f (as amended) ' Description Table 6.2.1-89, 90
Description:
(Editorial) Deletion of the referenced tables from the FSAR was in-advertently not performed in the final processing of a- , mendment 76. which incorporated: revised design bases l due to implementation of leak before break (Main' Loop ;
. piping and branch: lines 10. inch and up).
Justification: Deletion of the tables which are no longer applicable $ to the subcompartment design bases. 1 Group: 4 ' FSAR Change Request Number: 89-629.2:
.Related.SER Section: 6.2.1: SSER17 4.1
- SER/SSER Impact:-No Figure 6.2.1-21, 22
Description:
(Editorial) Deletion of the referenced-figures from the'SAR was in-advertently not performed in the f.inal' processing of a ' , mendment 76, which incorporated revised design-bases due to implementation of leak-before break (Main Loop piping and branch lines 10 inch and up).. Justification: Deletion of the figures which are no longer applicable ] to the subcompartment design bases. ' Group: 4 FSAR Change Request Number: 89-629.3 Related SER Section: 6.2.1: SSER17 4.1 SER/SSER impact: No L Figure 6.2.1-23, 24
Description:
(Editorial). Deletion of the referenced figures from the.SAR:was in-advertently not performed in the final. processing of.a-mendment 76, which incorporated revised design bases' due to implementation of leak-before-break (Main Loop. piping and' branch lines-10 inch and up). Justification:
. Deletion of.the. figures which are no longer applicable to the subcompartment design bases. ,
Group: 4-FSAR Change Request Number: 89-629.3 Related SER Section: 6.2.1: SSER17'4.1 SER/SSER Impact: No Figure 6.2.1 25, 26
Description:
(Editorial) Deletion of- the referenced figures from:the SAR was .in-- advertently not performed.in the fina1 > processing of a-mendment 76, which incorporated revised design bases ' due to implementation of leak-before-break-(Main Loop piping and' branch. lines 10 inch and up). Justification: Deletion of the figures which are no longer applicable to the subcompartment design bases. Group: 4
- a
- Attach ent to TXX 90011 !
' January 15, 1990-Page 65 of 304 ;
)
1 FSAR Page IAA amended) Descrintion , FSAR Change Request Number: 89 629.3 Related SER Section: 6.2.1; SSER17 4.1
- SER/SSER Impact: No Figure 6.2.1-27, 28 -Descriptions (Editorial)
Deletion of the' referenced figures from the SAR was:in- .-l advertently not performed in the final processing of a-mendment 76, which incorporated revised design bases ; due to implementation of-leak-before-break (Main Loop 4 piping and branch lines _10-inch and up). , Justification: i Deletion of the figures which are no longer applicable , to the subcompartment design bases. . -[ Group: 4 . FSAR Change Re.uest Number: 89-629.3. Related SER St .: tion: 6.2.1: SSER17 4.1 l SER/SSER Impact: No Figure 6.2.1-29
Description:
(Editorial) [ l Deletion of the referenced. figure from the SAR was in-advertently not performed in the: final processing of a- - mendment 76, which' incorporated revised design bases due to implementation of leak-before break (Main Loop piping and branch lines 10 inch and up). l l Justification: , Deletion of the~ figure which are no longer ^ applicable to the'subcompartment-design-bases.. Group: 4 5 FSAR Change Request Number:' 89-629.3 Related SER Section: 6.2.1; .SSER17'4.1 SER/SSER Impact: No ' Figure 6.2.1-53
Description:
(Editorial) Deletion of the referencedifigure from,the SAR was-in ' ' advertently not performed in the final processing of a-hiendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main. Loop ! piping-and branch lines-10. inch and up).. Justification: Deletion of the figure . which are no longer applicable. to the subcompartment design bases. Group: 4
'FSAR Change Request Numberc 89-629.3 Related SER Section: 6.2.1; SSER17 4.1 SER/SSER Impact: No Figure 6.2.1-57
Description:
(Editorial) Deletion of the referenced figure from the SAR was in-advertently not performed in the final processing of a-mendment 76, which incorporated revised design bases due to implementation of leak-before-break (Main Loop
- piping and branch'11nes 10 inch and up).
f 1
- - ..-._m. _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ _ ._ _, _
Attach 2ent ' to TXX-90011
-January _15, 1990 Page 66 of 304 FSAR Page (as amended) Descrintion Justification:
Deletion of the figure -which are no longer applicable to the subcompartment design bases. Group:-4 FSAR Change Request Number: 89 629.3 Related SER Section: 6. 2.1 ; ' SSER17 4.1= SER/SSER Impact: No. Table 6.2.2-1 See Sheet No(s):01
Description:
.(Correction)
- Justi fi cati on s.
Add range to boric acid concentration consistent with Table 6.18 4 and 6.5-3. Group:'3 FSAR Change Request Number: 89-504.05 Related SER Section:'6.5.2 SER/SSER Impact: No Table 6.2.2-5 .
Description:
(Correction) . i Justification: Revises table to include miniflow recirculation valves in the single failure analysis. This change ic
-consistent with the current single failure analysis for this system.
Group 3 FSAR Change-Request: Number: 8? " " .1 -s Related SER Section: 6.2.2 -- i SER/SSER Impact: No j 1 Figure 6.2.2 1 See Sheet No(s):01 and 02 j
Description:
(Correction) 1 Deletion of locked closed (LC) and locked open-(LO) a notation for selected valves in the figure. ' l Justification:- In response to an ob'servation by INPO concerning i excessive numbers of locked valves. TU. Electric : reviewed requirements for locked valves and identified valves which were not required'to' be locked. Group: 3 FSAR Change Request Number: 89-645.2 Related SER Section: 6.5.2 - SER/SSER Impact:-No (
' Figure 6.2.2-1 See Sheet No(s):02 '
Description:
(Correction) - ! Justification: . { Corrects figure to properly show the vent configuration for the Refueling Water Storage Tank. Group: 3 FSAR Change Request Number: SA-90-007 Related SER Section: 6.2.2 SER/SSER Impact: No
Attach:ent. 'to TXX 90011 d January 15, 1990: , Page 67. of~304 ] 1 FSAR Page (as amended) Descrintion .i Table 6.2.4-1 .See Sheet No(s):01, 02,-03, 04. 07, 08, and~11-
Description:
-(Editorial) Justification: . The line.or service-column is updated to provide. morel
-1 specific description. ,
- Group: 4 FSAR Change Request' Number: 89-312.2 Related SER Section: 6.2.3 - '.
SER/SSER Impact: No Table 6.2.4 2 See Sheet No(s):03 and 04
Description:
(Editorial) . . Delete valves 1FW-110 (Item 24) and 1FW 119 (Item 26) from the table. Justification: These corrections'were justified in FSAR Amendment 68 but were inadvertently not incorporated. These changes: make this-table' consistent with Tables-6.2.4 l', -3 and'
-6 and Figure'10.4-9 (Sheet 2).
~ Group: 4 FSAR Change Request Number: 89-573
- Related SER Section:'6.2.3 SER/SSER' Impact: No l
Table 6.2.4-2 See Sheet No(s):11 . I
Description:
-(Correction) Identifies the. type of containment leakage test ; E to be performed-on penetration # 123.- Justification: ! Penetration.# 123 requires a Type B Test' for containment leakage.- This is consistent with CPSES design' documents and with the leakage < testing performed on similar maintenance penetrations. Group: 3 FSAR Change Request Number: 89-748.2 ,
, Related SER Section: 6.2.5 SER/SSER Impact: No Table 6.2.4 See Sheet No(s):01 thru 06, 10, 11, 15, and 16-
Description:
(Editorial)- Justification: The normal operating function column is updated'to be' consistent with the other FSAR tables description.
~
Group: 4 FSAR Change Request Number: 89-312.3 Related SER Section: 6.2.3 SER/SSER Impact: No 4
---me , . - . - , . ,n . ., , -w-- , -- > - , - - -
E I- Attachient ' to TXX-90011 January 15, 1990
-Page 68 of 304 .
FSAR Page . (as amended) Descrintion l Table 6.2.5 6
Description:
(Editorial) Justification: Adds Table containing the component materials specifi - cations for the Hydrogen Purge System._This information was previously listed in Table 6.1B-1 prior to the'de-
- j. classification of this system to a Non-ESF Non safety. I L Group: 4 .
FSAR Change Request Number: 89-505.2 l
.Related SER Section: 6.2.4 r SER/SSER-Imp:Lia Me Table 6.2.5A-2' See Sheet No(s):01 '
Description:
- (Correction) The weight of zirconium cladding is corrected from ' 43.204 to 43.375 lb. Justification: This change is made.to be consistent with the. assumption of zirconium inventory used in.the hydrogen production and accumulation analysis. Group: 3 FSAR Change Request Number: 89-703.01
- Related SER Section: 6.2.4 SER/SSER Impact: No Table 6.2.5A-2 See Sheet No(s):01-i
Description:
'(Correction) l Corrects- the RCS total hydrogen inventory in primary coolant from 1701 to 1191'to be consistent with the changes made_on:page 6.2-110 and 6.2-124. Justification: Group: 3 FSAR Change Request' Number: 89-703.06 - Related SER Section: 6.2.4 l SER/SSER Impact: No l Table 6.2.5A-2 See Sheet No(s):01
Description:
(Editorial) Corrects a typographical error for the hydrogen recombiner capacity from 1000 to'100 SCFM.
-Justification:
This change is consistent with FSAR sections 6.2.5.3.3-(page 6.2-115) and 6.2.5A.5 (page 6.2-131). Group: 4 FSAR Change Request Number: 89-703.07 Related SER Section: 6.2.4 SER/SSER Impact: No Table 6.2.5A-3
Description:
'(Correction)
The inventory of aluminum contained in miscellaneous mechanical and_ electrical equipment is corrected.to
. reflect the amount used in the hydrogen production and accumulation analysis.
.t f
Attach ent to TXX-90011 l January 15, 1990 ! Page 69 of 304 ) j u iFSAR Page- ] (as amended) Descrintion Justification: ., l The previous update to these parameters and the impact ; of additional aluminum inventory for the rate of hydrogen production is discussed in FSAR section! , 6.2.5A.S. ' Group: 3-FSAR Change Request Number:- 89-703.08 Related SER Section: 6.2.4 : SER/SSER Impact: No Figure 6.2.5A-5 . Descripti on: (Revision) " Justification:: ' Adds a note to the curves of hydrogen. production and- ; accumulation to cross' reference =FSAR text corrections.' See discussions provided for subsection 6.2.5A.5 page 6.2-131. Group: 2 i FSAR Change Request Number: 89-703.09-Related SER Section: 6.2.4 SER/SSER Impact: Yes - SER 6.2.4.is not consistent as a result of this change. I Figure 6.2.5A-7
Description:
(Revision) I Justification:
. Adds a note to the curves of hydrogen production and accumulation to cross reference-FSAR text corrections.
See discussions.provided for subsection 6.2.5A.5 page 6.2-131. Groupt 2 FSAR Change Request Number: 89-703.09 ! Releted'SER Section: 6.2.4 3 SER/SSER Impact: Yes . SER 6.2.4list not consistent as a result of this change. ' Figure 6.2.5A-9 Descriptions (Revision) Justification: Adds a note to the curves of hydrogen production and. accumulation-to cross reference FSAR text-corrections. See-discussions provided for subsection 6.2.5A.5 page , 6.2-131. Group:,2. FSAR Change Request Number: 89-703.09 Related SER Section: 6.2.4 SER/SSER Impact: Yes SER 6.2.4 is not consistent as a result of this change. , 6.3-13 Descripti on:' (Cl arifi cation) ' Justification:- Clarifies the discussion of total differential pressure across the Safety l Injection accumulator check valves. Group: 4' FSAR Change Request Number: 89-446 I I
1 Attachhsnt to TXX-90011 January 15, 1990 ; Page 70 of 304 j
-l l
FSAR Page I (as amended) Descrintion l 1 Related SER Section: 6.3.2 l SER/SSER Impact: No R 6.3 24
Description:
(Revision)- . Corrects the switchover time from 18 to 16 hours to conform to the change made in FSAR subsection 15.6.5.2 which was submitted as an advance FSAR change to the i NRC in TXX-89815 dated 12-15-89. . Justification:. Increasing the upper limit on the RWST boron'concentra- t tion from 2100 to 2200 has been determined by calcula-tion to decrease the time at which hot leg <switchover 't should be. initiated from 18-to 16 hours. This revised. ' time will result in adequate safety' injection flow to: provide continued-long term cooling of the reactor core: without boron precipitation. .The impact'of:this~ change , has been eyeluated under the TV Electric 10 CFR 50,59 + process asz discussed in'TXX-89718 dated 9/28/89. Group: 2 . FSAR Change Request Number: SA-89 808 Related SER Section: 6.3.3 SER/SSER Impact: No i 6.3-25
Description:
(Editorial) 'I Justification: ' Change " Action 5" to " Action 6" to be consistent with the'new numbering of Table 6.3-7. Group: 4 , FSAR Change Request Number: 89 674.7- ' Related SER.Section:-6.3.2- L SER/SSER Impact: No- ' Table 6.3-7 See Sheet No(s):01 r
Description:
(Editorial)- Justification:- Change " actions 1 thru 5" to." actions 1 thru 6" to be consistent with the inclusion of'the new step 4.
< Group: 4 FSAR Change Request Number: 89-674.6 Related SER Section: 6.3.2 SER/SSER Impact: No Table 6.3-7 See Sheet No(s):02
Description:
(Correction) Justification:. Add step-4'to close the CCP miniflow to RWST valves, in order to prevent the injection of radioactive sump ( water into the RWST during recirculation mode. .This.is consistent with existing plant operation procedures. Group: 3 FSAR Change Request Number: 89-674.5 , Related SER Section: 6.3.2 l t
I Attach 2ent to TXX 90011 January. 15, 1990 Page 71 of 304-FSAR Page (as amended) %gicyJPt19.R H' SER/SSER Impact: No Table 6.3 7 See Sheet No(s):03
Description:
-(Revision) Corrects the switchover time from 18 to 16-hours to conform to the change made:in FSAR subsection 15.6.5.2 which was submitted as an advance FSAR change to-the NRC in TXX-89815, dated 12-15 89. Justification: See justification provided for subsection 6.3.2.8 page 6.3-24. Group: 2 j FSAR Change Request Number: SA 89-808 Related SER Section: 6.3.3 SER/SSER Impact: No Table 6.3-7 See Sheet No(s):05
Description:
(Correction) Justification: l Add step 13 consistent with Table 6.2.4 2. This alignment provides for presurizing valves by the Safety Injection Pump during hot leg recirculation for valves identified by Note 13 in Table 6.2.4-2. i Group: 3 FSAR Change Request-Number: 89-674.1 Related SER Section: 6.3.2 _{ SER/SSER_ Impact:'No- 1 Figure 6.3-1 See Sheet No(s):01
Description:
(Revision) { Revises support requirements-for non nuclear safety piping. Justification: Revises support requirements for non-nuclear safety - j piping to be consistent with Westinghouse design ' requirements. Piping'from the outlet of the relief valves to the Refueling Water. Storage Tanks shall be supported such that the line' remains functional: ' and provides a flow path through the line following- ) a safe shutdown earthquake. The availability of this i flow path through the centrifugal charging pump minimum ! flow bypass line ensures the ability-ofLthe centrifugal. charging pump to provide flow to the Reactor Coolant }, System following the receipt of a' Safety' Injection- ) Signal. 4 Group: 3 FSAR Change Request Number: 89-636.1 Related SER Section: 6.3.1 SER/SSER Impact: No !
Attachaent to TXX-90011 January 15, 1990: Page 72 of 304- .FSAR Page (as amended) Description Figure' 6.3 See Sheet No(s):02 and 03
Description:
(Update) Minor figure updates. Justification: No justification necessary. These figures contain changes of.the following type:
- 1. Manual vent or' drain vleves addition, removal, re-location, valve. number.
2..Manways or handways - addition, removal,:or re-location.
- 3. Editorial.- spelling, editorial or drafting errors which cannot impact technical meaning of the diagram
- 4. Line numbers or line sizes.;
- 5. Flanges or reducers - addition, removal, or re-location.
- 6. Piping or instrumentation'- physical interconnection changes which'have no impact on the operation /func-tion of system and equipment.
- 7. Manual valves - valve numbers or physical: location changes which have no impact on the operation /func- I tion of system and equipment.
- 8. Elevation changes.
Group: 4_ l FSAR Change Request Number: 89-732 SER/SSER Impact: No Figure 6.3 1 See Sheet No(s):04Jand 05 l
Description:
.(Correction) J Deletion of locked open (LO) notation for selected valves in the figure. Justification: ~ In response to an observation by INPO concerning- ) excessive numbers of: locked valves,- TU Electric reviewed requirements for4 1ocked valves and identified ~; valves which were not required'to-be-locked. Group: 3 FSAR Change Request Number: 89-645.3 1 Related SER Section: 6.3.2' i SER/SSER Impact: No Figure 6.3-2 See Sheet No(s):01
Description:
(Correction) Justification: Adds cross-connect valve #36 to figure to match the as-built plant. 1 Group: 3-FSAR Change Request Number: 89-674.4 Related SER Section: 5'.4.3 SER/SSER Impact: No l l i
Attach: nt to TXX-90011 iJanuary 15, 1990 J
.Page 73 of 304 ]
FSAR Page-(as amended)- Descrintion > Figure 6.3-2 See Sheet No(s): Notes: Sheet 3
Description:
- (Correction) Justification: Corrects the position status for valve no 6.. Operational Node C to open. -Adds note to valve'#6&7'. These changes are consistent with-Table 6.3-7. Group: 3 FSAR Change Request Number: 89-674.2 Related SER Section: 6.3.2 SER/SSER Impact: No Figure 6.3-2 See Sheet No(s): Notes: Sheet 4
Description:
(Correction) Justification: Adds valve #36 to be consistent with Figure 6.3-2 Sheet I changes. ! Group: 3- l FSAR Changt Request Number: 89 674.3 Related SER Section: 5.4.3 i SER/SSER Impact: No l i 6.4-1
Description:
(Clarification) ; Justification: ! Clarifies statement defining the control room envelope ; by adding a cross reference to section 6.4.2.1. l Group:-4 . , FSAR Change Request Number:: 89-800.01 Related SER Section: 6.4 ; SER/SSER Impact: No ! 6.4-4 Descript1on: (Clarification)- 4 Justification: Clarifies that the control room envelope includes the mechanical equipment rooms on Elevation 854*-4". This-i clarification ensures that-this section is not mis- t interpreted-to exclude the' mechanical equipment room. ! Group: 4 FSAR Change ' Request Number: 89 800.02 i Related SER Section: 6.4 l SER/SSER Impact: No- ! 6.4-6
Description:
(Clarification) Justification: Clarify the discussion relating to.the modes of opera- , tion which the control room. envelope is pressurized. This. clarification avoids any misinterpretation regard-ing the modes of operation' requiring positive pressure of 0.125 in, w.g. in the control room envelope. Group: 4 FSAR Change Request Number: 89 800.03 Related SER Section: 6.4 SER/SSER Impact: No I
Attach;ent to TXX-90011 ' January 15 -1990. Page 74 of 304 1; i FSAR Page (as amended) Agscrintion , h 6.4-7 Description (Editorial). Justification: Deletes redundant information which is included in the ! preceding and following paragraphs. I Group: 4 ' FSAR Change Request Number:- 89 800.04. Related SER Section: 6.4- ' SER/SSER Impact: No 6.4
Description:
(Clarification) i Justification: Adds the mode of operation which-the control room envelope will be pressurized.to verify leakage. Group:-4 . .. -l FSAR Change Request-Numbers:89 800.05 ' Related SER Section: 6.4 SER/SSER Impact: No-6.5-6. 13 See Page No(s):21
Description:
(Editorial) Justification: . . Sentences are relocated and minor editorial' changes are made for clarity. Group: 4 _. FSAR Change Request Number: 89-504.07-Related SER Section: 6.5.2 SER/SSER Impact: No 6.5-7
Description:
(Correction) Justification:
~ Change the words "the design" to "a minimum" to.be, ,
consistent with' Table 6.'2.2-2. ' Group: 4 , FSAR Change Request Number: 89 504.08 1 i= Related SER Section: 6.5.2 SER/SSER Impact: No ' 4 6.5-7
Description:
(Clarification) Justifications-Rewrite sentence to clarify that this section will only discuss those aspects <and subsystems of the-CSS which are used in the. removal of post LOCA fission products. Group: 4 ' FSAR Change Request Number: 89-504.15 Related SER Section:~6.5.2 SER/SSER Impact: No
.l
i Attach 22nt ' to TXX 90011 ; January-15, 1990
- Page 75 of-304- ]
FSAR Page. , 2 (as amended) ~ Descrintion i 6.5 8
Description:
(Editorial)- , Justification: Add section 6.5.2.2.1 on Nodes of Operation from i information.previously contained in section 6.2.2 and' section 6.5.2.for clarity. and add- discussion to clarify ,
.under what-conditions an equilibrium sump pH exists..
Group: 4 FSAR Change Request Number: 89 504.09 i Related SLR.Section: 6.5.2 ; SER/SSER Impact: _No
. 6.5-10
Description:
(Editorial) q~ Justification: Add item 3 " Piping _and. Valves" and a reference to i section 6.2.2.to make this section more complete. Grot.p: 4 FSAR Change Request Number:_89 504.11 Related SER Section: 6.5.2 SER/SSER_ Impact:.No 6.5-10
Description:
(Editorial). Justification: , _ . ; Delete section-on source of water; supply since this information is more appropriately included in section i 6.2.2.2. ' Group: 4 FSAR Change Request Number: 89-504.12 , Related SER Section: 6.5.2 SER/SSER Impact: No 6.5-12
Description:
(Editorial) Justification: Deletes section on modes of operation since this information is more appropriately contained in sections-L 6.2.2.2 and 6.5.2.2.3 and is therefore redundant. ! Group: 4 FSAR Change Request Number: 89-504.13-Related SER Section: 16.512 SER/SSERl Impact: No 6.5-18
Description:
(Editorial)- 4 Justification: + Delete reference to single failure analysis on this page, since it is more appropriately. included at the ; end of this section.- - Group: 4
- FSAR Change Request Number: 89-504.10 Related SER Section: 6.5.2
~
SER/SSER Impact: No i e e
- , ._____________x_-_____
-i AttachCent' to TXX-90011 January 150 1990-Page 76 of 304 l l
FSAR Page Description (as amended) f]i i 6.5 Description (Editorial) l Justification:' ; Delete reference to Tables 6.2.2 5 and 6.5 2..since ) this-information is more appropriately described'in ; sections 6.2.2.3.5 and 6.5.2.2.2 respectively. ' Group: 4 FSAR Change Request Number: 89 504.14 Related SER Section: 6.5.2 SER/SSER Impact: No Table 6.5-3
Description:
(Revision) RWST volume is revised.to be consistent with revised calculation resulting from corrections in the calcula-tion for referenced levels, Justification:- This change has been evaluated under the TU Electric 10 CFR 50.59 process as described in TXX 89718, dated' 9/28/89. Group: 2 FSAR Change Request Number:- 89 683.01- , Related SER Section: 6.5.2 l SER/SSER Impact: No Table 6.5-3 Descriptions (Revision) The upper limit-for boron concentration'in the RWST is ! increased from 2100 to 2200 ppe for operation 61~ flexibi.11ty. Justification:' _ . A minimum range of 200-ppe is provided.to avoid' opera-tional. constraints associated with the restoration of 3 RWST boron concentration within one hour as-required by ' technical specifications action statement. The recircu-lation time alone for this tank is approximately.90 minutes using.both Containment Spray pumpsLand approxi-mately 3 hours using one' Containment Spray' pump. This restrictive 200 ppa span will provide flexibility 1 in adding, recirculating,'. sampling, and analyzing-the
. RWST boron concentration within the one hour requirement.
This change has been evaluated under the TU Elect'ric 10 CFR 50.59 process as described in TXX-89718, dated 9/28/89, i Group: 2 . i FSAR Change Request Number: 89 683.02' ; Related SER Section: 6.5.2 j SER/SSER' Impact: Yes ' The boron concentration 1 described in SER section 6.5.2 t page 6-22 is not consistent -as a result of' this change. ;
~!
i
i Attach ent lto TXX-90011 -l i January 15, 1990-Page 77 of 304 j i FSAR Page (as amended) Description i
. }
Table 6.5 3
Description:
(Revision) I l Corrects the boron concentration for the RCS as a result of revised calculation. A more realistic boron concentration is used-in the' calculation in lieu of. the i bounding maximum concentration.< Justifications ; This change has been' evaluated under the.TU Electric 10 CFR 50.59 process as described in TXX 89718, dated 9/28/89. Group: 2 , FSAR Change Request Number: 89-683.03 Related SER Section: 6.5.2 SER/SSER Impacts No' f Table 6.5-3
Description:
(Revision) [ The Safety Injection accumulator volumes are corrected ! to properly account for the low lower head water volume of the accumulator. ' Justification: This change has,'been evaluated under the TU Electric . 10 CFR 50.59 process as described in TXX-89718, dateo 9/28/89. Group: 2 ' FSAR. Change Request Number: 89-683.04 Related SER Section: 6.5.2 SER/SSER-Impact: No 6.6-3
Description:
(Update) . A change to reflect evaluation = requires.ents of ASME . Section XI. Justification: This section is being updated to reflect that evaluation of examination results for Class 2 &'3 components will be conducted-in accordance with ASME , Section XI requirements. Articles IWC-3000 and IWD-3000 have been reviewed and are being incorporated into this section of the FSAR because'of their. ;
, applicability to CPSES.
Group: 4. FSAR Change Request Number: 89-797 :; Related.SSER Section: SSER12 6.6 g SER/SSER Impact: No . 7.1-1. 12 See Page No(s):30 l
Description:
(Correction) Instrumentation and Controls Justification: Correct reference to tables to reflect consistency with the FSAR. Groups 3 FSAR Chenge Request Number: 89-442.2 Related SER Section: 7.1 l l . .
-d
l Attachmnt- to TXX 90011 ! January.25. 1990 Page 78 of:304
+
FSAR Page (as amended) Description SER/SSER Impact: No 7.1 3
Description:
(Correction) Reactor trip system l Justification: Clarification of the definition of the delay times associated with reactor trip in this section and as specified in Table 7.2 3. The definition of time-delay represents the functional requirements for the reactor trip hardware as tested by the NSSS vendor. The previous definition represented the overall channel- , response time.specified in the Technical Specification and safety analyses which' takes into consideration. the hardware and downstream electronics time delays- i associated with the rods being free to fall. Group: 3 FSAR Change Request Number: 89-610.1 Related SER Section: 7.2.4 SER/SSER Impact: No 7.1-23
Description:
(Update) Instrumentation and. Controls Justification: Updates FSAR to reflect that provisions have been implemented to ensure that maximum credible f ault voltages / conditions from CPSES. cable roeting design will.not exceed tested voltages / conditions. Group: 3 FSAR Change Request Number: 89-442.3
- t Related SER Section: 7.1 SER/SSER Impact:LNo j 7.1-23, 24
Description:
(Correction) l Internal Wiring Separation for Instrumentation. Cabinets' Justification: The 7300 Series Process Control System. Noise Test (WCAP-8892A) addresses,the consequences of'Iack of: s internal rack wiring separation for,the 7300 Process Protection: Racks. This: report 1 concluded;that.. faults
.will not propagate from wire to wire even if the wires '
are ir, close proximity or even touching. Since the. internal wiring for the Auxiliary-Relay Racks and-the Reactor Trip Switchgear,use similar wiring routing patterns and are supplied by Westinghouse asLan assembled cabinet, Westinghouse has-indicated-that the conclusions.of WCAP-8892A are also' applicable to the Auxiliary Relay Racks and Reactor Trip Switchgear. l When the FSAR was updated in Amendment.66.to. include. the discussion regarding physical and electrical' separation of Westinghouse'B0P' Analog Instrumentation. System. the Auxiliary Relay Racks and Reactor Trip _ 1 Switchgear should have been included-in the Amendment. !______.___._____ _ - .i
. Attach 2ent to TXX-90011
-January 15, 1990' Page 79 of 304 l FSAR Page (as amended) Description [
This change was previously discussed in a conference l call (11/14/89) between the NRC and TV Electric, Group: 3~ ' j FSAR Change' Request Number: 89-740 Related SER Section: 8.4.4 SER/SSER Impact: No 7.1-30
Description:
(Correction) Equipment not Tested at Power - Reg Guide 1.22 Justification: In Amendment 77. FSAR Section 7.3.2 was revised to-describe an additional method for testing final actuation devices which no additional block circuitry is provided and which cannot be operated by.an individual slave relay or actuation of which would cause plant upset / equipment damage. When using this
-test methodology, the devices are~ declared inoperable, disabled (e.g. pull fuses. lift leads) and continuity checks performed, locally, to= determine if the slave relay has. changed states. Reg Guide 1.22 requires that-if a system is intentionally bypassed, then each bypassed condition should be individually and-automatically indicated in the control room. However, using the alternate test methodology =whereby devices ,
are being disabled by lifting leads, pulling fuses, etc.. indication of this condition is accomplished manually instead.of automatically.~This.is a deviation to the requirements of Reg Guide 1.22. but=is considered acceptable due to.the CPSES plant specific applications, and.since.the appropriate LCO will be entered for those t'avices' which are-declared inoperable j due to the test set-up requirements..In addition, this. ! section should have been updated and submitted in
-j conjunction with the Amendment 77 change to section 7.3.2, to reflect the impact of the alternate test J methodology on the-requirements of-Reg Guide 1.22.
Group: 3 s FSAR Change Request. Number: 89-659.1 '! Related SER Section: 7.3.3 -! SER/SSER Impact: No j 7.1-32, 40 See Page No(s):41 and 42
Description:
'(Addition) I Equipment not Tested at Power - Reg Guide-1.22 -i Justification:
Added the following list of equipment which devices H are not provided with additional block circuitry, + cannot be tested at reactor power and which will be .! tested using the alternate test method. Also, provided ! a brief description of,why the equipment / device (s), .; cannot be tested a' reactor power. 1
- 1. Residual heat removal pump containment sump l
l
' Attach:ent. to TXX-90011 January 15, 1990
- Page 80 of 304 1
- 1 FSAR Page 3 (as amended) Descrintion l l
L suction isolation valve : L 2. Normal charging containment isolation valves f l
- 3. Normal letdown containment isolation valves :
I
- 4. RWST charging pump suction isolation valves !
- 5. VCT outlet isolation valves !
Groups 3 . FSAR Change Request Number: 89 659.2 . Related SER Section: 7.3.3' ) l SER/SSER Impact: No 7.1-43
Description:
(Correction) i Instrumentation and Controls Justification: . Deletes A/E designation to drawings since drawings actually belong to TU Electric. r Group: 3 FSAR Change Request Number: 89 442.4 Related SER Section: 7.1 SER/SSER Impact: No Table 7.1-1 See Sheet No(s):01
Description:
-(Correction) Instrumentation and Control - Listing of #pplicable ! Criteria Justification: Corrects table to'be consistent with FSAR text.. Includes Section 9.5 of the FSAR as a related section-which discusses CPSES compliance to GDC 3. Group: 3 FSAR Change Request Number: 89-218.1
- Related-SER Section: 7.1.2 SER/SSER Impact: No Table 7.1-1 See Sheet No(s):02 .
l
Description:
(Correction) L Instrumentation and Control Listing of Applicable Criteria
, Justification:
Corrects table to be consistent with FSAR text. Includes FSAR Sections.6.4 and 9.4 as related. sections. > which discuss CPSES' compliance with GDC'19. Group: 3-FSAR Change Request Number: 89-218.2 Related SER Section: 7.1.2 SER/SSER Impact: No Table 7.1 1 See Sheet No(s):03
Description:
(Correction) Delete sections 7.3.1 and 7.3.2 from conformence discussed in column for GDC 27 and 28 in Table 7.1-1 Sheet 3. Justification: I
)
. Attach: nt to TXX 90011 ! ' January 15, 1990 Page 81 of 304 j i
FSAR Page ! (as amended) Descriati.gn-Deleted GDC's 27 and 28 applicability to FSAR Sections i 7.3.1-and 7.3.2. These changes are being made to be. I consistent with other changes in this LDCR. See description-for pages.7.3-1 and -73. ! Group: 3 . FSAR Change Request Number: 89 527.2 Related SER Section: 7.1.2 l SER/SSER Impact: No Table 7.1-1 See Sheet No(s):03
Description:
(Correction) Instrumentation ard Control - Listing of Applicable = Criteria Justification: Corrects table to be consistent with FSAR text. " Includes FSAR Section 7.7 as a related section which' discusses CPSES compliance.to GDC 26.. Group: 3 FSAR Change Request Number: 89-218.3 Related SER Section:!7.1.2 - SER/SSER Impact: No Table 7.1 1 See Sheet No(s):04
Description:
(Correction) Instrumentation and Control Listing of Applicable Criteria Justification: Corrects table-to be consistent with FSAR text. ' Includes FSAR Sections 6.3 and 9.3 as related: sections which discuss CPSES compliance with GDC 33. Group: 3 FSAR Change Request Number: 89-218.4= Related SER Section: 7 .1. 2 . SER/SSER Impact: No Table 7.1-1 See Sheet No(s):04
-Description: (Correction) s Instrumentation and Control - Listing of Applicable-Criteria Justification:
Corrects table to be consistent with FSAR text. Includes FSAR Section 5.4.7 as a related section which discusses CPSES compliance with GDC'34. Group: 3 k FSAR Change Request Number: 89-218.5 Related SER Section:~7.1.2 SER/SSER lapact:.No Y i
Attach:2nt- to.TXX-90011 January 15. 1990 Pace 82 of 304-FSAR Page (as amended) Descrintion Table 7.1-1 See Sheet'No(s):04
Description:
(Correction). Instrumentation and Control - Listing of Applicable, Criteria Justification: Corrects table to be consistent with FSAR text'. Deletes: incorrect references to FSAR instrumentation sections and adds the applicable system section reference, 6.2.2. for.CPSES compliance with GDC 38 and 40-Group: 3 FSAR Change Request Number: 89-218.6 Related SER Section:.7.1.2' SER/SSER Impact: No Table 7.1-1 See Sheet No(s):05
Description:
(Correction)- _ Instrumentation and Control - Listing of _ Applicable: Criteria Justification: Corrects table to be consistent with FSAR text. Deletes the incorrect FSAR instrumentation section and ' adds the correct system sections,.6.2.2 and_6.5.2, for CPSES compliance to GDC 41. L Group: 3 1 FSAR Change Request Number: 89-218.7 I Related SER Section: 7.1.2 SER/SSER Impact: No_ 4 I Table 7.1-1 See Sheet No(s):05 l
Description:
(Correction) __ Instrumentation and Control '- Listing of Applicable y Criteria Justification: .
']'
Corrects table to be consistent with FSAR' text. "j L Deletes the incorrect FSAR instrumentation section and' adds the correct system section, 6.5.2 for CPSES compliance with GDC 43. l
, Group: 3 l '
FSAR Change Request Number: 89-218.8 Related_SER Section: 7~.1.2 SER/SSER Impact: No .j Table 7.1-1 See Sheet No(s):05
Description:
(Correction) *
-l Instrumentation and Control - Listing of Applicable - 1 i Criteria --!
Justification: i Corrects-table to be consisten with FSAR text. _j Includes FSAR section 9.2.2 as a related section which discusses CPSES compliance.with GDC 44. j Group: 3 ., FSAR Change Request Number: 89-218.9 1 1 A
Attachment to TXX 90011 l Jan:ary 15, 1990 Page 83 of 304 FSAR Page ; (as .aW) Descrintion ; Related 3ER Section: 7.1.2 ! SER/SSER Impact: No J Table 7.1 1 See Sheet No(s):05 , Descriptions (Correction) Instrumentation and Control Listing of Applicable Criteria : Justification: 1 Corrects table to be consistent with FSAR text, i Deletes the incorrect FSAR instrumentation section and ; adds the correct system reference. 9.2.2, for CPSES ! compliance with GDC 46. [ Groups 3 t FSAR Change Request Number: 89 218.10 Related SER Section: 7.1.2 SER/SSER 1mpact: No Table 7.1+1 See Sheet No(s):05 and 06 Descriptions (Correction) Instrumentition and Control Listing of Applicable Criteria Justification: Corrects table to be consistent with-FSAR text. Includes FSAR section 6.2.4 as a related section which discusses CPSES compliance to GDC 54, 55, 56 and $7. Group 3 FSAR Change Request Number: 89 218.11 Related SER Section: 7.1.2 SER/SSER lapact: No Table 7.1 1 See Sheet No(s):06 Description (Correction) Instrumentation and Control Listing of Applicable Criteria Justification: Corrects table to reflect the correct year of applicability (1974) for IEEE-308'for CPSES. Also. adds
, FSAR sections 7.1.1.1.3 and 8.3.1 as related sections which discuss CPSES compliance'with IEEE 308 1974 Group 3 FSAR Change Request Number: 89-218.12 Related SER Section: 7.1.2 SER/SSER 1mpact: No Tabic 7.1 1 See Sheet No(s)t07 Description (Correction)
Instrumentation and Control' Listing of Applicable Criteria Justification: Deletes reference to FSAR section-7.1.2.10. This section does not contain any information regarding CPSES compliance with IEEE 336 1971. The section
t Attachment to TXK 90011 ! January 15. 1990 i Page 84 of 304 1 FSAR Page ! (as_ amended) Descristion j references 8.3.1.2. which is reflected in this Table, i Group 3 i FSAR Change Request Number: 89 218.13 i Related SER Section: 7.1.2 i SER/SSER Impact: No
-l Table 7.1-1 See Sheet No(s):08 !
Descriptions (Correction; ! Instrumentation and Control Listing of Applicable i Criteria i Justifications i Corrects table to be consistent with FSAR text, i Deletes the incorrect instrumentation section and adds ! the correct electrical section. 8.3 for CPSES
- l compliance with RG 1.6. ,
Groups 3 FSAR Change Request Number: 89 218.14 i i Related SER Section: 7.1.2 i SER/SSER Impact: No Table 7.1 1 See Sheet No(s):09 ! Description (Correction) , Instrumentation and Control - Listing of Applicable ! Criteria ! Justification: Corrects table to be consistent with FSAR text. t includes FSAR section IA(B) which addresses CPSES compliance to RG 1.22 for the Balance of Plant (BOP) equipment. i Group 3 . FSAR Change Request Number: 89 218.15 i Related SER Section: 7.1.2 . SER/SSER 1mpact: No l Table 7.1-1 See Sheet No(s):10 i Description (Correction) ; Instrumentation and Control Listing of Applicable , s Criteria ; Justification: ! I Corrects table to be consistent with FSAR text. 1 l Includes FSAR section 8.3 as a related section which i discusses CPSES compliance with RG 1.32. ' Group 3 ' FSAR Change Request Number: 89 218.16 ! Related SER Section: 7.1.2 SER/SSER 1mpact: No f Table 7.1-1 See Sheet No(s):11 Descriptions (Correction) ; Instrumentation and Control Listing of Applicable i Criteria Justification: l i l
Attachment to TXX-90011 l 5 January 15, 1990 I Page 85 Gf 304 FSAR Pope l (as amended) Descrintion Corrects table to be consistent with FSAR text. Includes.FSAR section 1A(B) which addresses CPSES i compliance with RG 1.53 for Balance of Plant (80P) l equipment, j Groups 3 FSAR Change Request Number: 89 218.17 i Related SER Section: 7.1.2 ! SER/SSER Impact: No l i Table 7.1 1 See Sheet No(s):12 i Descriptions (Correction) l Instrumentation and Control Listing of Applicable i Criteria l Justification Corrects' table to be consistent with FSAR text. Includes the applicable seismic and environmental ; qualification FSAR sections (3.10N&B and 3.11N&B) which - ; discuss CPSES compliance with RG 1.73. ! Groups 3 j FSAR Change Request Number: 89 218.18 -j Related SER Section: 7.1.2 , SER/SSER Impact: No i Tabic 7.1-1 See Sheet No(s):12
Description:
(correction) Instrumentation and Control - Listing of Applicable Criteria ' Justification: i Corrects table to be consistent with FSAR text. l Includes FSAR section 8.3 which addresses CPSES i compliance to RG 1.75 for electrical systems. Group 3 1 FSAR Change Request Number: 89-216.19 .{ Related SER Section: 7.1.2 1 SER/SSER impact: No l Table 7.1 1 See Sheet Nc(s):13
Description:
(Correction) Instrumentation and Control - Listing of Applicable Criteria Justification: Deletes reference to FSAR section 1A(N) for CPSES compliance with RG 1.95. Section IA(N) relates only to NS$$ and the specifics cf the RG addresses a plant specific BOP system for CPSES. Group: 3 FSAR Change Request Number: 89-218.20 Related SER Section: 7.3.2 SER/SSER Impact: No l l
6 Attachment to TXX 90011 ! January- 15, 1990 Page 86 of 304 { l l FSAR Page , (as. amended) Description i i Table 7.1 1 See Sheet No(s):13 Descriptions (Correction) ! Instrumentation and Control Listing of Applicable i l Criteria l Justification: : Corrects teble to be consistent with FSAR text. Includes FSAR section 7.$ which discusses in detail CPSES compliance with RG 1.97.
-Group: 3 !
FSAR Change Request Number: 89 218.21 !' l Related SER Section: 7.1.2 SER/SSER !apact: No Table 7.1 1 See Sheet No(s):13 i Description (Correction) l Instrumentation and Control Listing of Applicable
- Criteria L Justifications Corrects table to be consistent with FSAR text. !
' Includes FSAR sections 3.10N and 3.108 which discuss ; CPSES compliance with RG 1.100 in detail. ! Group: 3 l FSAR Change Request Number: 89 218.22 i Related SER Section: 7.1.2 SER/SSER Impact: No Table 7.1 1 See Sheet No(s):14 ! Descriptions (Correction)
- Instrumentatiun and Control Listing of Applicable l Criteria Justification: !
Corrects table to he consistent with FSAR text. I includes FSAR section 7.1.2.11'as a related section ( which discusses CPSES compliance with RG 1.118 for ! l ' instrumentation and control circuits. ' Group: 3
- FSAR Change Request Number:. 89 218.24 '
, Related SER Section: 7.1.2 SER/SSER Impact: No I l
Table 7.1 1 See Sheet No(s):14 ; Description (Addition) ! Instrumentation and Control Listing of Applicable
- Criteria Justification:
- l Adds RG 1.106 to the Table and the applicable FSAR i related sections which discuss CPSES compliance with ;
this RG. This addition is consistent with the FSAR .; text. / Group: 3 FSAR Change Request Number: 89 218.23 Related SER Section:'7.1.2 '!
l Attachment to TXX+90011 l January 15, 1990 ' Page 87 of 304 : FSAR Page I (as amended) Descrintion i i SER/SSER Impact: No ! Table 7.1-1 See Sheet No(s):14
Description:
(Correction) fe Instrumentation and Control - Listing of Applicable- l Criteria ; Justification: l Corrects table to be consistent with FSAR text. ! Includes FSAR section 9.5 as a related section which ! discusses CPSES compliance with RG 1.120. Groups 3 ,, FSAR Change Raquest Number: 89 218.25 l Related SER Section: 7.1.2 : SER/SSER Impact: No i Table 7.1 2.2 See Sheet No(s):01 Descriptions (Correction) i instrumentation and Control Reactor Trip System ., i Justifications Adds applicability of GDC 12 to Table 7.1-2.2 to the i the reactor trip system and NSSS system inputs. This ! change is consistent with related FSAR sections. 'l Groups 3 FSAR Change Request Number: 89 218.26 ; Related SER Section: 7.1 SER/SSER Impact: Yes ; SER Table 7.1 Safety-Related Instrumentation and Control Systems / Codes, Standards and Guides /
.i Applicability Matrix (Sheet 1 of 2) 7.2 Reactor Trip ,
System "RTS & NSSS Inputs" column does not designate - GDC 12 as applicable, t Table 7.1 2.2 See Sheet No(s):02 Descriptions (Correction) Instrumentation and Control - Reactor Trip System l Justification , Adds the applicability of Reg. Guide 1.47 to the reactor trip system instrumentation.in thic Table. This is consistent with the related portions of the 9 FSAR text. ; Group: 3 FSAR Change Request Number: 89-218.28 Related SER Section: 7.1 ; SER/SSER Impact: Yes ' SER Table 7.1 Sheet 2 of 2. does not designate Reg ' Guide 1,47 as applicable to the pertinent Reactor Trip ' System columns. 7 i
Attachment- to TXXo90011 l January 15, 1990 l Page 88 of 304 t FSAR Page (as amended) Descrintion l Table 7,1 2.2 See Sheet No(s):02 !
Description:
(Correction) . [ Instrumentation and Controls - Reactor Trip System ' i Justifications : Adds the applicability of Reg. Guide 1.22 to turbine [ trip reactor trip and reactor coolant pump under- ! , voltage underfrequency trip instrumentation. This is ! consistent with related portions of the FSAR text. l l Group: 3 l FSAR Change Request Number: 89-218.27 ! Related SER Section: 7.1 F SER/SSER Impact: Yes . SER Table 7.1 (Sheet 2 of 2) "7.2 Reactor Trip System" i column does not designate Reg. Guide 1,22 as applicable ! in the pertinent columns. Table 7.1-2,2 See Sheet No(s):03-Descriptions (Correction) Instrumentation and Controls Reactor Trip System l l Justification: ; ) Deletes the applicability of=!EEE 308 from the Table for " Turbine Trip Reactor Trip" and "RC Pump Undervoltage Underfrequency Trips" to be consistent I with related FSAR sections. ' Group: 3 FSAR Change Request Number: 89 218.29 ' Related SER Section: 7.1 SER/SSER Impact: Yes , SER Table 7.1 (Sheet 2 of 2) "7.2 Reactor Trip System" i column designates IEEE 308 as applicable in the [' pertinent columns. i Table 7.1 2.2 See Sheet No(s):04
Description:
(Correction) ' Instrumentation and Controls - Reactor Trip System Justification: Corrects text to reflect actual design. Adds "NSSS" to Note 1 of the Table to reflect the association of NSSS with the reactor trip system. ' Group: 3 FSAR Change Request Number: 89 218.30 - Related SER Section: 7.1.2 SER/SSER Impact: .No ' Table 7.1 2.3 See Sheet No(s):01-Descriptions (Correction) l Instrumentation and Controls - Engineered Safety I . Features System Justification: Deletts GDC 15 applicability from the control room air. ! conditioning instrumentation. The scope of GDC 15 is that the reactor coolant system be designed adequately ; 5 e e. e~.er- . -w _m. ,., v,,,- -
,,,.,-w-
Attachment to TXX 90011 i January 15, 1990 ! Page 89 of 304 ! I FSAR Pepe ! (as amended) Descrinlign ! to maintain the reactor coolant pressure boundary for ! normal operations and anticipated operational l occurrences. ! Group:.3 ' FSAR Change Request Number: 89-218.33 } Related SER Section: 7.1 i SER/SSER 1mpact: No table 7.1 2.3 See Sheet No(s):01 and 02 ! Description (Correction) [ Instrumentation and Controls Justifications ! Deletes GDC 10. 15, 35, 37, 38, 40. 41. 43, 44. 46 and I 50 applicability from the ESF support systems, where ! appropriate. This is consistent with related FSAR and Standard Review Plan sections (6.2. 6.5. 9.2 and 9.4). t Group 3 . FSAR Change Request Number: 89-218.31 , Related SER Section: 7.1 l SER/SSER Impact: Yes ! SER Table ~7.1 (Sheet 2 of 2) "7.3 Engineered Safety : Features System - ESF" column. designates the respective . GDCs as applicable in the pertinent columns. '
\
Table 7.1 2,3 See Sheet No(s) 01 and 02 ' Description (Correction) g Instrumentation and Controls . Justification: ; Deletes GDC 25 37, 40, 43 and 46 applicability for i ESFAS. ESFAS ts merely the actuation signal which l initiates an ESF system. The noted GDC's apply to the ; ESF system function and not the actuation signal. . Group: 3 I FSAR Change Request Number: 89 218.32 : Related SER Section: 7.1 i SER/SSER Impact: Yes SER Table 7.1 (Sheet 2 of~2) 7.3 Engineered Safety { features System - ESF Support" column designates the , respective GDCs as applicable in the pertinent columns. - Table 7.1-2.3 See Sheet No(s):02
Description:
(Correction) Instrumentation and Controls ! Justification: l Adds GDC 56 applicability to component cooling water , system. The scope of GDC 56-includes systems which , penetrate the reactor containment and thereby required - to be provided with containment isolation valves. : Group: 3 FSAR Change Request Number: 89-218.34 i Related SER Section: 7.1 i 1
-- . . . - __ . _ _ _ _ _ _ _ -- , . . , _ . - .. . -- -- I
i Attachment .to TXXo90011 January 150 1990 i Page 90 of 304 ! i FSAR Page (as.. amended) Descrintion SER/SSER Impact: Yes j SER Table 7.1 (Sheet 1 of 2) "7.3 Engineered Safety Features System ESF Support-CCW" column does not ! designate GDC 56 as applicable. : Table 7.1 2.3 See Sheet No(s):02 and 03 f Description (Correction), Instrumentation and Controls Justification: i Added the applicability 01 Reg. Guides- 1.22, 1.47 .
+
1.53, 1.73 and 1.97, where appropriate to the ESF and i ESF support instrumentatic.n. This change is consistent ! with related FSAR sections. Group 3 i FSAR Change Request Number: 89 218.35 Related SER Section: 7.1 i SER/SSER Impact: Yes ' I l SER Table 7.1 incorrectly reflects the applicability of [ these Reg Guides, r Table 7.1-2.3 See Sheet No(s):03
Description:
(Correction) Instrumentation and Controls i Justification l Delete IEEE-308 from Table 7.1 2'3 (Sheet 3 of 4) from all "ESF" columns and all "ESF Support columns except "Onsite Power Supply" in order to be consistent with j applicable instrumentation and electrical system design . per FSAR Sections 7.3 and 8.8.~ respectively. The scope of IEEE 308 addresses the surveillance requirements for power sources, actuation devices. etc. 'i Group 3 FSAR Change Request Number: 89 218.37 ' Related SER Section: 7.1 ' SER/SSER Impact: Yes SER Table 7.1 "7.3 Engineered Safety Features System - ESF and ESF Support" columns designate IEEE-308 as- ; applicable in the pertinent columns. ' Table 7.1 2.3 See Sheet No(s):03 ) I Descriptions (Correction) Instrumentation and Controls . Justification: . Added IEEE-338 and IEEE 379, where applicable to'"ESF"- l and "ESF Support" equipment. This is consistent with related portions FSAR sections 7.1.2.7 and 7.1.2.11. ,
- Group
- 3 FSAR Change Request Number: 89 218.38 Related SER Section: 7.1 i
Attachment to TXX-90011 January 15. 1990 Page 91 of 304 FSAR Page (as amended) Descrintion SER/SSER Impact: Yes SER Table 7.1 "7.3 Engineered Safety Features System - ESF and ESF Support". columns do not designate IEEE 338 as applicable in the pertinent columns. Table 7.1 2.3 See Sheet No(s):03 Descriptions (Correction) !
~ Instrumentation and Controls l Justification: _
l Deletes Reg. Guide 1.95 applicability for the j Control Room Air Conditioning. The CPSES chlorination ] system was replaced. Related FSAR sections 2.2.3, 6.4 ) and 9.4.1 were revised in Amendment 76 delineating this ' change. An evaluation of this change in Section 2.2.3 revealed no significant hazard is posed to the control room due to chlorine. Thus since Reg Guide 1.95 1
- specifically addresses accidental. chlorine releases, it is not applicable to the CPSES control room based on the current plant design.
Group 3. FSAR Change Request Number: 89 218.36 Related SER Section: 7.1 SER/SSER !apact: Yes SER Table 7.1 (Sheet 2 of 2) "7.3 Engineered Safety ] Features System Control Room Air Conditioning" column -! designates Reg. Guide 1.95 as applicable. - Table 7.1 2.3 See Sheet No(s):04 !
Description:
(Correction) Instrumentation and Controls 1 Justifications Adds "NSSS" to Note l'of the Table to reflect the l association uf NSSS ESF systems. l Group: 3 ) FSAR Change Request Number: 89 218.39 l Related SER Section: 7.1 1
- SCR/SSER 1mpact
- Yes #
, SER lable' 7.1, Note 1 does not include "NSSS" within the scope of applicability.
. Table 7.1 2.4 See Sheet No(s) 01
Description:
(Correction) Instrumentation and Control ; Justification: : Deletes GDC 34 applicability for the hot standby ' systems. GDC 34 specifically addresses the functional ' provisions of a residual heat removal system, i Group: 3 ; FSAR Change Request Numbers 89-218.44 Related SER Section: 7.1 ,
. . _ . . - . . ~ ._ - . - ~ . . . _ . ., ..-.m _- , 4
1 Attache:nt to TXX-90011 1 January 15. 1990 l Page 92 of 304 i t t FSAR Pepe ; (as. amended) Descrintion ! i SER/SSER Impact: Yes ! SER Table 7.1 reflects GDC 34 as applicable to the ; hot standby systems. l 1 Table 7.1 2.4 See Sheet No(s):01 l Descriptions (Correction) !
'nstrumentation and Control ;
Justification: Adds GDC 29 applicability to remote and cold shutdown j systems. This is consistent with related FSAR ; 4 sections. ; Group: 3 , FSAR Change Request Number: 89 218.51 , Related SER Section: 7.1 j SER/SSER Impact: Yes : SER Table 7.1 does not reflect GDC 29 applicability } for these syttees. ! Table 7.1 2.4 See Sheet No(s)t01 Description (Correction) ! l Instrumentation and Controls ; l Justification: Deletes GDC 15 from the applicable hot standby support ; instrumentation which is the same instrumentation j utilized as ESF support equipment. This is consistent ' with the changes to Table 7.1-2.3. ; I Group: 3 . I FSAR Chan9e Request Number: 89 218.41 Related SER Section: 7.1 ' SER/SSER Impact: Yes l Table 7.1 2.4 See Sheet No(s):01 -l l Descriptions (Correction) Instrumentation and Control i Justifications : Deletes GDC 24 applicability from Atmos. Steam Relief . instrumentation since it pertains to separation of' :
; protection and control systen. This is consistent ;
with related portions of the FSAR. Group 3 j' FSAR Change Request Number: 89-218.42 Related SER Section: 7.1 ' SER/SSER lapact: Yes t SER Table 7.1 "7.4 Systems Required for Safe Shutdown - [ Hot Standby-Required" designates GDC 24 and GDC 34 as , applicable in the pertinent column. Table 7.1 2.4 See Sheet No(s):01
Description:
(Correction) l instrumentation and Controls Justification: Deleted GDC 10 applicability from the hot standby l i
T Attachment to TXX 90011 January 15, 1990 l Page 93 of 304 I rsAn es,e l (as amended) Descrintion ! support, remote shutdown and cold shutdown instrumenta- ! tion where appropriate. The scope of GDC 10 includes i the reactor core and the associated coolant, control l and protection systems designed to prevent exceeding ! I fuel design limits. This is consistent with related [ FSAR sections.
- l Group 3 :
FSAR Change Request Number: 89 218.40 i kelsted SER Section: 7.1 SER/SSER Impact: Yes SER Table 7.1 "7.4 Systems Required for Safe Shutdown- I Remote Shutdoto Cold Shutdown" column are inconsistent I with the respective designations in the pertinent ; columns. l s Table 7.1 2.4 See Sheet No(s):01 l Descriptions (Correction) -i Instrumentation and Control ! Justification: I Deletes GDC 33 applicability for the onsite power l supply system. The scope of GDC 33 includes maintaining reactor coolant inventory. This is consistent with related FSAR sections. ! Groups 3 FSAR Change Request Number: 89 218.43 ; Related SER Section: 7.1 - SER/SSER Impact: Yes i SER Table 7.1 reflects GDC 33 as applicable to ' the onsite power supply. : Table 7.1 2.4 See Sheet No(s):02 L Descriptions (Correction) Instrumentation and Control Justification: Deletes GDC 44 and 46 applicability for the onsite.
- power supply. UPS ventilation and ESF ventilation systems. Also, adds GDC 44 and 46 applicability for the [
< control room air conditioning-system. This is consistent with related FSAR sections.
Group 3 FSAR Change Request Number: 89 218.45 Related SER Section: 7.1 i SER/SSER Impact: Yes . J SER Table 7.1 reflects'GDC 44 and 46 as ap111 cable - to the onsite-power supply and UPS and ESF ventilation systems and not applicable to control room air conditioning system. t h b s
. . _ . - _ _ - . - - . - ~ _ . . - . - -
Attache;nt to TXX 90011 January 15, 1990 Page 94 of 304 l FSAR Page (as amended) Descrintion Table 7.1-2.4 See Sheet No(s):02 l
Description:
(Correction)
- Instrumentation and Control l Justification l Adds GDC 56 and 57 applicability to the component l cooling water system. Also adds GDC 57 applicability l to the auxiliary feedwater system. The.GDC scopes include containment isolation provisions. for lines which penetrate the primary reactor containment.
( Group: 3 FSAR Change Request Number: 89 218.46 l Related SER Section: 7.1 i SER/SSER Impact: Yes l SER Table 7.1 does not reflect GDC 56 and 57 as I applicable to these systems. ! Table 7.1 2.4 See Sheet No(s):02 and 03 l Descriptions (Correction) Instrumentation and Controls Justification: Added Reg. Guides 1.22, 1.47, 1.53, 1.73 and 1.118 applicability to the hot standby, remote shutdown and cold shutdown instrumentation where appropriate. This change is consistent with related FSAR sections. Group: 3 FSAR Change Request Number: 89-218.47 Related SER Section: 7.1 SER/SSER Impact: Yes SER Table 7.1 (Sheet'2 of 2) "7.4 Systems Required for Safe Shutdown Hot Standby Required" column does not designate Reg. Guide 1.22 or Reg. Guide 1.47 as applicable in the pertinent column. Table 7.1 2.4 See Sheet No(s):03
Description:
'(Correction) Instrumentation and Controls l Justification: Deleted IEEE-308 applicability for hot standby and remote shutdown equipment with the exception of the onsite power supply. The scope of IEEE 308 does not address system functional requirements, but addresses the power-systems which enable the systems to meet their functional requirements. This is consistent with related FSAR-section 8.2.1.2.3. t Group: 3- i l FSAR Change Request Number: 89 218.49 " Related SER Section: 7.1 ,
Attachment to TXX 90011 January 15, 1990 Page 95 of 304 FSAR Pete (as amended) Description l l SER/SSER Impact: Yes . SER Table 7.1 incorrectly reflects IEEE 308 l applicability. l Table 7.1 2.4 See Sheet No(s;:03
Description:
(Correction) Instrumentation and Controls Justification: Added IEEE 279. 338 and 379 applicability to the hot standby and remote shutdown equipment, where , appropriate. This is consistent with related FSAR l section 8.2.1.2.3. Group: 3 FSAR Change Request Number: 89 218.50 Related SER Section: 7.1 SER/SSER Impact: Yes SER Table 7.1 does not correctly reflect the applicability of these standards. Table 7.1-2.4 See Sheet No(s) 03 and 04
Description:
(Correction) Instrumentation and Controls Justification: Added' Note 9 for clarification for Reg Guide 1.97 applicability. Accident monitoring instrumentation for hot standby conditions is the same Table 7.1 2.3 instrumentation utilized for ESF systems. Group 3 FSAR Change Request Number: 89 210.48 Related SER Section: 7.1 SER/SSER Ispect: Yes SER Table 7.1 does not reference Note 9. l Table 7.1-2.5 See Sheet No(s):01, 02, 03 and 04 Descriptions (Correction) Instrumentation and Control Justification: Osletes SS!! applicability to the safety related display Table. SSI! is a non safety related display. Group: 3 FSAR Change Request Number: 89 218.61 Related SER Section: 7.1-SER/SSER Impact: Yes SER Table 7.1 reflects SSII'as a safety related display.
- Table 7.1-2.5 See Sheet No(s):03
Description:
.(Correction) Instrumentation and Control L Justification: Adds Reg Guide 1.53 and IEEE 379 applicability for accident monitors safety-related display instruments.
Attachment to TXX 90011 January 15. 1990 -l Page 96 of 304 : FSAR Pepe ; (as amended) Descrintion l This is consistent with related FSAR sections. ! Group: 3 ! FSAR Change Request Number: 89 218.52 i Related SER Section: 7.1 . SER/SSER Impact: Yes SER Table 7.1 does not reflect the applicability i of the Reg Guide and IEEE Standard. ' Table 7.1-2.5 See Sheet No(s):03 , Descriptions (Correction) i Instrumentation and Contro) ' Justification: Deletes IEEE 308 applicability for the accident monitors safety related display instruments. The scope , of IEEE 308 addresses surveillance requirements for , power sources, actuation devices, etc. Group: 3 FSAR Change Request Number: 89 218.53 Related SER Section: 7.1 SER/SSER 1mpact: Yes _ SER Table 7.1 reflects IEEE 308 as applicable for. - these displays, i Table 7.1 2.5 See Sheet No(s):04 b Description (Correction) i Instrumentation and Control -; Justification: t Revised Note I to reflect that the scope of this - Table is to denote the applicability of GDC's. IEEE's ; and Reg Guides for instrumentation only. ; Group: 3 . FSAR Change Request Number: 89 218.54 [ Related SER Section:'7.1 SER/SSER Impect: Yes SER Table 7.1 includes control and electrical power supplies within the scope of this Table, which is incorrect. i Table 7.1 2.6 See Sheet No(s):01 ; Description (Correction) i Instrumentation and Control ' Justification: Deletes GDC 15 applicability for reactor coolant ' pressure boundary leak detection instrumentation. This is consisent with related FSAR sections and the ' Standard Review Plan section 5.2.5. : Group: 3 ' FSAR Change Request Number: 89-218.57 Related SER Section: 7.1 . r
Attachment to TXX 90011 .i, January 15, 1990 Page 97 of 304 l i FSAR Page l (as amended) Descrintion , ' i SER/SSER Impact: Yes SER Table 7.1 reflects GDC 15 as applicable to RCPS f' leak dection. { Table 7.1 2.6 See Sheet No(s):01 and 02
Description:
(Correction) l l Instrumentation and Control l Justification:
- l Deletes GDC 24, 54 and 56 applicability for hydrogen (
! monitoring instrumentation. This is consistent : with related FSAR sections and design documents. ! Groupt 3 ~i FSAR Change Request Numbers'89 218.58 l Related SER Section: 7.1 l SER/SSER Impact: Yes i SER Table 7.1 reflects these documents as applicable ~ ! to the hydrogen monitoring instrumentation. i Table 7.1-2.6 See Sheet No(s) 01 and 03 i
Description:
(Correction) , Instrumentation and Control l Justifications ; l Deleted GDC 3. 5,13,19, 24 and RG 1.70 applicability ! l for fire protection instrumentation. The CPSES fire i protection regulatory requirements are described in the ' FSAR section 9.5 as denoted in Note'6. Group 3 FSAR Change Request Number: 89 218.56 ' Related SER Section: 7.1 SER/SSER Impact: Yes ! SER Table 7.1 reflects the noted GDC's and RG as applicable to fire protection instrumentation. ' l Table 7.1-2.6 See Sheet No(s):01, 02 and 03 !
Description:
(Cerrection) t l l Instrumentation and Control. l Justification: . 7 Deletes applicability of GDC's. Reg Guides and IEEE's i The scope of.this Table includes instrumentation and ! not power supplies. Power supplies are addressed in FSAR section 8.3.1.2.1 as indicated by Note 3. i' Group: 3 FSAR Change Request Number: 89 218.55 ' Related SER Section: 7.1 l SER/SSER 1mpact: Yes SER Table 7.1 incorrectly includes power supplies , in this Table, i
,j i
Attachment to TXX 90011 ! January 15, 1990 t Page 98 of 304 ; j FSAR Page (as amended) Descrintion t Table 7.1-2.6 See Sheet No(s):02 and 03 !
Description:
(Correction) ! l Instrumentation and Control l Justification: ' Adds Reg Guide 1.22, 1.47, 1.53, 1.73, 1.97, IEEE.338 i and 379 applicabiltiy to the instrumentation noted in l , this Table, where applicable. This is consistent with ; related FSAR sections. ;
- Groups 3 FSAR Change Request Number: 89 218.59 .
I Related SER Section: 7.1 , SER/SSER 1mpact Yes SER Table 7.1 does not accurate reflect the applicability of these documents. i Table 7.1 2.6 See Sheet No(s) 03 i
Description:
(Correction) ' l Instrumentation and Control Justification: ( Deletes IEEE 308 applicability to this Table, The scope i of IEEE 308 includes power supplies, actuation devices. etc. . Groups 3 ! FSAR Change Request Number: 89 218.60 l Related SER Section: 7.1 - SER/SSER Impact: Yes ! SER Table 7.1 incorrectly reflects' the applicability i of IEEE '508. Table 7.1-2.6 See Sheet No(s):04 ' Descriptions (Correction) Instrumentation and Control Justification: : Revised Note 1 to reflect that the scope of this Table ' only addresses instrumentation. & Groups 3 FSAR Change Request Numbers. 89 218.62 Related SER Section: 7.1 l SER/SSER Impact: Yes , SER Table 7.1 reflects that the scope of this Table . includes electrical power supplies only. ' Table 7.1 2.7 See Sheet No(s):01
Description:
(Correction) : Instrumentation and Control ' Justifications ! Deletes GDC 15, 28, 29 and 33 applicability for ' NSSS contro1' system instrumentation not required for. l safety. This is consistent with related FSAR : sections. Group: 3 t FSAR Change Request Number: 89 218.64>
<z
~ ._ _ _ . _ . _ _ _ _ _ _ . __ _ - - _ _______
Attachment to TXX 90011 January 15. 1990 t Page 99 of 304 i i FSAR Page las amended) Etterietion l Related SER Section: 7.1 i SER/SSER Impact: Yes i SER Table 7.1 reflects that the GDC's are applicable -! to NS$$ control systems. ! 1 Table 7.1 2.7 See Sheet No(s):01 l'
Description:
(Correction) Instrumentation and Controls ! Justification: . Added the applicability of GDC 26 to the NSSS control [ system instrumentation. This change is consistent with related FSAR sections. See FSAR sections 3.1 and 7.7. Group 3 FSAR Change Request Number: 89 218.67- ! Related SER Section: 7.1 SER/SSER Impact: Yes ! SER Table 7.1 does not reflect GDC 26 as applicable to
- the NSSS control system. j Table 7.1-2.7 See Sheet No(s):01, 02, 03 and 04
Description:
' (Correction) : Instrumentation and Control , , Justification: l Deletes the term " safety related" from the title of i this Table for this Table pertains to systems not required for safety. . Group 3 , FSAR Change Request Number: 89 218.63 Related SER Section: 7.1 SER/SSER impact: No ' l Table 7.1 2.7 See Sheet No(s):03 and 04 ,
Description:
(Correction)
- Instrumentation and Control -
Justification: Adds IEEE 279 applicability for NS$$ control system instrumentation not required for safety. Note 8 was -t added to clarify that the applicability of IEEE 279 ' Section 4.7 pertains to these systems. Group: 3 FSAR Change Request Number: 89 218.65 ~ Related SER Section: 7.1 SER/SSER Impact: Yes i SER Table 7.1 does not reflect the applicability of' ( IEEE 279 section 4.7 for NSSS control systems. ; Table 7.1 2.7 See Sheet No(s):04 ' '
Description:
(Correction) ' Instrumentation and Control Justification:
- Revised Note I to reflect that the scope of this Table only addresses instrumentation.
P
,., -y , , ,.-w.- -r, _ + - -,, + e
Attachment to TXX 90011 l January 15, 1990 ! , Page 100 of 304 : i { i I I FSAR Page ; l (as amended) Descrintion ; Group 3 l FSAR Change Request Number: 89 218.66 : Related SER Section: 7.1 EER/SSER Impact: Yes SER Table 7.1 includes electrical power supplies j I within the scope of this Table. ;
+
i . Figure 7.1 3 See Sheet No(s) 02 ' i Descriptions (Addition) . Conformance to Reg Guide 1.97, Rev. 2 ;
~
Justification: Updated the figure to reflect RHR heat exchanger inlet -l temperature indication (TE 612 and TE 613) as accident ; monitoring instrumentation. : Group 3 i FSAR Change Request Number: 89-695.16 ' Related SSER Section: SSER12 APP T SER/SSER Impact: No Figure 7.1 3 See Sheet No(s):05 and 07 Descriptions (Correction) , Instrumentation and Controls - Identification of -i Safety Related Systems - Updates figure by indicating proper position of class IE instrumentation. Justification l Updates figure by indicating proper position of Class ' 1E instrumentation. Prior IE instrumentation drawings l did not reflect the correct location of Class IE - [ instrumentation.
- Group: 3 FSAR Change Request Number: 89 457, i Related SER Section: 7.1.2' SER/SSER Impact No ,
Figure 7.1 3 See Sheet No(s):07 Description (Update)- Conformance to Reg Suide 1.97, Rev. 2 Justification: Updated the figure to reflect the RCS wide range i pressure transmitter (PT 3616), that is utilized as one of the three required accident monitoring channels. Group: 3 - FSAR Change Request Number: 89 695.15 ' Related SSER Section: SSER12 APP T - SER/SSER Impact: No. . Figure 7.1-3 See Sheet No(s):16 and 18 '
Description:
(Correction) ! Location of Class IE and Accident Nonitorino Instrumentation ' Justification: In SDAR 86 19. several' steam service pressure transmit-
. . ~ . , , _
i Attachment to TXX-90011 ! January 15, 1990 Page 101 of 304 : i i FSAR Pepe >
- (as amended) Description >
?
l l ters were identified as installed above the root valve ; ! without steem traps or wetlegs, which could result in : I erratic transmitters behavior due to a buildup of I condensation. To correct the problem TU Electric l' relocated the transmitters below the root valve and rerouted the tubing per the proper slope requirements, i Turbine impulse pressure transmitters, 1 PT 505 and l 1 PT 506, required relocation per the above discussion. i Figure 7.1 3 Sheet 16 depicts the new location of these l transmitters and Figure 7.1 3 Sheet 18, which showed , the old location, was deleted since no other instrumentation is depicted on this drawing. , Group:.3 i FSAR Change Request Number: 89-724 . Related SER Section: 7.1 SER/SSER Impact: No 7.2 4 Descriptions (Editorial) , Reactor trip system Justification: Correction of typographical error "Interrange" should , be " intermediate range." l Group: 4
- FSAR Change Request Number: 89 610.2 Related SER Section: 7.2 :
SER/SSER Impact: No 7.2 5 Descriptions (Correction) Reactor trip system Justification: - Ccrrect FSAR text by deleting the reference to DNB t protection for rod ejection accidents. For rod ejection accidents, limited DNS is expected to occur
- and is considered an acceptable' consequence in the Chapter 15 accident analysis.
Group 3 , FSAR Change Request Number: 89 610.3 l Related SER Section: 7.2.1 ' SER/SSER Impact: Yes : The original SER (section 7.2.1, p. 7-5) should be revised to reflect that the power range high positive neutron flux rate trip does not~ provide protection from DNB for rod ejection accidents. 7.2 7 Descriptions (Correction) Reactor trip system Justification: t Corrects text to include the gain term associated with , the calculation of the Overtemperature N 16 setpoint. 1 This term was in advertently omitted from the FSAR. ' text. . Group: 3 : 1,
?
4 .~,. - - - . . ~ - , - . . _ . -
Attachment to TXX-90011 January 15. 1990 Page 102 of 304 l l l FSAR Page (as amended) Description FSAR Change Request Number: 89 610.4 Related SER Section: 7.2.1 SER/SSER 1mpact: No 7.2 20 Descriptions (Update) Transit time flow meters ! Justifications i Update of the FSAR text regarding N 16 TTFM flow measurement accuracy. The correct accuracy associated ' with the conversion between N 16 activity and RCS flow is +/- 1.3% (without conservatism). This is consistent l- with the accuracy values previously submitted ; to the Staff in TU Electric letter, TXX 89151, dated March 31, 1989. Enclosed in the above letter was WCAP 12228 (Proprietary), demonstrating the }' calculation utilized to establish the 1.3% accuracy i value. The letter also provided clarification , regarding RCS flow measurement accuracy included in Technical Specification. This value included additional ; conservatism such that the accuracy considered in ; the Technical Specification is 1.8%. Group: 3 i FSAR Change Request Number: 89 610.5-Related SER Section: 7.2.1 SER/SSER !apact: No 7.2 27 Descriptions (Clarification) Reactor trip system
.)ustification:
Clarification of the accident analysis reference : regarding the functional requirements of the reactor trip system. Group: 4 ) FSAR Change Request Number: 89 610.6 Related SER Section: 7.2 SER/SSER Impact: No 7.2-31
Description:
(Correction) Trip setpoints : Justification:
- Corrects text to properly identify the overtemperature l N 16 trip lines designation in Figure 15.0.1. .
Group: 4 ! FSAR Change Request Number: 89 610.7 i Related SER Section: 7.2 SER/SSER 1mpact: No l t Table 7.2 1 See Sheet No(s):02
Description:
(Correction) Reactor trip system , Justification: Corrected Table 7.2 1 entry for the' reactor trip, . L
- - + - -- ,-.a,n , -. - - -- m
AttachZ nt to TXX 90011 l January 15, 1990 l Page 103 of 304 . i l FSAR Page l (as amended) Descrintion ' l low reactor coolant flow by deleting the 1/4 ', j coincidence for P 8 permissive. This entry has no l relevance to this table. i Group 3 l i FSAR Change Request Number: 89 610.8 ' l Related SER Section: 7.2 i SER/SSER Impact: No- [ Table 7.2 3 See Sheet No(s):01 !
Description:
-(Correction) Reactor trip system i Justification: _ Editorial correction. The "+/ " symbol was , inadvertently omitted from the trip accuracy percentage i for power range high neutron flux. . Group: 4 i FSAR Change Request Number: 89 610.9 Related SER Section: 7.2 SER/SSER Impact: No , Table 7.2 3 See Sheet No(s) 01, 02 and 03 [ Descriptions (Correction) i Reactor trip system i i Justifications i The information in Table 7.2-3 represents the ! l functional requirements used for equipment J specifications and not the Technical Specification and ; l safety analysis. Therefore, the noted change!, in this ! thble reflect the applicable range. trip accuracy, ! l and response times for the functional requirements. These changes are consistent with tne l
" Control and Protection Systems Functional Requirements" document. (See also the description for .
page 7.1 3). - Group 3 . FSAR Change Request Number: 89 610.10 Related SER Section: 7.2 SER/SSER Impact: No > I i Table 7.2 3 See Sheet No(s):03 Descriptions (Correction) ; l Reactor trip system l Justification: Replaces the term " linear" with " travel" which describes the trip accuracy for the turbine trip stop valves..This clarifies that the trip accuracy is a percentage of valve travel. , Group: 3 FSAR Change Request Number: 89 610.16 i Related SER Section: 7.2 ' SER/SSER lupacts' No i i
Attache:nt -to TXX-00011 January 15. 1990 Page 104 of 304 FSAR Page (as aa W ) Descrintion Table 7.2 4 See Sheet No(s):06 Description (Correction) Reactor trip system Justification: Corrects the Table entry for low reactor coolant flow trip. The reference to the Chapter 15 section was incorrect. Also, added a line entry for reactor coolant pump shaf t seizure (locked rotor) Condition IV accident and the applicable Chapter 15 cross reference. This change is consistent with the accident scenarios specified in the safety analysis which initiate a reactor trip due to reactor coolant low flow. Groups 3 FSAR Change Request Number: 89 610.11 Related SER Section: 7.2-SER/SSER Impact: No Table 7.2 4 See Sheet No(s):06
Description:
(Correction) Reactor trip system Justification: Corrects Table entry for low-low steam generator level trip. The Condition IV accidents (loss of non emergency AC power to the station auxiliaries' and feedwater system pipe break) are being added to be consistent with Chapter 15 and therefore makes the Table more i complete. i Group 3 ; FSAR Change Request Number: 89 610.12 Related SER Section: 7.2 SER/SSER Impact: No Table 7.2-4 See Sheet No(s):07
Description:
(Correction) ! Reactor trip system Justification: Corrects Table entry for an $1 signal actuation trip to include a steam system piping failure Condition IV accident. This change is consistent with Chapter 15 for this trip and therefore makes the Table more complete. Group: 3 FSAR Change Request Number: 89 610.13 Related SER Section: 7.2 SER/SSER 1mpact: No 7.3 1, 73
Description:
(correction) ESFAS GDC Applicability. Justification: Deleted the requirements GDC's 27, 28, and 38 from FSAR Section 7.3.1 because they are not applicable to ESFAS. Also deleted the reference to 1971 since GDC are not generally dated. l-i
i Attachm3nt to TXX+90011 January 15. 1990 Page 105 of 304 I FSAR Page 1 (as. amended) Descriation j l Group 3 j FSAR Change Request Number: 89 527.1 : Related SER Section: 7.1.2 I SER/SSER Impact: No 7.3 11
Description:
(Correction) ; Justification: l Removed statement concerning a flow orifice and valve i providing the required bypass flow for the Containment Spray pump if the discharge valve has not reached the full open position. This change is made to match the as built condition of the plant. The recirculation i valve closes soon after the discharge valve begins to j open as described in FSAR section 6.2.2.5. .) Group: 4 ) FSAR Change Request Numbert 89 564.2 l Related SER Section: 7.3.1.3 ; SER/SSER 1mpact: No 1 7.3 42
Description:
(Revision) Removal t,f Station Service Water (SSW) recirculation 1 line control valves associated piping and orficies. { Justification: ) i The Service Water Recirculation piping is internally ! i coated with plasite. This material may flake off during ] the recirculation operation and then be discharged . into the Service Water Pump Suction Bay where it could be drawn into the service water pump. Once inside the i Service Water system, plasite could block equipment 1 inlets / openings, thereby reducing the supply of service ' water to equipment. To prevent this condition, the SSW 1 recirculation control valves, associated piping and orifices were removed and replaced with blind flanges which prohibits flow in the loop. The FSAR text was I revised deleting the reference to the SSW pump ] recirculation valves since they are longer capable of i controlling pump flow. Note that pump testing can ; still be conducted without the recirculation-line by i starting the pump in the standby mode, as long as the j availability of the remainder of the SSW train is' { assured. This change has been evaluated under the TU ' Electric 50.59 process as described in TXX 89718.- dated 9/28/89. Group: 2 l FSAR Change Request Number: 89 782.1 l Related SER Section: 9.2.1 ]1 SER/SSER Impact: Yes The SER states that the recirculation loops are ! provided around the Station Service Water pumps for i testing of SSW components. These loops are no longer 1 capable of performing this function. Thus, the FSAR is .! inconsistent with the SER. 1 1 {. j
Attachment to TXX 90011 i' January 15, $990 Page 106 of 304 FSAR Page ' (45..amenC%) Descrintion l 7.3 67, 68
Description:
(Correction) , ESTAS response times
- Justification:
Corrects text by deleting the measured reactor coolant system Tavg since it is not used for ESFAS actuation or in the plant design steamline break protection ; logic. ! Group: 3 FSAR Change Request Number: 89 610.14 Related SER Section: 7.3 l SER/SSER Impact: No ; 7.3 68 Descriptions (Correction) ESFAS response times , Justification j Correct ESFAS response times to be consistent with.the
" Control and Protection System" document. The times specified in this section represent the functional ,
requirements specified in the equipment specifications. ' (See also the description for page 7.1 3). . Group 3 FSAR Change Request Number: 89 610.15 Related SER Section: 7.3 ; SER/SSER lapact No ! 7.3 88
Description:
(Correction) Manual Initiation of Protective Actions (R.G. 1.62) i Justification: _ Corrects FSAR section 7.3.2.2.7 to show that CPSES l has replaced the MS!V bypass valve automatic valve actuators with manual actuators. All other applicable FSAR sections reflect this change. Group: 3 FSAR Change Request Number: 89 460 - Related SSER Section: SSER12 10.3.1 , SER/SSER Impact: No - Table 7.3 4 See Sheet No(s):14 - Description (Revision) ; Removal of Station Service Water recirculation line ; control valves, associated piping and orifices, i Justification: Deleted valves, 1-PV 4252 and 1-PV 4253, from the equipment actuated upon receipt of an safety injection injection signal. Since the SSW recirculation lines ' have been blind flanged, fluw is prohibited in the - loop. Thus, these valves no longer have an active . function. This change has been evaluated under the TU Electric 50.59 process as described in TXX-89718, dated - 9/28/89. Group: 2 l r
Attachment to TXX-90011 ! January 15. 1990 .l l Page 107 of 304 l FSAR Pepe ( (as amended) Descrintion j FSAR Change Request Number: 89-782.2 l Related SER Section: 9.2.1 SER/SSER !apact: Yes-SER section 9.2.1 states that $$W recirculation loops i are provided for testing components. This is inconsistent with this change. ; Table 7.5 3 See Sheet No(s):02 l Description (Update) f Conformance to Regulatory Guide.l.97, Revision 2 { Justification: . i Based on NRC request, in TXX 89253, dated 5/19/89. TV Electric committ3d to expand the utilization of the , steam generator wide range level instrumentation.to a ! Type B Category 1 accident monitoring variable, and i update the FSAR in a future amendent to reflect this designation. This change satisfies the requirements . of Reg Guide 1.97, Revision 2. ! l Group: 3 ; ! FSAR Change Request Number: 89 608.1 ! Related SSER Section: SSER12 APP T , SER/SSER Impact: No Table 7.5-5 See Sheet No(s):06 [ l Descriptions (Addition) l Conformance to Reg Guide 1.97, Rev. 2 Justifications i Added RHR heat exchanger inlet temperature as an . I accident monitoring D3 Backup variable. In lieu of the ; required containment sump water temperature variable. ! this variable in conjunction with containment atmospheric temperature and RHR heat exchanger outlet temperature variables, are considered adequate to monitor containment cooling. RHR heat exchanger inlet temperature is reflected in SSER#12 Appendix T as part i-of the CPSES design.-In a telephone conference call between the NRC and TU Electric (9/27/89), the difference between SSER#12 and the CPSES design was I noted. TU Electric has since added this variable to the CPSES design. , Group: 3- l FSAR Change Request Number: 89 695.1 Related SSER Section: SSER12 APP T - l SER/SSER Impact: No 1 1 Table 7.5-6
Description:
(Update) I Conformance to Regulatory Guide 1.97, Revision 2 Justification: Revised the variable function and category for'the ' control room area radiation monitors from " Key-E2" to -
" Backup-E3." TU Electric indicated in TXX 89253 dated 5/19/89, that fixed area monitors in the CPSES accident l
i
Attach ent to TXX 90011 January 15, 1990 :
.Page 108 of 304 l l FSAR Page l 1ALamended) Descrietion ,;
i l monitoring design are utilized as back up monitors ! l to portable monitors. Portable monitors are considered ! to be more reliable for detecting localized areas of ! higher contamination. i Group 3 : FSAR Change Request Number: 89 608.2 ! l Related SSER Section: SSER12 APP T SER/SSER Impact: Yes i SSER #12 does not list the control room area monitors [ as a deviation, j Table 7.5 7 See Sheet No(s):01 Descriptions (Update) l l Conformance to Regulatory Guide 1.97, Revision 2 i Justification:- ; l Based on NRC request, in TXX 89253. dated 5/19/89 TU Electric committed to expand the utilization of the i
- steam generator wide range level instrumentation to a i Type b Category 1 accident monitoring variable, and '
update the FSAR in a future amendment tc reflect this f I designation.-This change satisfies the requirements of l Reg Guide 1.97, Revision 2. ' Group: 3 ; FSAR Change Request Number: 89 608.3 ' Related SSER Section: SSER12 APP T SER/SSER Impact: No Table 7.5 7 See Sheet No(s):01 Description (Update) , l Conformance to Reg Guide 1.97, Rev. 2 , i Justification: A fourth wide range pressure transseitter (PT 3616) has ' been added to the CPSES reactor coolant system. The additional transmitter is utilized as one of the three i y required accident monitoring channels for RCS because of the improved instrument accuracy. This transmitter replaces the existing transmitter (PT-405) as an accident monitoring ~ channel. However, PT-405 is still a being utilized for a non-accident monitoring function. ! Thus, Table 7.5 7.is being updated to reflect the : change in tag numbers. Groups 3 FSAR Change Request Number: 89 695.2 [ Related SSER Section: SSER12 APP T ; SER/SSER Impact: No i Table 7.S 7 See Sheet No(s):02 i Descriptions (Correction) . Conformance to Regulatory Guide 1.97, Revision 2 , Justification: Corrects the upper range for the containment radiation f high range accident monitoring instrumentation. The t
~. ... . . - _ _ ___ .. Attachment to TXX 90011 ; Jonuary 15. 1990 : Page 109 of 304 . FSAt Page [ (as amended) Descrintion ; corrected upper range of 10E7 R/hr-meets the range l requirements of the Reg Guide for this variable. : Group: 3 i FSAR Change Request Number: 89 608.4 ! Related SSER Section: SSER12 APP T , SER/SSER Impact: No ' Table 7.5 7 See Sheet No(s):03 and 15 ! Description (Correction) _ l Conformance to Regulatory Guide 1.97. Revision 2 Justification: ' Corrects the upper range for steam generator blowdown. : liquid waste effluent and turbine building drains t radiation accident monitoring instrumentation. These taonitors are not required by the Reg Guide, but are designated as eccident monitoring instrumentation- i based on the CP7Ef4 plant specific design. Although the [ change in upper range for_these monitors is > conservative, it has no direct correlation to the Reg Guide. Group 3 I FSAR Change Request Number: 89 608.5 i Related SSER Section: SSER12 APP T SER/SSER Impact: No Table 7.5 7 See Sheet No(s):06 Descriptions (Correction) ; Conformance to Reg Guide 1.97, Rev. 2. Justification:
- Reference to Table Notes 7 and 11 reflect that RCP Seal Water Injection Flow instruments are seismically qualified for pressure boundary integrity and ,
seismically mounted. : Group: 3 - FSAR Change Request Number: 89 553.1 Related SER Section: 7.5 SER/SSER Impact: No Table 7.5 7 See Sheet No(s):09 Description (Correction) Conformance to Reg Guide 1.97. Rev. 2 Justification: SI Accumulator Tank Level instruments are seismically qualified for pressure boundary integrity and are seismically mounted as delineated by Notes 7 and 11. Group 3 FSAR Change Request Number: 89 553.2 Related SER Section: 7.5 SER/SSER Impact: No
Attachment to TXX 90011 January 15, 1990 i Page 110 of 304 I l ! FSAR Pepe (as amended) Descrintion Table 7.5-7 See Sheet No(s):11 Descriptions (Revision) Accident Monitoring j Justifications ; The accident monitoring variable "CCW Header i Temperature" instrument range has been revised. A i calculation was performed to determine the maximum I heat loads from the components cooled by component i cooling water (CCW). that would maximize CCW ; temperature. The calculation took into consideration i various plant conditions (i.e. startup, normal, l cooldown, refueling, refueling with core dump. S signal j and LOCA) for determining the highest temperature. , The resulting maximum CCW temperature was approximate 1y' i 136 degrees F. Based on this temperature..the "CCW -j Header Temperature" instrument range was changed from 0 200 to 30 150 degrees F. Although the new range deviates from the instrument range specified in Reg Guide 1.97, Rev. 2., the range is adequate to cover the
']
maximum anticipated CCW temperature'and improves the 4 accuracy and readability of the instrument. The accuracy improved from +/ 6.2 'to +/- 3.5 degrees F. j Note that this change is a_ plant enhancement that i improves the-accuracy and readability without changing ' the purpose and function of the instrument. No new failure mode is introduced by this change. This change , was evaluated under the TU Electric 50.59 process as ' described in TXX 89718, dated 9/28/89. : Group: 2 FSAR Change Request Number: 89 862.1 : Related SSER Section: SSER12 App T SER/SSER Impact: Yes The SER/SSER does not reflect CCW Header _ Temperature as a deviation. Table 7.5 7 See Sheet No(s):14
Description:
(Correction) Conformance to Regulatory Guide 1.97, Revision 2 Justification: ' Delete the E0 and 50 requirements for the safety chilled water flow instrumentation and added Note 7 for i clarity. This instrumentation is a designated CPSES ? nonsafety accident monitoring variable that is not required per the Reg Guide. However .the CPSES design' ; requires that this instrument'be designed to maintain - pressure boundary integrity. Group: 3-FSAR Change Request Number: 89 608.6 Related SSER Section: SSER12 APP T SER/SSER Impact: No 1 n - - -
, , - , w - - . . , - - . - , , . ..- _ ~ - - - , .
, ,._s.... n - ---+
-Attach: nt to TXX 90011 January" 15, 1990- .! , Page 111 of.304-l FSAR Page. .
f fas amended) Descrintion- ,
-Table.7.5 7- See Sheet No(s):14 I
Description:
(Addition) i Conformance to Reg Guide 1.97. Rev. 2~. Justification: i Added-RHR heat exchanger inletLtemperature as an i accident monitoring 03 Backup variable. In ' lieu of the' ' required containment sump water temperature variable. , this variable in conjunction with containment atmospheric temperature and RHR heat exchanger' outlet' r temperature variables are considered; adequate to .: measure containment cooling..See related description ! for T7.5-5 Sheet 6. ! Group: 3 ; FSAR Change Request Number: 89 695.3 ' Related SSER Section: SSER12 APP T - SER/SSER Impact: No: Table 7.5-7 See Sheet No(s):15 Descriptiont-(Update).. . .. Conformance to Regulatory Guide 1.97. Revision'2 1 Justification: Revised the variable _ function and category for the 1 control room area. radiation monitors from " Key-E2" to l.
" Backup E3." TU Electric indicated in TXX-89253. dated 5/19/89, that fixed area monitors in:the CPSES accident-monitoring design are utilized as?back-up monitors.to
- j. portable monitors. Portable monitors are considered; !,
f to be more reliable for detecting' localized areas'of highericontamination. ' a i Group: 3 FSAR. Change; Request Number:. 89-608.7 'i Related SSER Section: SSER12 APP T SER/SSER Impact:-Yes SSER #12 does not include the control room area monitors as a deviation.-
- Table 7.5-7 .See Sheet No(s):15
Description:
(Clarification) Conformancelto Regulatory Guide 1.97. Revision 2 ' Justification: $ Added the term " Area" to.the control room. RHR pump room and' PASS room to be consistent with the. y nomenclature in the Reg Guide and related sections _of. ' the FSAR. Group: 4 i FSAR Change Request Number: 89-608.18 ' Related SSER Section: SSER12' APP T ' SER/SSER Impact: No i }.,
' Attach 7;nt to_TXX-90011 January 15, 1990 Page.112.of 304 FSAR.Page (as.naended) Description Table 7.5 7 See Sheet No(s):15 and 22 Description (Correction)
Conformance to Reg Guide 1.97, Rev. 2 Justification: Added_line entry for radiation exposure' meter to-be consistent with the requirements of the Reg Guide even though this variable is not part of the CPSES plant specific accident monitoring design. Note 12 was added-to explain why this variable is not applicable to CPSES. Group 3 FSAR Change Request Number: 89-695.4 Related-SSER Section: SSER12 APP T SER/SSER Impact No Table 7.5 7 See Sheet No(s):16 Description (Clarification) Revises temperature range for atmospheric stability. Justification: Clarifies the temperature range from " 5 to +5" to i
"-5 to +15" degree F to provide consistency with.a '
revision to T2.3 34 submitted'in a previous amendment. These changes 'to the Delta Temperature callbration ~ range will eliminate rollover problems in recording instruments and ensure valid meteorological data' collection. Group: 4 FSAR Change-Request Nuaber: 89 566.2 Related SER Sectiore: 2.3 a SER/SSER 1mpact: No Table 7.5-7 See Sheet No(s):17 ,
Description:
-(Correction) ._
l Post Accident Sempling Instrumentation - pH Reg Guide 1.97 Justification: Corrects FSAR text to reflect the correct display range for pH_as specified in the vendor manual. Group: 3-FSAR Change Request Number: 89-671.2
~Related SER Section. 2242 SER/SSER Impact:.Wo Table 7.5-7 See Sheet No(s):21
Description:
(Update) - Conformance to Regulatory Guide 1.97, Revision 2 Justification: Deleted Note 1 since it is no longer applicable. TU Electric committed to expand the utilization of the ; steam generator wide range level instrumentation to a l Type B Category 1 accident' monitoring variable. ! Group: 3 i l
~!
Attach;cnt to TXX-90011 .;
. January 15,.1990 l Page 113 of 304 l
i FSAR Page l (as amended). Description i FSAR Change Request Number: 89-f08.8 I Related SSER Section: SSER12 APP T , SER/SSER; Impact: No i 7.64 Descriptions (Correction) .; Justification: t Deletes the reference to the Barton pressure i transmitter. This transmitter has been_ replaced with a Rosemount transmitter. ' Group: 3 FSAR-Change Request Number: 89-697.6: i Related SER Section:"7.6.1. t SER/SSER Impact: No j 1 Figure 7.7-18.
Description:
-(Revision)- Computation of Tave via'N-16 Power' System- ' Justification: Revised Figure-7.7-18 to' reflect the correct torms:
- associated.with the computation of Tavg via.the N 16' <
power system. This change.is a result of! hardware ; changes to the system (i.e. moving the compensation-term to the other side of the summation), to eliminate excessive noise on the output, which.was1 observed during testing..It should be note that the nardware change has no effect on-the computation of Tavg.. Group: 3 FSAR Change Request Nuoter: 89 704 Related SER Section:'.7.2 - SER/SSER Impact: No . Figure 8.2-9
Description:
(Revision) Replaces the CCPD on phase.A and phase C of transformer XST1.with potential transformer, J9stifications. The CCPDs.on phase A & C are replaced with-potential transformers. The CCPDs are currently leaking oil, which' could lead to their failure if lef t , unchecked. The. potential transformers will serve the-same purpose.: The~CCPD'will remain on phase B because of the wave trap installed on it. The phase B'CCPD will be replaced at a later date. Group: 3 FSAR Change Request Number: 89'-481.1 + Related SER Section: 8.2.1 SER/SSER Impact: No 8.3-25
Description:
(Revision) Deletes the operator action since design now ensures
'the reset of the static exciter voltage regulation (SEVR) circuit if the. emergency diesel generator (EDG) is required during coastdown following testing.
Justification:
Attach %ent .t'o TXX 90011' f
. January 15, 1990-Page 114'of 304 l
l FSAR Page-Description ; (48. amended) TU Electric has completed a design modification to the diesel generator exciter circuitry.that will ensure the- , energization of the exciter _upon receipt of an r emergency start signal ("S" or; manual emergency start)1 during coastdown (450 to 425 rpm) following testing. ! The ' manual operator _ action is no longer necessary and
~
is being-deleted from the FSAR. This is consistent: - with the' corrective actions for Significant Deficiency .; Analysis Report (SDAR)'CP-88 033'as reported to'the' ) NRC in TU Electric letters logged TXX 896324 and - TXX-89833.-dated August 30, 1989 and' December.7, 1989.. f respectively Group: 3 FSAR Change Request Number:'89-165 3' Related SER Section: 8.3.1 SER/SSER Impact:_ No l 8.3 46
Description:
(Revision) Containment electrical penetration primary protection ~ for.the containment motor space heaters fed from 480V
~
switchgear is changed to a fuse. Justification:
' Fuses have been installed in place of breakers for'thes -
l primary protection' for the; containment motor space l heaters fed from 480V switchgea'r to.better coordinate: with the penetration' thermal characteristics. Backup protection-remains circuit breakers. ..The' Technical . Requirements' Manual is being revised to reflect this; ' change. Group: 3 ) FSAR Change Request Number: 90-009-
~
Related SER Section: 8.4.1 l SER/SSER Impact: Yes . i The-fuse provides an acceptable means-of circuit-protection. This circuit was not described:in the' original SER, however.- this does change material reviewed in detail. by the NRC for' the draf t SSER.
- l. 8.3-49
Description:
-(Revision) l Containment electrical penetration backup protection
- for the Fire Protection / Detection System isschanged'to a fuse. s Justification. ,
A fuse has been installed as backup protection for the Fire Protection / Detection System. The previously described breaker'was not readily accessible for performance of-the technical' specification surveill- [ ances, since this required disassembly'of.the power supply in the Fire Detection ~ Panel 'and desoldering of ; the wires at the breaker terminals. The installation , of the fuse to provide protection alleviates this , concern. The Technical Requirements'Manuel'is being-
f. Attach:ent to TXX 90011 January- 15,=1990-Page 115 of 304 FSAR Page
- 185. amendet ) Descrintion revised to reflect this change.
The remainder of this section is reissued due to shifts'in the text. Group: 3 FSAR Change Request Number: 89-863.1 j Related SER Section: 8.4.1- ' SER/SSER !apact: Yes The fuse provides an acceptable means of circuit. protection. This circuit was not described in the original SER, however, this does change material-reviewed in detail by the NRC for the_ draft SSER, 8.3-50 :
Description:
(Revision) Containment electrical penetration-primary protection for the Containment Door Position Limit Switches-is changed to a fuse. Justification: A fuse has been installed as primary protection for the Containment Door Position Limit Switches. The previously described breaker was not readily accessible for performance of the technical specification ! surveillances, since this required'de-energization of part of'the P2500-Computer-cabinet and removal of circuit boards. The installation of.the fuse to provide protection alleviates'this' concern. . The Technical Requirements ~ Manual is being revised to reflect-this change.- Group: 3-FSAR Change Request Number: 89 863'.2 i Related SER Section: 8.4.1 SER/SSER Impact:.Yes-The: fuse provides an acceptable.means of circuit protection. This circuit'was not described in the original SER, however..this-does change material reviewed in detail by the NRC for the draft SSER, 8.3-52
Description:
(Clarification)- Justification: Clarifies that discussion is on Class 1E power buses and that all methods of separation' described apply l (not just a safety injection. signal breaker trip).- as identified in Table 8.3-11. Group: 4 j 4 FSAR Change Request Number: 89-795.1 Related SER Section: 8.4.5 i SER/SSER Impact: No , i 1
' Attach:ent to TXX 90011 {
January 15, 1990 > Page 116 of-304 FSAR Page . Description f? (as amended) 8.3-52
Description:
(Clarification) Clarifies FSAR by adding description of associated , cables routed beyond isolation device as described-in Table 8.3-10 and shown on Section 8.3 figures. , Justification:- Clarifies FSAR by adding description of associated I cables routed beyond isolation device as described in. , Table 8.3-10 and shown on referenced Section 8.3 figures. These-cables are. routed with their.. respective f train and a f ault on the connected non-Class ~ 1E Joad L will not degrade the. Class 1E power source (due.to'the isolation' device) or' Class'1E cables routed with the associated cables- (due toL this' isolation- combined 'with - the Class IE' circuit protection device and the-qualifi-cation and routing of associated cables).- Groups 3 FSAR Change Request Number: 89-795.3 3 Related SER'Section: 8.4.4
~
SER/SSER Impact: No . , - Does not conflict with'SER and design was previouly reviewed by the NRC in prior amendments to FSAR. 8.3-52
Description:
(Correction) Justification: Deletes figure note-numbers,'since.they have changed oa the latest figures and this-level'of detail:is unnecessary. Group: 4 FSAR Change-Request' Number: 89-795.2 i Related SER Section: 8.4.5 ; SER/SSER Impact: No 4; 8.3-54 Descriptions (Clarification)' Adds the non-Class IE AC' lighting inside, containment to= the lighting system' separation' description'. c Justification: . ._ 4 Adds the non-Class 1E AC lighting inside containment to the lighting system separation' description for-consistency. As previously described in FSAR Amendment 77, the containment lighting: transformers ! have two' Class'IE circuit breakers in series' which i meets the electrical separation ~ requirements Lof 'FSAR Section 8.3. Since the method of separation is the same'as that used for-the'other~ systems described in the subsection, the lighting-system. separation-description is being revised accordingly.
- . Groupi 3 FSAR Change Request Number
- .89-711.1 4
Related SER Section: 8.4.5 SER/SSER Impact: No The AC lighting inside the containment is not specifically discussed in the SER, but the separation
--+~: -- ,
L Attach 2Gnt to TXX 90011 January- 15, 1990 Page 117 of 304 FSAR Page (as amended)' Descrintion method discussed above has been reviewed by the NRC. 8.3 71
Description:
(Clarification) Clarification of the separation criteria used for power cables at CPSES.
' Justification:
Clarifies the separation criteria us'ed for " bare" cables consistent with1TXX-89359 dated June 5. 1989. Group: 3 FSAR Change Request Number: 89-559.1 Related SSER Section: SSER17 App. A SER/SSER Impact:-No-
- TXX-89359 was? issued June 5, 1989 to clarify TV Electric's response to SSER 17, Appendix A, Open Item E-28, and'has been reviewed by the NRC.
8.3-71
Description:
(Addition) Adds separation requirements for Class 1E power conduits and non-Class-1E instrument / control cable tray and cable.- Justification: The minimum separation between Class IE power conduit- l and.non-Class IE instrument _and control conduit (1/8") J was specified in FSAR Amendment 76.- The minimur, separ-ation between Class IE power ~ conduit?and non-Class IE j j instrument and control-cable tray and cable (1");is. added in thisJamendment as justified below. Control.and instrumentation-cable and ractway outside 1 of equipment uses a minimum separation'of one barrier 1 and one inch as described in the FSAR. This criteria i is based on a more restrictive test configuration of two cables- one inch: apart with no barrier-in Reference . 41-(Wyle Lab Test Report 48037-02).- This test demonstrated that cables with control or instrumenta-tion circuit energy levels have no adverse impact on each other-when installed per the tested configuration. ; If the installed configuration has'a non-Class IE control or instrumentation cable, it.followsi that this - 1 non-Class IE-cable has no adverse: impact on the'second ! cable irrespective of .its classification or energy level. If the second cable is a power cable, its impact on the non-Class-1E cable is-not safety -! i significant. Therefore. the separation-criteria for two control or instrumentation cables can be applied to i a configuration where only'the non Class 1E-cable is ! control or-' instrumentation and the other a' Class 1E '; power cable. The conduit (or an equivalent. wrap of ' woven silicon dioxide) around the Class IE cable provides the single barrier. ,' This change has been evaluated under the TU Electric
Attach 2snt to TXX 90011' January 15, 1990 Page 118 of 304 FSAR Page-(as amended) Description 10CFR50.59 procedures per TXX 89718 dated' September 28, 1989. Group: 2 FSAR Change Request Number: 89 762 Related SER Section:- 8.4.4 SER/SSER Impact: Yes New criteria has not been reviewed by the NRC. The criteria, however, is an extension of testing and criteria previously reviewed by the NRC. 8.3-72
Description:
(Editorial) Justification: Replaces Amendment'64 sentence inadvertantly deleted'in. FSAR Amendment 77. 'This description provided at-request of NRC. Amendment 64 revision barfis' retained since there is no change being made.. Group: 4 FSAR Change Request Number:. 89-559.3 Related SER Section: 8.3.1 SER/SSER lupact: No. 8.3-75, 76
Description:
(Clarification) Clarification of the-separation criteria used for power .' cable with a silicon dioxide wrap. Justification: The clarification'provided'is more specific . reflects-the design documents, and is consistent with the as-built plant and the information provided in' TXX-89359 dated June 5, 1989. Note that this sentence regarding woven silicon dioxide wrap'was'inadvertantly. deleted in FSAR Amendment 77 and is: included in FSAR Amendment 78-in its revised form. Group 3 FSAR Change Request Number: 89-559.2 Related SSER Section: SSER17 App. A SER/SSER Impact: No- ! TXX-89359 was issued June 5, 1989 to clarify TU Electric's response to SSER 17, Appendix A. 0 pen Item. E 28, and has been reviewed by'the-NRC. 8.3-92, 93
Description:
(Revision) 3 Revises criteria for the loading of cable trays ! above siderails.- Justification: ' The criteria for the loading of cable trays above ' siderails is revised by correcting the cable tray fill l criteria description to account for the exception and i to remove the list of situations which "may" require ; cables to extend above the siderails, making the j criteria more general and less confusing. . The-criteria to not extend cables above the siderails j of cable tray was based on good workmanship and' 1
~ Attach ent to TXX 90011-' s January 15, 1990 LPage 119 of 304 FSAR Page (as amended) Description general construction practice. TU Electric can-find no technical basis for this requirement not: ..
already addressed by other criteria such as thermal rating for power cables, cable tray: support dssign', fire protection, or cable separation criteria. Due to
= specific installation configurations, cables will extend above the siderails. The deleted list provided several areas _where this is expected to occur but, for such areas as the cable spreading. room,-space limitations may also require certain straight runs of
, tray'to exceed the-sidera11s,-even after reasonable: means of rerouting-cable or extending sidera11s have-been used.- Since some areas of the plant such as the~ turbine building were not reinspected', it is'possible.. for other areas of the plant to have-installations where cable extended above the siderail.- Since repulling cables, running new cable tray or' extending siderails requires'majorJrework, with the potential-to-damage cables or.to restack-them in-a.less organized manner.(i.e., even higher in the tray), and~since there is no safety benefit to be derived (since safety'._ concerns are addressed by other existing criteria) TU 1 Electric has chosen to- revise this. criteria to be clearly generic. The requirements. ensuring electrical and mechanical separation and avoidance'ofi. physical' damage hazards will be maintained whenever the siderails are exceeded. 'This change has been evaluated under the-TU Electric'10CFR50.59 procedure per TXX-89718, dated. September 28, 1989.- Group: 2-FSAR Change Request Number:'89-763~ Related SER-Section:'8.4.6 i SER/SSER lapact: Yes: i New criteria has not been reviewed'by-NRC. 1 8.3-94
Description:
(Editorial) i Justification: ! Text consolidation which deletes' details on fire _ stops 1 from Sec. 8~3.3.4 and refers to Sec.-9.5.1 for details. Group: 4 FSAR Change Request Number: 89 199 SER/SSER Impact: No Table 8.3-1A See Sheet No(s):02 and 03
Description:
(Correction) ! Corrects equipment tag numbers to reflect ( reclassification as non-Class IE, consistent with i previous FSAR change. Justification: ,I As part of FSAR Amendment 75, isolation transformers TXEC1, TXEC2 TXEC3, TXEC4, & T1EC3-3 were declassified from Class 1E to non-Class 1E.. This ! 1
Attach:Ont.. to TXX-90011 1 January 15. 1990. + Page 120 of 304 ;
~
FSAR Page . (as amended) Description ; change corrects the tag numbers to be consistent-with I the CPSES. numbering system for non-Class IE equipment. 4 Group: 4 , FSAR Change Request Number: 89 583.6 ~ Related SER Section: 8.4.5-SER/SSER Impact: No As reviewed by the.NRC for' Amendment 75 to FSAR.'the isolation transformers are no longer being used as' the j i s ol ati on' devi ce. ! i Table 8.3-1A. 1B See Sheet No(s): Sheet 8 and Table 8.3-2 Sheet 10 l
Description:
(Clarification) Clarification of Specific Note 9."of Tables 8.3-1A. 8.3-18 &~8.3-2 to explain that the start' times i listed after the automatic loading sequence'are estimates. Justification: The ' start tin.. associated with.the equipment listed are after the cc.,matic loading sequence and are estimates used to calculate the diesel generator loading at specific time intervals.- The=' start times' do not restrict plant operation' based upon diesel generator loading. Group: 4
?SAR Change Request Number: 89-547.1 Re'ated SER Section: 8.3.1 SER/SSER Impact:'No ,
Table 8.3-1B See Sheet No(s):02
Description:
(Correction) Corrects equipment, tag numbers to reflect reclassification as non-Class 1E. consistent with previous FSAR change. Justification: As part of FSAR Amendment 75, isolation transformers TXEC1. TXEC2 TXEC3, TXEC4. & T1EC3-3 were declassified from Class.1E to non-Class'1E. This change corrects the tag numbers to be consistentcwith. the CPSES numbering system for non-Classs IE equipment. Group: 4 FSAR Change Request Number: 89-583'.7 Related SER Section: 8.4.5 SER/SSER Impact: No . As reviewed by the NRC for Amendment 75 to FSAR, the isolation transformers are no longer being used as the isolation-device. { Table 8.3-2 See Sheet No(s):01 thru 08, 11
Description:
(Correction) Correction of column heading from " START TIME AFTER SIAS" TO'" START TIME AFTER BOS". Also added the abbreviation "BOS" (Blackout Signal).
Attach:ent to TXX 90011-
' January- 15, 1990
~
Page 121 of 304 . FSAR Page -> (as. amended) Descrintion i JusEification: > Amendment 76 revision:to' Table 8.3.2 inadvertantly_ listed "SI AS" (Safety ~ Injection Actuation-Signal) ' . instead of "BOS" (Blackout Signal), Table 8.3 2 is ; based.on a Loss of Offsite Power (Blackout)-condition. Group: ,. FSAR Change Request Number: 89 547.2: > Related SER Section: 8.3.1 SER/SSER Impact: No' Table 8.3 2 See Sheet No(s):03-
Description:
(Correction) . _ Corrects equipment tag numbers to reflect reclassification as non Class IE, censistent-with previous FSAR change..
- Justification:
- As part of FSAR AmendmentL75, isolation transformers ['
L TXEC1, TXEC2, TXEC3, TXEC4, & T1EC3-3 were _ declassified from Class 1E to non Class 1.E. .This change corrects the tag' numbers to be consistent with I the CPSES numbering system for non-Class 1E equipment. ! Group: 4 FSAR Change Request Number:-89 583.8 Related SER Section: 8.4'5 . li SER/SSER Impact: No _ . As reviewed by the NRC for Amendment 75 to FSAR, the _ isolation transformers are no longer being used as the - isolation device. _j Table 8.3-9 See Sheet No(s):02
Description:
J(Correction) Adds the 180 KW duct heater to the 480V main bus load assignments table. Justification: l Consistent with existing Figure 8.3-7, the 180 KW duct I heater is added to the 480V main bus load assignments ( for Switchgear.1B4 to: reflect theJas-built plant. l Group: 3 3 FSAR Change Request Number: 89-721.2 Related SER Section: 8.3.1 SER/SSER Impact:'No 2 Table 8.3-10 See Sheet No(s):02
Description:
(Correction) Corrects equipment tag numbers to reflect I reclassification as non-Class IE, consistent with " previous FSAR change. Justification: As part of FSAR Amendment 75, isolation transformers TXEC1, TXEC2, TXEC3, TXEC4, T1EC3-3 & T2EC3-3'were-declassified from' Class 1E to non-Class 1E. This change corrects the tag numbers to be consistent with r - - - -- ..,. . . , , e.-- w .- .'
u ^ h
' Attach 2ent to TXX-90011 January .5.-1990 --.
Page 122 of 304-FSAR Page (as amended) Dgscription the CPSES numbering system for non Class IE equipment. Group: 4 FSAR Change Request Number: 89-583.1 Related SER Section: 8.4.5 SER/SSER Impact::No As reviewed by the NRC for Amendment 75 to FSAR, the isolation-transformers are no longer being-used as the isolation device. Table 8.3-11 See Sheet No(s):03, 06'and'07
Description:
-(Correction) Corrects equipment tag numbers'to reflect reclassification as non Class 1E.-consistent with: ' previous FSAR change. Justification: As'part of FSAR Amendment-75, isolation transformers TXEC1, TXEC2, TXEC3,' TXEC4, &'TIEC3 3 were declassified from Class 1E to non-Class IE. This changeLcorrects the tag numbers to be consistent with the CPSES numbering system for non-Class IE equipment. The circuit breaker cubicle numbers are also updated consistent with the FSAR Amendment-75 figure changes, where two circuit breakers-in series were.provided.for electrical separation. Group: 3 FSAR Change Request Number: 89-583.2 Related SER Section:.8.4.5 SER/SSER Impact: No- , j As reviewed by the NRC for Amendment 75 to'FSAR, the j isolation transformers are no longer'being used as the ; isolation device. ' Figure 8.3-1 Description -(Update) g Figures are updated to reflect "as-built" drawings. Justification: " Figures are updated to' reflect "as-built" drawings, i Additional details consistent with site-drawings have ; been added.- Incorporated-in these updated figures.are -I changes which do not impact the operation of safety-systems, voltage profile diesel generator load calcu- , lation. battery load calculation, or existing FSAR-text 1 or tables, such as described below: Editorial changes, changes -to reference drawing nuinbers . and tag numbers:
~
Changes to physical dimensions, locations'& elevations; Additions or deletions of auxiliary relays which do.not perform protective and/or safety functions: Changes to ground resistor tap settings:
Attachaont.- to TXX 90011 January 15. 1990 Page 123 of-304 FSAR Page (as amended) Description MCC spaces converted'to instrument compartments: Shifting of loads on the same MCC bus: and Decreases or increases in load' or current on the MCC branch circuits and'down (the electrical-distribution-systems) which do not.. impact the voltage profile.- the diesel load or,the battery load calculations and~ do not impact the FSAR text or tables.- Groups 3 FSAR Change Request Number: 89-687.1 Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3 2 See Sheet No(s):01
Description:
(Revision) . Replaces the CCPD on phase A and phase C of transformer , XST1 with potential transformer. Justification: i The CCPDs on phase A & C are replaced with-potential transformers. The CCPDs are currently- R leakingioil. which could lead to their failure if left
' unchecked. The potential transformers will serve the i same-purpose. The CCPD will remain'on phase B because 1 of the wave trap installed on it. The phase B CCPD
~'
1 will be replaced at a-later date. ! Group: 3 ' l FSAR Change Request Number: 89-481.2L Related SER.Section: 8.2.1
- l SER/SSER Impact: No Figure 8.3-2 See Sheet No(s):1 thru 3 l
Description:
(Update) Figures are updated to reflect'"as-built" drawings. { Justification: ' Figures are updated:to reflect "as-built" d'rawings. ' i See detailed description provided under Figure 8.3-1. Group: 3 ' FSAR Change Request' Number: 89-687.2 ; Related SER Saction: 8.3.1 SER/SSER I cett: No Figure 8.3-5 I See Sheet Nots):1 & 2
Description:
(Update) li Figures are updated to reflect "as-built" drawings. Justification: Figures are updated to reflect "as-built" drawings. See detailed description provided under Figure 8.3-1. Group: 3 FSAR Change Request Number: 69-687.3
Attach 2Ent 'to TXX-90011
' January 15, 1990 Page:124 of-304 FSAR Page (as amended)- Deserintion Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-6 See Sheet No(s):1 thru 3
Description:
(Update) Figures are updated to reflect "as-built" drawings. Justification:- Figures are updated to reflect "as-built" drawings. See detailed description provided under Figure 8.31. Group:-3 FSAR Change Request Number: 89 687.4-Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-7 See Sheet No(s):02 Descriptions (Corre'ction) Corrects breaker rating for the 180 KW duct heater. Justification: The breaker rating for the 180 KW duct heater (location- i
- 480V Switchgear 184, cubicle 108) has been changed !
from 300A to 400A to reflect the as-built plant condi-tion. The actual load has not been changed. Group: 3 . FSAR Change Request Number: 89-721.1-Related SER Sections;8.3.1 SER/SSER Impact: No Figure 8.3 7 See Sheet No(s):1 &-2
Description:
(Update) Figures are ' updated to reflect "as-built" drawings. Justification: Figures are updated to reflect "as-built" drawings. . See detailed description provided under Figure 8.3-1. i Group:-3 j FSAR Change Request Number: 89-687.5:- Related SER Section: 8.3.1 SER/SSER !apact: No
- ({
l Figure 8.3 8 See Sheet No(s):1 & 2
Description:
(Update) Figures are updated to reflect "as built" drawings. l Justification: Figures are updated to reflect "as-built" drawings, d See' detailed description provided under Figure 8.31. Group: 3 FCAR Change Request' Number: 89-687.6 Related 5ER Section: 8.3.1 SER/SSER Impact: No l 4
v .- Attach cnt to TXX-90011.
' January 15, 1990 Page 125 of 304 FSAR Page (as amet)ded)- Descrintion Figure 8.3 9 See 0heet No(s):1 thru 4
Description:
(Update) Figures are updated to reflect "as'-built" drawings. Justification: Figures are updated to reflect "as built" drawings.
-See detailed descriptica provided under-Figure 8.3 1.
Group: 3 FSAR Change Request Number: 89 687.7 Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-10 See Sheet No(s):01
Description:
'(Correction) Corrects equipment-tag numbers to reflect-reclassification'as non-Class 1E consistent with-previous FSAR change.
-Justification: ~
As part of FSAR Amendment 7G, isolat' ion transformer T1EC3 3 was declassified from Class IE to non-Class 1E. This change corrects the tag number to be consistent. ; with the CPSES' numbering system for non-Class 1E equipment. i! Group: 4 FSAR Change Request Number: 89-583.3 Related SER Section: 8.4.5 SER/SSER-Impact: No + As reviewed by the NRC for Amendment-75 to FSAR, the1 isolation transformers are no-longer being used as the isolation device. Figure 8.3-10 Sea Sheet No(s):01
Description:
(Correction)' Deletes the "S" trip on the containment lighting-transformer. and the vent control cooling unit cooler / - chilled water motor operated' valves (MOV's). i Justification: 'l The containment lighting-transformer and vent control cooling unit cooler / chilled water NOV's'have two Class 1E circuit breakers:in series', which meetsnthe ! eletrical separation requirements of FSAR Section 8.3. The control circuit "S" contact has been removed (it is - not needed for separation). This change is consistent with information provided in FSAR Amendment 77 for 2 11 Table 8.3-11. ; Group: 3 ' FSAR Change Request Number: 89-711.3 Related SER Section: 8.4.5 SER/SSER Impact: No - i The separation method discussed-above has ! been reviewed by the NRC. I
Attachu nt to TXX 90011 January 15, 1930 -Page 126_of 304 FSAR Page (as amended) Description Figure 8.3 10 See Sheet No(s):02 Description (Correction) Deletes the "S" trip on containment lighting transformer and vent control cooling unit cooler / chilled water motor operated valves (H0V's). Justification: The Containment '11ghting transformer and vent control cooling unit cooler / chilled water MOV's have two Class 1E circuit breakers in series,~which meets the electrical separation requirements of FSAR Section 8.3. The control circuit "S" contact has been removed (it:is-not needed fo?-separation). _This change is consistent with information provided in FSAR Amendment 77 for
- Table.8.3-11.
Group: 3 , . FSAR, Change Request Number: 89-711.4
-Related SER Section: 8.4.5
.SER/SSER Impact: No l The separation method discussed above has been reviewed
.by the NRC. -i Figure 8.3-10 See Sheet No(s):1 & 2
Description:
(Update) '] Figures are updated to reflect "as-built" drawings. Justification: ' Figures are updated to reflect "as-built" drawings. See- detailed description provided under Figure 8.3-1. 1 Group: 3 i FSAR Change Request Number: 89-687.8 ~! Related SER Section: 8.3.1 SER/SSER 1mpact: 'No Figure 8.3-11 See Sheet No(s):01
Description:
(Revision) Hydrogen Purge Exhaust _ System power supply cables are reclassified as associated. Justification: j Hydrogen Purge' Exhaust fan and' filter heater power ! supply. cables are reclassified as associated since these loads do not supply a required safety function. At this time, the fans;and heaters themselves will be maintained with Class 1E qualification and documenta- i tion but do-not supply'a_ required safety function.' This drawing revision is consistent with FSAR Amendment 76 changes in Sections 6 and 17 which reclassified the-Hydrogen Purge Exhaust System-as a backup for the Hydrogen Recombiner. The Hydrogen Purge Exhaust System remains listed as a potential diesel generator load (Table 8.3 1B). ,' Group:'3- . i FSAR Change Request Number: 89-729 i Related SER Section: 8.4.5 i
Attach;ent to TXX 90011 . January 15. 1990 =i Page 127 of 304 FSAR Page (as amended) Descrintion SER/SSER Impact: No See Sheet No(s):01', 02 and 03.
~
Fig"re 8.3 11
Description:
(Correction) Corrects equipment tag numbers to reflect reclassification as non Class 1E, consistent with. previous FSAR change.- , Justification:
-As part of FSAR Amendment 75, isolation ,
transformers TXEC1; TXEC2, TXEC3, & TXEC4 were' declassified from Class 1E to non-Class IE. This; ) change corrects the tag numbers.to be' consistent' with the CPSES numbering system for non Class 1E-equipment. Group: 4 FSAR Change Request Number:. 89-583.4 - Related SER Section:-8.4.5 SER/SSER Impact: No . As reviewed by the NRC for Amendment 75 to FSAR, the I isolation transformers.are no longer being used as the isolation device. Figure 8.3-11 See Sheet No(s):1 thru 3
Description:
(Update) Figures are updated.to reflect."as-built" drawings. Justification: Figures are updated to reflect'"as-built" drawings. ~ See detailed: description provided!under Figure 8.3-1. Group: 3 -
- FSAR Change Request Number
- 89-687.9 l- Related SER Section: 8.3.1
[ SER/SSER Impact:'No ' Figure 8.3 12 See Sheet No(s):1 & 2 *
Description:
(Update) ' l Figures are updated to reflect "as-built'" drawings. Justification: Figures are updated to reflect "as-built" drawings. - See detailed description provided under Figure'8.3-1. Group: 3 FSAR Change Request Number: 89-687.10-Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-13 See Sheet No(s):1 & 2 'I
Description:
'(Update). Figures are updated to reflect "as-built" drawings. Justification: Figures are. updated to reflect "as-built" drawings. See detailed description provided under Figure 8.3-1.. Group: 3 1 FSAR Change Request Number: 89-687.11 s
'I LAttach:snt to TXX-90011-January 15. 1990 i Page 128 of 304 FSAR Page (as amended) Description Related SER Section: 8.3.1 '
SER/SSER impact: No Figure 8.3-14 See Sheet No(s):01 and-02
Description:
(Revision) Deletes references to values of adjustable ; instantaneous trip setpoints for the D.C.-system. Justification:~ t These setpoints are unnecessary detail withinLthe FSAR
~
L and are already controlled by-the design calculation- .i and Protective Device Setpoint Drawings. Group: 3 FSAR Change Request Number: 89-458.1 i Related SER Section: 8.3.1 i
-SER/SSER Impact: No Figure 8.3-14 See Sheet No(s):01.and 02 Description (Clarification)
Clarifies existing Note 6 to be consistent with notes provided for Figure 8.3-15B. Justification: Note 6 is. separated into two notes. The.first note (6) identifies that when an-"*" is placed next to a value for am interchangeable trip unit it indicates that the trip unit is located withir, a 225- A. frame size breaker. This first note.is applicable to the Distribution Panels. The second note (13) indicates that 225 A frame, and larger frame size-breakers have an interchangeable
. trip unit with an adjustable instantaneous magnetic trip. The second note is applicable to the 1 Distribution Panels. Battery Chargers.and Switchboards. '
Group: 4 FSAR Change ~ Request Number:-89-458.5 Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-14 See Sheet No(s):1 & 2-
Description:
(Update) . . Figures are updated to reflect "as-built" drawings. ; Justification: , Figures are updated to reflect "as built" drawings. See detailed' description provided under Figure 8.3-1. Group: 3 FSAR Change Request Number: 89-687.12 Related SER Section:.8.3.1 SER/SSER Impact: No Figure 8.3-14A See Sheet No(s):01
Description:
(Clarification) Clarifies existing Note 4 to be consistent with notes provided for Figure 8.3-158. Justification:
Attachm nt to TXX 90011 January 15, 1990-Page 129 of 304. FSAR Page (as amended) Description Note 4 is. separated'into two notes. . The first. note (4) identifies that when an "*" is placed next to a value for an interchangeable trip unit it indicates that the trip unit is located within a'225 A frame size breaker. This first note .is applicable to Distribution Panels . The second note (9) indicates.that 225 A frame and larger frame size breakers have an interchangeable trip with an adjustable ~1nstantaneous magnetic trip.- The second note is applicable to the: Distribution Panels. Battery Chargers and the Switchboards. Group: 4 FSAR Change. Request Number:- 89 458.6 Related SER Sections 8.3.1 SER/SSER Impact: No Figure 8.3 14A See Sheet No(s):01 and 02 Descriptions (Revision) Deletes references to values of adjustable instantaneous-trip setpoints for the D.C. system. Justification: i These setpoints are unnecessar.y detail'within the FSAR I and are-already controlled by-the' design calculation and Protective Device Setpoint Drawings. Group: 3' FSAR Change Request Number: 89-458.2 Related SER Section: 8.3.1 SER/SSER Impact: No L Figure 8.3-14A See Sheet No(s):02' !
Description:
(Editorial) ( Deletes Note 4 and Note:11 since they are not= applicable to the Figure. : Justification: . 1
. Note 4' and Note 11 are only applicable to- Distribution i Panels and'there are none on this figure.
Group: 4 .
-i FSAR. Change Request Number: 89 458.7
- t. Related SER Section: 8.3.1 p SER/SSER Impact: No Figure 8.3-14A See Sheet No(s):1 & 2 .
Description:
(Update)- l Figures are updated to reflect "as-built" drawings. l Justification: . l Figures are updated to reflect "as built" drawings. See detailed description provided under Figure 8.3-1. .1 Group: 3. d FSAR Change Request Number: 89-687.13 j Related SER Section: 8.3.1 j
'SER/SSER Impact: No i l
I J
Attac'h:ent' to TXX 90011 l January 15, 1990 Page'130-of 304~ j I FSAR Page (as amended) Descrintion Figure 8.3 15' See Sheet No(s):1 thru 3 Descriptions (Update) Figures are updated to reflect "as built" drawings. Justification: ' Figures are updated to reflect t'as built" drawings.
- See detailed description provided under Figure 8.3-1.
Group: 3 , FSAR Change Request Number: 89 687.14
- Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-15A ' See Sheet Nc(s):01 Descriptions (Correction)
Corrects' equipment tag numbers to reflect-reclassification as;non Class IE,. consistent with previous FSAR change. Justification: As part of FSAR Amendment 75, isolation transformers TXEC1, TXEC2, TXEC3 & TXEC4 were' ( declassified from Class IE to non-Class IE. This change corrects the tag numbers to.be consistent with the CPSES numbering system for,non-Class 1E equipment. Group 4-FSAR Change Request Number: 89-583.5-Related SER Section: 8.4.5' ' SER/SSER Impact:-No As reviewed by the NRC for Amendment 75 to FSAR. the isolation transformers-are.no longer being~used as the - isolation device. Figure 8.3-15A See Sheet No(s):1 & 2
Description:
(Update) ' Figures are updated to reflect "as-built"' drawings. Justification: Figures are updated to reflect' "as-built" drawings. See detailed description provided under Figure 8.3-1. . Group: 3 FSAR Change Request Number:'89-687.15 Related SER Section: 8.3.1 SER/SSER Impact: No Figure 8.3-15B See Sheet No(s):01 and 02 !
Description:
(Revision) ! Deletes references to values of adjustable instantaneous trip setpoints'for the D.C. system. _ Justification: l These setpoints are unnecessary detail within the FSAR and are already controlled by the design calculation and Protective Device Setpoint Drawings. Group: 3 FSAR' Change Request Number: 89 458.3
Attach::nt to TXX 90011 EJanuary. 15.-1990 Page 131 of 304 FSAR Page (as amended) Descrintion Related SER Section:~8.3.1 SER/SSER. Impact: No Figure 8.3 15B See Sheet No(s):1 & 2
-Description: (Update)
Figures are updated to reflect "as-built" drawings. Justification:-
. Figures are updated to reflect "as-built"' drawings.
See detailed description provided under Figure 8.3-1. Group: 3 FSAR Change Request Number: 89-687.16 Related SER Section: 8.3.1= SER/SSER Impact: No Figure 8.3-15C
Description:
(Revision) Deletes references'to values of. adjustable instantaneous _ trip setpoints for the D.C. system. Justification: These setpoints are unnecessary detail within the FSAR- l and are already controlled by the design calculation ' and Protective Device Setpoint Drawings. Group: 3 FSAR Change Request Number:-89-458.4 Related SER Section: 8.3.1 SER/SSER Impact:-No ' Figure 8.3-15C
Description:
.(Addition) Adds Note 5 to be consistent with Figure 8.3-15B. Justification:- 1 Note 5 indicates that 225 A frame and. larger frame size breakers have an interchangeable trip unit with an-adjustable instantaneous magnetic trip, 4 Group: 4 FSAR Change Request" Number: 89-458.8- ' Related SER Section: 8.3~.1 4 SER/SSER. Impact: No j Figure 8.3-15C
Description:
(Update) Figures are updated to reflect "as-built": drawings. 4-Justification: Figures are updated to reflect "as-built" drawings. See detailed description provided under Figure 8.3-1. { 1 Group: 3-. FSAR Change Request Number: 89-687.17
~
Related SER Section: 8.3.1 : SER/SSER Impact: No a 9.1-2
Description:
(Addition) s Adds information re: treatment of the protective cover -! on each fuel assembly aftersvisual inspection to con- J firm that the assembly'has not been damaged during 4 shipment and remains suberitical during storage. 1 i
Attach ent . to TXX 90011 January 15, 1990 Page 132 of 304 C FSAR Page (as almended) Description Justifications. The information concerning the treatment of the-pro-tective cover on each fuel assembly after visual in-spection is added in response to an NRC Staff request.- The opening at the bottom of the protectiva cover en-sures that the fuel assemblies remain suberitical in the fuel storage racks. Group::3 FSAR Change Request Number: .89 663 Related SER Section: 9.1.1: SER/SSER Impact: No 9.1-32, 33
Description:
(Addition) Add paragraph describing limitations on fuel' assembly movements. Justification: Incorporate-licensing basis commitment intolthe FSAR. This commitment was made with the staff in letter TXX 89760 dated-October 23, 1989. Group: 3 I FSAR Change Request Number: 89-793 SER/SSER Impact: No 9.1-57, 58 See Page No(s):59
Description:
(Addition)- IncorporatesresponsetoNRCrequestforadditional; information concerning the handling of heavy-loads. Justification: As part of its-review of the'CPSES FSAR.Lthe NRC Staff requested that certain information be provided regard-ing the handling of heavy loads. This information was provided in the form of Q&R010.32 and .33.- (See . TXX-4395, dated January 22.-1985.) . These Q&R numbers I were already assigned to another issue (safe shutdown- ) and alternate shutdown) byfthe NRC. and these are' pre-sented in the FSAR. 'The information regarding the handling of heavy loads is now being incorporated into l the .FSAR in response to.the original NRC Staff request. Group: 3 FSAR. Change Request Number:-89-669 ;! Related SER Section: 9.1.4; SSER6. 9.1.4 SER/SSER Impact: No'- Table 9.1-1.1
Description:
(Cl arifi cati on) . Revises table to provide consistency with text and.to. i describe proper exponential- value. 1 Justification: 1 Revises FSAR table to provide' consistency with FSAR ,y text and to describe proper exponential value, o Group: 4 FSAR Change Request Number: 89-485-Related SER Section: 9.1.3
Attach;ent- toLTXX-90011-January- 15. 1990-Page 133 of 304 FSAR Page (as amended) Descrintion SER/SSER Impact: No Figure 9.1-13 See Sheet No(s):01. 02 and 04
Description:
(Correction) Addition of LC-2 notation-to indicate valves which will remain locked closed during-the construction of Unit 2 on the figure, Justification: Selected valves will remain locked closed to serve as'a boundry for Unit I during Unit 2 construction. Group: 3 FSAR Change' Request Numbert 89-614 Related SER Section: 9.1.3 SER/SSER Impact: No Figure 9.1-13 See Sheet No(s):03-Description (Update) Minor figure updates. Justification: No justification necessary. These figures contain changes of the following type:
- 1. Manual vent or drain valves - addition, removal, re-location, valve number.
- 2. Manways or handways - addition. removal, or re-location.
3', Editorial - spelling editorial or drafting errors which cannot impact technical meaning of the diagram
- 4. Line numbers or'line sizes <
- 5. Flanges or reducers addition, removal or re-location.
- 6. Piping or instrumentation ' physical. interconnection changes which have no impact on the operation /func-tion of system and equipment.
- 7. Manual valves - valve numbers or physical location changes which have:no impact on the operation /func-tion of system and equipment .
- 8. Elevation changes.
Group: 4 I FSAR Change Request Number: 89-732-SER/SSER Impact: No a 9.2-4
Description:
(Correction) Removes reference of-sodium bromide addition to the circulating water, and adds bromine based chemical addition to the service water ~ system. Justification: , The reference of sodium bromide addition to the - circulating water has been removed, and the addition ! of the bromine based chemical to the service water system has been added. These changes reflect-the plant configuration for. chemically controlling. organic fouling at the time of fuel load, v _ __ _a~ - - -
Attach 2ent- to TXX-90011 January- 15, 1990 . Page 134 of 304 l F5AR Page (as amended) Description , Group: 3 , FSAR Change Request Number:- 89-598.1 , Related SER Section: 9.2.1- : SER/SSER Impact: No , 9.2 4
Description:
(Revision) Adds a paragraph to Section 9.2.1.2.1 to describe the c'
- orrosion inhibiting chemicals being added to the Service Water for corrosion control.
Justification: . l Due to Placite removal corrosion inhibitors are added to the Service Water System.to minimize corrosion to -r the uncoated carbon steel pipe-in the service water - System. This change along with the: change to' Figure 9.2-1 Sheet I will reflect the current-corrosion-
?
system. Group: 3 . FSAR Change Request Number: 89-759.1 . Related SER Section: 9.2.1-SER/SSER Impact: No 9.2-10
Description:
(Clarification) Testing requirements of the Station Service Water Syst- ; em cross-connect valves between~ unit 1 & 2. Justification: Clarify the testing requirements,of the Unit l'& 2. Station Service Water. System cross-connect manual val-ves XSW-0006, XSW-0007' XSW-0008 XSW-0028. and-XSW-0029.These valves need to be stroked at least= quarterly through=the full range to insure that.the valves are in operating condition. This FSAR change incorporates the surveillance testing requirements ~of e the SSW System. cross-connect valves as discussed-with NRC and transmitted by TXX-88948, dated 12/16/88. Group: 3 . FSAR Change Request Number: 89 769 Related SER Section: 9.2.1 SER/SSER Impact: No 9.2-15 Descriptions (Clarification) 1 Clarifies'the. title of certain heat exchangers within the Gaseous. Waste Processing System.to be consistent . with FSAR Section 11.3. _
' Justification:
Group:.4 FSAR Change Request Number: 89-639.1 1 Related SER Section: 11.2.2 SER/SSER Impact: No i c
. _ . . . - . - - - _ _ _ - _ _ _ . - - - _ _ _ _ . - _ _ _ . - , _ , _ < + - - _ . _ . -
Attach: nt to TXX-90011 January 15. 1990 Page 135 of 304 FSAR Page , (as amended) Description 9.2-17
Description:
(Correction)- Corrects the ANSI Safety Classification from Safety Class-3-to non Safety Class.5. Justification:. The two catalytic recombiner heat exchangers and the
<two waste gas compressor seal water coolers have been'
. changed'from Safety Class 3fto non-Safety Class ~5 to match as-built conditions consistent with Amendment 76.
Group: 3 FSAR Change Request 1 Number: 89-639.2 Related SER Section: 11.2.2 SER/SSER Impact: No-9.2-27, 30
Description:
(Revision) Adds the manual operation of the Reactor Makeup Water System as a source for the Component Cooling-Water-System surge tank normal makeup water. Justification: The addition of the Reactor Makeup' Water System as a source for the Component Cooling Water' System (CCWS) surge tank normal makeup water. allows the CCWS surge tank normal makeup water te be obtained from the manual' operation of-either the Demineralized Water-System or .
.the Reactor Makeup. Water System.- '
Group: 3 FSAR Change Request Number: 89-784.1 Related SER Section:'9.2.2 SER/SSER Impact: Yes The SER states that makeup to.the: surge tank is pro- ,i vided by the Domineralized. Water System. This change adds the Reactor. Makeup Water System as an additional source of makeup to the surge tank, 9.2 31
Description:
(Revision)~ . Adds'the manual operation of the Reactor Makeup Water System as-a source for the Component Cooling Water-System surge tank normal makeup' water. , Justification:- .I The addition of the. Reactor Makeup Water System as a source for the Component Cooling Water System (CCWS). , surge tank normal makeup water allows the CCWS surge i tcnk normal' makeup' water to be obtained'from the manual ' operation of~either the Demineralized Water System or the Reactor' Makeup Water System. Group: 3 FSAR Change Request Number: 89-784.2 Related SER Section: 9,2.2
Attach ent to TXX 90011
= January. 15, 1990 ,
Page 136 of 304 .l FSAR Page (as amended) Descriotion i SER/SSER Impact: Yes The SER states that makeup'to the surge. tank is pro- , vided by the Demineralized Water System. This change i adds the Reactor Makeup Water System as an additional i source of makeup to the surge tank. 9.2-31
Description:
-(Clarification) . 4 Clarify the accumulator tank sizing requirements for 30 ; minutes af ter an instrument air header low pressure ,
- conditon, Justification
- .
i The design basis of the CCW/ safety chiller. accumulators is'to provide air to the condenser water-regulating l valves to permit the continued operation for 30 minutes ' following a loss of.the non safety Instrument Air Syst-em. At an instrument air header pressure of 80 psig decreasing.- operators begin^to secure certain air cper-ated valves in a safe, throttled position as, required. ; FSAR is revised to clarify that the,designLbasis of the' accumulator sizing is 30 minutes of air supply follow-ing an instrument air header' low pressure condition *,in t lieu of 'at low pressure alarm at'70 psig. Group:-3 , i FSAR Change Request Number: 89-788 l Related SER Section: 9.3.1 ! y SER/SSER' Impact: Yes . SER page 9-15 indicates that only' Aux Feedwater flow control valves, steam' supply valves to turbine driven AFW pump, and control room air dampers are provided r with air accumulators. The SER needs to be revised to add accumulator to ccw/ chiller condenser valve, a 9.2-43
Description:
(Correction)- Deletes the Testing and Inspections requirements for. !~ the Potable Water Well Pumps. Justification: The Testing and Inspection requirements for the Potable l Water Well Pumps have been deleted. The Surface Water Pretreatment System'is the primary source of Potable Water. The Potable Water Well Pumps are used only as a backup source during~ Surface Water Pretreatment System outages. A 30.000 gallon Potable Water: Storage ; Tank provides a buffer to prevent an equipment outage from affecting site supplies. The Potable. Water.Well Pumps are non-safety equipment. Therefore, Performance and Testing activities are-not required on.these pumps-since they are only one source of Potable Water to the site. Group: 3 7
- FSAR-Change Request Number
- 89-606 Related SER Section: 9.2.4 SER/SSER Impact: No ,
1 _ , , . .. , ~~_
' Attach ent to'TXX 90011:
January 15. 1990:. -
-Page 137,of 304 FSAR Page-(as. amended ) - Description 9.2 51, 52 : Description (Correction) .
Deletes specific volumes related to the Condensate Storage Tank in Section 9.2.6 and references Section' 10.4.7.2 or Table 10.4-8 -(as noted in- text).. Justification: Details regarding the Condensate Storage Tank are more appropriately presented in:FSAR Section 10.4.7.2 or-Table 10.4-8 (as noted in text).-.This change.will eliminate any unnecessary future changes to=9.2.6 : Group: 3 FSAR Change Request Number: 89-426.2 Related SER Section: 9.2.6 - SER/SSER Impact: Yes . . The discussion regarding the Condensate Storage-Tank-(volume and cooldown rate) should be clarified for consistency with.FSAR section 10.4.7.2.- 9.2-53
Description:
(Editorial). ' Corrects typo: changes transmitter function fr'on
" recording" to " monitoring".
Justification:- Group: 4 'j FSAR Change Request Number: 89-292.4~ ] SER/SSER Impact: No L; 9.2-54 See Page No(s):55. 57. 58. and 59
~
Description:
(Correction). . Reflects the' configuration of the. Water Pre-Treatment System at the time of: fuel load. Justification: These changes are'to reflect.the configuration of the ; Water Pre-Treatment System at the time of fuel load. ! The flow to the Pre-Treatment System has been revised-to 430 gpm..and 400 gpm to the R.O. System. This 4 reflects the capacities of.the existing Reacta Pak' -! units. A third filtered water transfer. pump has been- i added for manually filling the filtered water storage a tank. This line transfer pump is= reflected on FSAR ~ Fig. 9.2-4A Sht. 3. 'The filtered water clearwe11' level. j instrumentation has been updated to reflect as built I conditions and is reflected on FSAR Fig. 9.2-4A Sht. 3. l The corstruction-of portions of the new water pre-treatment (Clarifier System) are on construction hold. < Group: 3 l FSAR Change Request Number: 89-541.1 SER/SSER Impact: No { l i
'I
-Attach ent to TXX-90011 'j L January 15, 1990' 1 L Page 138.of 304 _
l l L FSAR Page. (as amended) Descrintion 9.2-62
Description:
( Correct'1 on) . - Revises the discussion of the requirements'to divert , potentially contaminated secondary waste from the Low Volume Waste (LVW) treatment facilities to the l l Co-Current Waste (C0W) treatment' facilities. 3 Justification: i The FSAR is being revised to clarify that the i requirements for diverting the waste stream from the' ! LVW treatment facility =to the COW treatment facility' l are based uponEidentificationi of. specific detectable
~
quantities of radioactivity in the waste stream'- FSAR
. j
-Section 9.2.8.2.2 incorrectly implies that if.any low i level radioactive contamination is detected or anticipated, the waste stream must be diverted to the ,
COW treatment facilities. The specific. detectable. , quantities referred.to in FSAR Section 11.5.3.2 are; detailed in the.0ffsite' Dose Calculation Manual 10DCM), s Section 3/4.11.1.1,-Table 4.11-l' 'This change provides .: consistency between'FSAR Sections 11.5.3.2 and- -* 9.2.8.2.2.. Group: 3 FSAR: Change-Request Number: 89-679-Related.SER Section: 9.3.3 SER/SSER: Impact: No Table 9.2-1 See Sheet No(s):01 ! l Descri pti on: . (Rev.i si on) . Removal Station. Service WaterL recirculation line l contro1~ valves, associated. piping and orifices.- ' Justification: i Deleted SSW pump recirculation valve from the. single failure analysis. Since the. recirculation line has been. blind flanged and' prohibits flow, there is.no failure r mode for the loop. This change was' evaluated under the' j TV Electric 50.59 process.as describedJin-TXX-89718.-- L dated 9/28/89.- Group: 2- i FSAR Change Request Number: 89-782.4 ' Related SER Section: 9.2.1? -! SER/SSER Impact:'Yes . . 3 SER section' 9.2.1' indicates- that the!SSW recirculation *
' loop is provideditor testing.
- Figure 9.2 1 See Sheetilo(s):01 l
Description:
(Correction) Reflects the plant configuration f-or chemically-controlling organic fouling at the time of fuel load. Justification: These changes reflect the: plant configuration for. chemically controlling organic fouling at the time j l-of fuel' load. v- *-'
, e -v a
( , Attachment to TXX 90011 ( January 15. 1990 Page 139 of 304 i FSAR Pepe (as. amended) Descrintion Group: 4 rSAR Change Request Number: 89 598.2 Related SER Section: 9.2.1 SER/SSER Impact: No Figure 9.2-1 See Sheet No(s):01
Description:
(Revision) Removal of Station Service Water recirculation line control valves, associated piping 'and orifices. Justification: Revised the figure to reflect that flow is prohibited in the SSW recirculation loop since the line has been blind flanged. This change has been evaluated under the-TU Electric 50.59 process as described in TXX 89718. dated 9/28/89. Group: 2 FSAR Change Request Number: 89 782.3 Related SER Section: 9.2.1 SER/SSER 1mpact Yes SER section 9.2.1 indicates that the recirculation loop is provided for testing $$W components. Figure 9.2 1 See Sheet No(s):01 Descriptions (Revision) Revises Figure to reflect the corrosion. inhibiting - chemicals being added to the Service Water System for corrosion control, Justification: See jur.tification for FSAR change request SA 89 759.1 (Page 9.2 4). Group: 3 FSAR Change Request Number: 89 759.2 Related SER Section: 9.2.1 SER/SSER Impact: No Figure 9.2-1 See Sheet No(s):01, 02 and 03 Description (Correction) Deletion of locked closed (LC) and locked open (LO) notation and addition of locked in position (LIP) notation for selected valves in the figure. Justification: Locked closed and locked open notation is deleted to make this figure consistent with FSAR Section 9.2.1.5. as it was revised in Amendment 76. LIP notation is added to selected valves in order to assure that the minimum required flow passes through the associated components. Group: 3 FSAR Change Request Number: 89 595 Related SER Section: 9.2.1 j i
.v.. . .. .. .. . .
_ . . , .. _n_
L . Attach Or,t to TKX*90011 January 15. 1990 Page 140 of 304 ; r$AR Pepe i IRLagtttdtd) Psseristion ; SER/SSER Impact: Yes l The ' figure is revised to be consistent with FSAR Sect. l 9.2.1.5. as revised in Amendment 76. Tho SER impact of - this change was addressed in the detailed description , (TXX 89202) t.upporting the changes submitted in that ; amendment. . Figure 9.2 3 See 3heet No(s) 01 ,
Description:
(Editorial) : Shade indicated valves on figure to indicate that they - ! are normally closed. Justification: Valves 100 0092 and 0093 are shown normally closed in i series with volves 100 1014 and 1015 to a:sure positive ; closure without the need of locking valves. Group: 4 FSAR Change Request Number: 89 593.3 , Related SER Section: 9.2.2 SER/SSER Impact: No [ Figure 9.2 3 See Sheet No(s):01 Descriptions (Editorial) Change direction of selected flow arrows on figure. ; Justifications ! Direction of selected flow arrows to correct flow ; direction drafting error l Grup: 4 F W, Change Request Number: 89 593.4 Ret,ated SER Section: 9.2.2 i SER/SSER Impact: No ) , i Figure 9.2 3 See Sheet No(s):01 thru 08 i Description (Correction) , Deletion of locked closed (LC). locked open (LO). and locked in position (LIP) notation for selected valves in figure. Justification: la response to an observation by INPO concerning c excessive numoers of locked valves. TU Electric reviewed requirements for locked valves and identified valves which were not required to be locked. Locked f notation for these valves are being deleted. ; Group: 3 FSAR Change Request Number: 89 593.1 Related SCA Section: 9.2.2 SER/SSER lapact: No Figure 9.2 3 See Sheet No(s):01 thru 08 :
Description:
(Clarification) . Delete the words "and:shall be administratively , controlled" form Note 8 on figure. 4 Justification: .i L I-
-Attachment
- to TXX 90013 January 15, 1990 Page 141 of 304 FSAR Page (as amended) Descrintion These words are deleted since they are a detail which is not required in the flow diagram.
Group: 4 FSAR Change Request Number: 89 593.5 Related SER Section: 9.2.2 CER/SSER Impact: No Figure 9.2 3 See Sheet No(s):02 and 03
Description:
(Correction) Addition of notation " Note 10" to selected valves and addition of Note 10 which states " Locked closed when supplied from Unit 2 Normally open when supplied from Unit 1" to figure. Justification: These valves are 'ocked closed when supplied by Unit 2 in order to assure that no interconnection exists between Unit 1 and Unit 2. Group 3 FSAR Change Request Number: 89 593.6 Related SER Section: 9.2.2 SER/SSER Impact: No Figure 9.2 3 See Sheet No(s):02. 03, 04 and 06
Description:
(Addition) Adds Unit 2 cross tie isolation. valves and the locked closed (LC 2) notation to the Unit I flow diagrams. Justification: Following engineering review, Unit 2 cross tie isolation valves and the locked closed (LC-2) notation were added to the Unit 1 flow diagrams for those valves which serve as a boundary for Unit I during Unit 2 construction. These additions will make the isolation configuration easier to understand during Unit 1 operation. Unit 2 piping is depicted as a dashed line instead of a solid line. Group: 3 FSAR Change Request Number: 89-678 Related SER Section: 9.2.2 SER/SSER impact: No Figure 9.2 3 See Sheet No(s):03
Description:
-(Correction) Addition of notation of LC-2 to selected valves and addition of Note 9 which states " Valves identified as LC 2 shall be locked closed during Unit 2 construction" on figure. Justification: Selected valves will remain locked closed t3 serve as l a boundary for Unit I during construction of Unit 2.
- l. Groups 3
! FSAR Change Request Number: 89 593.2 l Related SER Section: 9.2.2 l
Attachment to TXX 90011 1 January 15. 1990 Page 142 of 304 j FSAR Page l (as amended) Descrintion ; I f SER/SSER Impact: No I i ! l. Figure 9.2-3 See Sheet No(s):05 i
Description:
(Correction) j l Replace noted gate valve with a globe. valve in figure. Justification: This change is made to reflect the as built condition of the system. Group -4 FSAR Change Request Number: 89 593.7 Related SER Section: 9.2.2 SER/SSER Impact: No l Figure 9.2-3 See Sheet No(s):06 , Descriptions (Correction) l Corrects the ANSI Safety Classification from Safety Class 3 to non Safety Class 5. l Justification: The piping for the waste gas compressor seal water coolers has been changed from Safety Class 3 to non Safety Class 5 to match as-built conditions consistent with FSAR Amendment 76. Group: 3 FSAR Change Request Number: 89 639.3 Related SER Section: 11.2.2 SER/SSER Impact: No Figure 9.2 4 See Sheet No(s):01 and 02 Description (Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 9.1 13. Group: 4 FSAR Change Request Number: 89 732 SER/SSER Impact: No Figure 9.2 4A See Sheet No(s):01 Description (Revision) Removes clay pre mixing tank and all associated equip-ment, valves and piping from the surface water pre-f treatment system. Justification: The clay pre mixing tank is not presently used in the water treatment system. The tank and all associated equipment, valves and piping are to be removed to allow room for the-installation of new equipment per design modification. Group: 3 FSAR Change Request Number: 89 427 Related SER Section: 9.2.4 SER/SSER Impact: No
Attacnmont to TXX 90011 January 15. 1990 Page 143 of 304 , i FSAR Page j (as amended) Descrintion [ Figure 9.2 4A See Sheet No(s):01 thru 06 Oescriptions (Correction) Reflects the configuration of the Water Pre-Treatment l System at the time of fuel load, f i Justification -l l These changes are to reflect the configuration of the i Water Pre Treatment System at the time of fuel load. ! Fig. 9.2 4A Sht. I removes surface makeup water pump CPX-WTAPSM 01 and provides tie-in to new pumps i l CPX WTPMSW-01 and 02. Fig. 9.2 4A Sht. 2 updates tie ins to degasified water I clearwell and transfer pumps. Fig. 9.2-4A Sht. 3 updates filtered water. clearwell t instrumentation and adds filtered water transfer pump. 1 Fig. 9.2 4A Sht. 4 puts all items except surface water ! pumps and tie in to existing piping on hold. Fig. 9.2 4A Sht. 5 puts all items except the R.O. Product Storage Tank, the Filtered Water Storage Tank, l and the tanks interim piping tie ins on hold. 't Fig. 9.2 4A Sht.- 6 puts all items on the flow diagram cn hold. ; Group: 3 FSAR Change Request Number: 89 541.2 , SER/SSER Impact: No l Figure 9.2 4A See Sheet No(s):03 ;
Description:
(Revision) ; Reflects replacement of skid mounted piping in the surface water pre treatment system. Justification: The skid mounted piping in the surface water pre- i treatment-system was replaced because the piping mater-ial was corroded to the point of failure. The revised figure reflects the change to piping materials required i for chemical resistance, and to show as built flow + logic for the surface water pre treatment system chemical feed skid piping. Group 3 FSAR Change Request Number: 89 647 Related SER Section: 9.2.4 ! SER/SSER Impact: No t Figure 9.2-5 See Sheet No(s):01
Description:
(Revision) , Adds valve for isolation between fill ' connections and suction'of demineralized water transfer pumps. Justification: Additional isolation valve allows existing fill connections to be used to add makeup to the demineral-ized water storage tank via the mobile water treatment ' l _ _ _ _ _ . _ _ _ _ _ _ __ _ _ . , __ _ _ . -- ~.
Attachment to TXXo90011 January 150 1990 Page 144 of 304 FSAR Page (as amended) Description connection. Group: 3 FSAR Change Request Number: 89 755 Related SER Section: 9.2.3 SER/SSER Impact: No Figure 9.2 5 See Sheet No(s):01 Description (Revision) Removes changes made in LDCR # SA 88-646 for Amendment 76 by reassigning line numbers to the tank vent nozzle and overflow nozzle for the demineralized water storage tank. Justification: The following figure changes made per LDCR # SA-88 646 in Amendment 76 are no longer applicable: (1) The vent nozzle size is changed back from 6" diameter to 3" diameter (was 3" prior to Amendment 76). (2) Based on a revised operator action to control the DWST overflow by monitoring DWST level indication, the overflow nozzle size is changed back from 3" diameter to 2" diameter (was 2" prior to Amendment 76). Group: 3 FSAR Change Request Number: 89 716 Related SER Section: 9.2.3 SER/SSER Impact: No Figure 9.2 5 See Sheet No(s):01 thru 06
Description:
(Correction) Deletion of locked closed (LC) and locked open (LO) notation and addition of locked closed during construction of Unit 2 (LC-2) notation for selected valves in the figure. Justification: In response to an observation by INPO concerning excessive numbers of locked valves. TU Electric reviewed requirements for locked valves and identified valves which were not required to be locked. Locked notation for these valves are being deleted. Selected valves will remai.ned locked closed to serve as a boundry for Unit 1 during construction of Unit 2. Group: 3' FSAR Change Request Number: 89-599 Related SER Section: 9.2.3 SER/SSER Impact: No Figure 9.2-5 See Sheet No(s):02
Description:
(Correction) Modifies Turbine Oil Purification and Demineralized Water System to eliminate the presence of j Microbiological 1y Induced Corrosion-(MIC) bacteria. Justification:
. _______- _ -_ _ _- - _ L
,_ ~ -.. ._ -- _ _
i i , AttachCent to TXX 90011 . January 150 1990 ! l
~Page 145 of 304 l l !
( 1 FSAR Page (as amended) Descrintion t The Turbine Oil Purification and Demineralized Water ; System was modified to eliminate the presence of MIC : bacteria found to be present in low flow, high moisture ; regions of the mechnical filtration purification ! (Bowser) unit. .Therefore to eliminate the presence of ; MIC bacteria, two centrifuge units have been installed. l as a temporary modification. The inherent design of ! these units minimizes low flow and stagnant regions l within the lube nil purification cycle. .l Group: 4 { FSAR Change Request' Number:' 89 766.1 + Related SER Section: 9.2.3 I SER/SSER Impact: No i : Figure 9.2 5 See Sheet No(s):04 i
Description:
(Correction) r Makes miscellaneous minor changes for the Demineralized and Reactor Makeup Water System, i Justification: Miscellaneous minor changes are made to the Demineral-ized and Reactor Makeup Water System to reflect as- > built conditions. These changes were processed for , FSAR Amendment 76, and the detailed description / : justification was provided to the NRC in TXX 89201. l The changes resulting from this change request. though. were inadvertently omitted from the FSAR figure being ' revised. The changes, as C. ribed, are incorporated i into the figure and are included as part of FSAR i Amendment 78. ;f Group: 4 FSAR Change Request Number: 88-367 ! Related SER Section: 9.2.3 [ SER/SSER Impact: No ! Figure 9.2 6 Descriptions (Editorial) i Miscellaneous editorial changes to reflect as-built ! conditions of potable water system. -i Justifications- " Change to reflect permanent branch connection to - existing buried 4" potable water line. This change was ; processed for Amendment 76, and the detailed descrip- -) tion / justification was provided to the NRC in 3 TXX 89201. The change-resulting from this change re-quest. though, was inadvertently omitted from the FSAR : figure being revised. The change. as described, is incorporated into the figure and is included'as part of FSAR Amendment 78. ! Group: 4 > FSAR Change Request Number: 88 874
- - Related SER Sect 1on
- 9.2.4
! SER/SSER Impact: No !
. . ~ + . , . .
Attachment to TKX-90011 l January 15. 1990 ; Page 146 of 304 . FSAR Page [ L (as amended) Descrintion l Figure 9.2 7
Description:
(Update) . Minor figure updates, i l Justification: ! No justification necessary. See discussion under I Figure 9.1 13. Group: 4 FSAR Change Request Number: 89 732 SER/SSER Impact: No ; Figure 9.2-15 See Sheet No(s):01 Description (Addition) ' l Adds isolation valve to enable the positive isolation of the Natural Neutralization Basin, i Justifications : The isolation valve is added to enable the positive isolation of the Natural Neutralization Basin. During , normal flow from the chemical sump pumps to the equali- ' zation basin and the natural neutralization basin, the waste oil received by the chemical sump inhibits the effectiveness of the Natural Neutralization Basin and ; leads to a premature replacement of the neutralizing , limestone. When this happens, flow from the chemical sump will be diverted to the. Separator Surge Basin by opening a previously installed valve. and the isolation , valve being installed will positively isolate the . Natural Neutralization Basin. l Group 3 FSAR Change Request Number: 89 448 ! Related SER Section: 9.2 i SER/SSER impact: No Figure 9.2 15 See Sheet No(s):02 Descript-ion: (Update)
- Hinor figure updates. '
Justification: No justification necessary. See discussion under Figure 9.1-13. - Group: 4 FSAR Change Request Number: 89-732 . SER/SSER Impact: No Figure 9.2 16 See Sheet No(s):02 i
Description:
(Correction) Remove Metal Cleaning Waste (MCW) compartments from the FSAR figure to reflect the as-built condition at the l receipt of the operating license for Unit 1. Justification: _ FSAR figure changed to reflect as built condition. Construction and implementation of the design change submitted in FSAR Amendment-76 is deferred. . since compartmenalization is not a regulatory requirement as.. long as the Total Retention Pond (TRP) i s not utilized
.-n . , - - c---.... ~ -~ . -
Attachment to TXX 90011 : January 15e 1990 t Page 147 of 304 ? i FSAR Page (as . amended ) Descrintion i i for metal cleaning waste. ; Group: 4 i FSAR Change Request Number: 89-533 l' SER/SSER Impact: No 9.3 2 Description (Correction) l l Deletes the -40 F dewpoint requirement, and repleces it i with a reference to ANSI ISA $7.3. ; Justification: ! The -40 F dewpoint requirement was deleted. and i replaced with a reference to ANS! ISA $7.3. ISA S7.3. ; is the industry standard for instrument air quality. l The-design basis of the CPSES instrument air system is- ' that CPSES meets or exceeds the ISA requirements. This [ change does not represent a changes-in design or
- function of the instrument air system, only a- l clarification of design basis vs. equipment. design. l l Group: 3 i FSAR Change Request Number: 89 655 .
Related SER Section: 9.3.1 SER/SSER Impact: No { t i 9.3-9
Description:
(Clarification) .. Adds statement further describing the Instrument Air System. : Justification: A statement has been added to further describe the function of the Instrument Air System. NRC request to modify FSAR committment. that Instrument Air System is not safety related. however it supplies air to safety related components. Group: 4 FSAR Change Request Number: 89-661 ! Related SER Section: 9.3.1 ' SER/SSER Impact: No 9.3-14. 15
Description:
(Correction) Increases allowable pressure for sampling. ; Justification: The increase in allowable pressure of samples insures [ that adequate flow can be achieved in all sample lines to prevent boric acid from precipitating out of- : solution. i Group: 3 i FSAR Change Request Number: 89 438.1 Related SER Section: 9.3.2 SER/SSER Impact: No i 4 I i
?
i ' l Attachment to TXX-90011 January 15, 1990 Page 148 of 304 ! FSAR Pope (as amended) Descrintion 9.3 17, 18
Description:
(Correction) Provides further description and text consistency for j the sample flow rates and the Class IE panel which i operates the sample line containment isolation valves. Justification: l A clearer description has been provided to describe the ' sample flow rates and the location of the Class 1E l panel which operates the sample line containment i isolation valves, and to provide text consistency. l Group 3 FSAR Change Request Number: 89 438.2 Related SER Section: 9.3.2~ t SER/SSER Impact: No , 9.3-26
Description:
(Correction) 1 Specifies that the auxiliary building sump No. 2 will continue to be routed to floor drain tank No. I after - I completion of Unit 2. Justification l A change is required to this paragraph because l auxiliary building sump No. 2 will continue to be routed to floor drain tank No. I after completion of Unit 2. Groups 3 FSAR Change Request Number:. 89-514.1 Related SER Section: 9.3.3 SER/SSER Impact: No 9.3 77
Description:
(Correction) Adds a description of.a third boration path available to the operator. Justification: A description of a third boration path available to the-operator has been added. A third boration path can be provided if the normal charging lines or reactor coolant pump seal injection paths are not available. The operator can cool'down and depressurize the RCS to a pressure less than the shutoff head of the safety injection pumps without allowing the core to return to a critical condition. Borated water from the_RWST can then be delivered to the RCS via the safety injection pumps, thus establishing an alternate boration line to-the RCS. Group: 3 FSAR Change Request Number: 8t'- 658 Related SER Section: 9.3.4 SER/SSER Impact: No
i Attachment to TXX 90011 i January 15. 1990 Page 149 of 304 l FSAR Page ' (as. amended) Description i Table 9.3 4 See Sheet No(s):01 and 02
Description:
(Correction) Revises Table to provide minimum ficw for grab sample. Justification: The Table has been revised to add the grab sample [ minimum flow.
- Group: 3.
FSAR Change Request Number: 89 438.3
- Related SER Section: 9.3.2 ,
SER/SSER Impact: No ' Figure 9.3 1 See Sheet No(s):01- Descriptions.(Addition) Reflects addition of cross-connection,between Units 1 i and 2 service air system downstream of their respective : air receivers. i Justification: Cross-connecting the service air system improves system . reliability to service air users. Either compressor 4 can now be shut down'for maintenance activities'while ' the air distribution networks of both units continue to i have a service air supply from one operating ! compressor. Group 3 FSAR Change Request Number: 89-425 t Related SER Section: 9.3.1 SER/SSER Impact: No Figure 9.3 1 See Sheet No(s):02 -
Description:
(Correction) Corrects figure by adding instrument air and service air for the new auxiliary boiler, , Justification i Existing electric auxiliary boiler is being replaced ' by a new. oil fired auxiliary boiler. The new installation requires instrument air for air operated-valves / components and service air for fuel oil ; atomizing. This change was processed for FSAR Amend-ment 76. and the detailed description / justification was provided to the NRC in TXX-89201. The change resulting i from this change request, though, was inadvertently' ' omitted from the FSAR figure being revised. The i change, as described, is incorporated into the figure- i and is included as part of FSAR Amendment 78. { Group: 3 FSAR Change Request Number: 89-076 E Related SER Section: 9.3.1 SER/SSER Impact: No < 1
, , . - . - . _ -, , . _ . . , - w -- r - -- _
Attachment to TXX-90011 ! January 15, 1990 , Page 150 of 304 l 3 FSAR Page ; (as amended) Descrintion j Figure 9.3-1 See Sheet No(s):03 i
Description:
(Correction) , Delete lube oil level indication for the instrument air compressor. Justification: , . Instrument air compr6ssor lube oil level indication is [ monitored visually through the sight glass, however : other protective controls such as pressure and tempera-ture indication for the lube oil are available. i Group: 3 . FSAR Change Request Number: 89 766 i Related SER Section: 9.3.1 t SER/SSER Impact: No Figure 9.3-1 See Sheet E9(s):03 and 04 Descriptions (Update) : Minor figure updates.
- Justifications ,
No justification necessary. See discussion under ' Figure 9.1 13. Group 4 FSAR Change Request Number: 89 732 ' SER/SSER Impact: No , Figure 9.3 1 See Sheet No(s):04 ;
Description:
(Update) t Assigns tag numbers to previously unidentified instru- : ment air system valves. Justification: Assigns tag numbers to previously unidentified instru- ' ment air system valves to facilitate system line ups and tag outs. . Group: 4 FSAR Change Request Number: 89-802.1 Related SER Section: 9.3 SER/SSER Impact: No ; Figure 0.3 2 See Sheet No(s):01 and 02
Description:
(Update) Minor figure updates. Justification: No justification necessary. See. discussion under Figure 9.1 13. Group: 4 FSAR Change Request Number: 89-732 SER/SSER Impact: No , Figure 9.3 3 See Sheet No(s):01
Description:
(Update) Assigns tag numbers to previously unidentified instru-ment air system valves. , Justification: l
-. .. . .. . .~ ..-
f Attach ent to TXX 90011 ; January IS. 1990 ; Page 151 of 304 i FSAR Page ! (as amended) Agipriotion } Assigns tag numbers to previously unidentified instru- ! ment air system valves to facilitate system line ups ! and tag outs. l Group: 4 FSAR Change Request Number: 89 802.2 : Related SER Section: 9.3 [ SER/SSER Impact: No ; Figure 9.3-3 See Sheet No(s):01 thru 10 - j
Description:
(Update) Minor figure updates. ! Justification: _ l No justification necessary. See discussion under ! Figure 9.1-13. ! Group: 4 i FSAR Change Request Number: 89-732 ; SER/SSEk Impact: No -) Figure 9.3-3 See Sheet No(s):03 and 04 ! Descriptions (Update) Assigns tag numbers to previously unidentified instru-ment _ air system valves. Justification: Assigns tag. numbers to,previously unidentified instru- ' ment air system valves to facilitate system line_ups and tag outs. . Group: 4 FSAR Change Request Number: 89 802.3 ' , Related SER Section: 9.3 i SER/SSER Impact: No-Figure 9.3 3 See Sheet No(s):09
Description:
(Revision) Adds a block valve and deletes distribution piping downstream of valve to reflect as built conditions. Justification: _ The addition of the block valve and deletion of the distribution piping downstream of this valve reflects as-built conditions. The distribution piping was-originally proposed in'a design modification request. ' which has been deferred until af ter fuel load. The design modification request covers certain enhancements of water treatment system equipment. The distribution piping proposed as part of this enhancement is not required for current system operation: the piping proposed as well as its current configuration does not impact any safety-related system or component. Group: 3 FSAR Change Request Number: 89-737 Related SER Section: 9.3.1 SER/SSER Impact: No
i Attachment to TXX 90011 ! January 15, 1990 ! Page 152 of 304 l FSAR Page Ias_ amended) Deserintion i' Figure 9.3 3 See Sheet No(s):10
Description:
(Addition) i Adds vacuum breaker to Circulating Water System Justification: ( An air operated vacuum breaker is added to'the main i condenser outlet waterboxes to protect the tube side components from transients (such as waterhammer) in the j event of simultaneous trip of all four Cire water pumps , Group: 3 ! FSAR Change Request Number: 89-754.2 ! Related SER Section: 10.4 SER/SSER Impact: No l l Figure 9.3 4 See Sheet No(s):01 !,
Description:
(Editorial) ,
- Change IPS 194 to IPS-503 on FSAR figure. -{
l Justification: 1PS-194 is changed to IPS 503 because this change was inadvertently omitted from Amendment 76 issuance of ! the print ready figure. Group: 4 FSAR Change Request Number: 89 455 Related SER Section: 9.3.2 SER/SSER Impact: No Figure 9.3 4 See Sheet No(s):01 thru 05 ' Descriptions (Correction) Reflects the plant configuration of the Process l Sampling System at the time of fuel load. Justification: ' Reflects the plant configuration of the Process Sampling System at the time of fuel load.- ' Group: 4 i FSAR Change Request Number: 89 438.4 Related SER Section: 9.3.2 SER/SSER Impact: No ' Figure 9.3 4 See Sheet No(s):03 ,
Description:
(Addition) I Justification: This figure is revised to show the enhanced sodium ' analyzer system. This enhanced system will provide more reliable monitoring of sodium in'the steam generators. Group: 3 i FSAR Change Request Number: SA-89 801 Related SER Section: 9.3.2 s SER/SSER Impact: No l l l I 1 1 .
Attachment to TXX 90011 January 15. 1990 i Page 153 of 304 ; i FSAR Page l (as amended) Descriction , Figure 9.3-5 See Sheet No(s):01 and 02 Description (Update) ; Minor figure updates. l Justification: No justification necessary, see discussion under ! Figure 9.1-13 ; Group: 4 ; FSAR Change Request Number: 89 732 L SER/SSER Impact: No I Figure 9.3 6 See Sheet No(s):01 and 02
Description:
(Update) r Minor figure update. Justification: No justification necessary. See discussion under I Figure 9.1 13. Group: 4 i FSAR Change Request Number: 89-732 SER/SSER Impact: No Figure 9.3-7 See Sheet No(s):01, 03 and 04 '
Description:
(Addition) Adds locked closed (LC 2) notation to those valves i which serve as a boundary for Unit 1 during Unit 2 t construction. I Justification:- :5 In response to an observation by INPO concerning i excessive numbers of locked valves, TV Electric. reviewed requirements for locked valves and identified t instances where locked valve requirements needed to be ! added to match the as built status of the system and to : reflect the CPSES locked valve criteria. Group: 3 FSAR Change Request Number: 89 640 i Related SER Section: 9.3.3 SER/SSER Impact: No Figure 9.3 7 See Sheet No(s):02, 05 and 06 Descriptions (Update) Minor figure updates. Justification: ; No justification necessary. See discussion under Figure 9.1-13. Group: 4 l FSAR Change Request Number: 89 732 SER/SSER Impact: No i Figure 9.3 8 See Sheet No(s):01 -(
Description:
(Correction) Corrects actuator levels for the chemical sump in the Vents and Drains System of the Turbine and Fuel
- Handling Building.
Attach ent to TXX-90011
- January 15, 1990 Page 154 of 304 FSAR Page (as amended) Descrinti on Justification:
Corrects actuator levels for the chemical sump in the Vents and Drains System of the Turbine and Fuel Handling Building to reflect as built conditions. Group: 3 FSAR Change Request Number: 89 470 Related SER Section: 9.3.3 SER/SSER Impact: No Figure 9.3-8 See Sheet No(s):02
Description:
(Update) 4 Minor figure updates. Justification: No justification necessary. See discussion under Figure 9.1-13. Group: 4 FSAR Change Request Number: 89 732 SER/SSER Impact: No Figure 9.3-8 See Sheet No(s):02
Description:
(Correction) Modifies Turbine 011 Purification and Domineralized Water System to eliminate the presence of Microbiologically Induced Corrosion (MIC) bacteria.. Justification: The Turbine Oil Purification and Demineralized Water System was modified to eliminate the presence of MIC bacteria found to be present in low flow, high moisture regions of the mechnical filtration purification (Bowser) unit. Therefore.to eliminate the presence of MIC bacteria, two centrifuge units have been installed as a temporary modification. The inherent design of these units minimizes low flow and stagnant regions within the lube oil purification cycle. Group: 4 FSAR Change Request Number: 89 766.2 Related SER Section: 9.3.3 SER/SSER Impact: No Figure 9.3 9 See Sheet No(s):01 and 02
Description:
(Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 9.1-13. Group: 4 FSAR Change Request Number: 89 732 SER/SSER Impact: No
Attachment to TXXo90011 January 15, 1990 Page 155 of 304 l l FSAR Page (as amended) Descrintion ! I Figure 9.3-10' See Sheet No(s):01, 02, 08 and 09 Descriptions (Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 9.1-13. Group: 4 FSAR Change Request Number: 89-732 SER/SSER Impact: No Figure 9.3-10 See' Sheet No(s):03, 05 and 07 j Description (Correction) ! Deletion of locked closed (LC) and locked open (LO) ] notation and addition of locked closed during ' construction of Unit 2 (LC 2) notation for selected valves in the figure. Justification: In response to an observation by INP0 concerning excessive numbers of locked valves. TU Electric
- reviewed requirements for locked valves and identified valves which were not required to be locked.. Locked I notation for these valves are being deleted. ;
Selected valves will remain locked closed to serve as - . a boundry for Unit 1 during construction of Unit 2. I Group: 3 FSAR Change Request Number: 89 615 Related SER Section: 9.3.4 SER/SSER Impact: No Figure 9.3 10 See Sheet No(s):04 i
Description:
(Correction) .W Adds heat tracing. ! Justification: . Heat tracing is added to' provide freeze protection for i Chemical & Volume Control System lines which contain concentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal to 65 >
, degrees (fahrenheit) and ensure the operability of that I portion of the system. i Group 3 FSAR Change Request Number: 89-689.1 1
Related SER Section: 9.3.4 i l SER/SSER Impact: No ; t l Figure 9.310 See Sheet No(s):05 j] Description (Revision) Revises support requirements for non-nuclear safety piping. Justification: l Revises support requirements for non nuclear safety ) piping to be consistent with Westinghouse design ; I requirements. Piping from the outlet of the relief e l
- - . _ _ . . _ _ _ _ __ _ _ - _ , . . . - - . . - ~ . ., c
Attachment to TXX;90011 January 15. 1990 Page 156 of 304 FSAR Page (as.. amended) Description valves to the Refueling Water Storage Tanks shall be supported such that the line remains functional and provides a flowpath through the line following a safe shutdown earthqvake. The availability of this flow path through the tentrifugal charging pump. minimum flow bypass line ensures the ability of the centrifugal [ charging pumps to provide flow to the Reactor Coolant System following the receipt of a Safety Injection Signal. Group: 3 FSAR Change Request Number: 89 636.2 Related SER Section: 6.3.1 SER/SSER Impact: No Figure 9.3-10 See Sheet No(s):05
Description:
(Revision) 4 Relocates relief valve inlet lines from downstream to i upstream of check valves. Justification: The figure was revised to relocate the relief valve inlet lines to prevent pump discharge through two relief valves causing inadequate water flow. Group: 3 FSAR Change Request Number: 89 648 Related SED Section: 9.3.4 SER/SSER Impact: No Figure 9.3 10 See Sheet No(s):06 l
Description:
(Correction) Adds heat tracing. Justification: Heat tracing is added to provide freeze protection for Chemical & Volume Control System lines which contain cencentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal-to 65 degrees (fahrenheit) and ensure the operability of that portion of the system. Group: 3 FSAR Change Request Number: 89 689.2 Related SER Section: 9.3.4 SER/SSER Impact: No Figure 9.3-10 See Sheet No(s) 07 1
Description:
(Correction) Adds heat tracing. Justification: Heat tracing is added to provide freeze protection for Chemical & Volume Control System lines / pumps containing concentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal to 65 degrees (fahrenheit) and ensure the operability of that portion of the system.
Attachment to TXX-90011 3 January 15. 1990 i Page 157 of 304 l FSAR Page 1 (as aseetded) Descrintion d-Group: 3 [ FSAR Change Request Number: 89-689.3 i Related SER Section: 9.3.4 ! SER/SSER Impact: No ! Figure 9.3 10 See Sheet No(s):07 !
Description:
(Correction) > Deletes heat tracing. - Justification
- Heat tracing is deleted from several Chemical & Volume Control System lines to be consistent with as built '
conditions. These lines do not contain concentrated i boric acid solution (4% boric acid). Group 3 - FSAR Change Request Number: 89-689.4 5 Related SER Section: 9.3.4 , f SER/SSER Impact: No Figure 9.3 10 See Sheet No(s):07 ,
Description:
(Correction)
- l Adds heat tracing. ,
1 Justification: 1 Heat tracing is added to provide freeze protection for i a Chemical & Volume Control System line which contains r concentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal to 65 , degrees (fahrenheit) and ensure the operability of that ' portion of the system. Group 3 l. FSAR Change Request Number: 89-708 Related SER Section: 9.3.4 ' SER/SSER Impact: No Figure 9.3 11 See Sheet No(s)':01 '
Description:
(Editorial) Makes minor change to reflect as built conditions. L Justification: ' Deletes line number to correct a drafting error, and thereby reflect as-built conditions. Group: 4 FSAR Change Request Number: 88 704 , Related SER Section: 9.3.4 l SER/SSER Impact: No ' Figure 9.3-11 See Sheet No(s):02
Description:
(Correction) - Adds heat tracing. Justification: Heat tracing is added to provide freeze protection for Boron Recycle System lines which contain , concentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal to 65
Attach Ont to TXX 90011 January 15, 1990 Page 158 of 304 FSAR Page (as amended) Desc.r. int.1on , degrees (fahrenheit) and ensure the operability of that portion of the system.
- Group: 3 .;
FSAR Change Request Number: 89 689.5 l Related SER Section: 9.3.4 ! SER/SSER Impact: No ! Figure 9.3 11 See Sheet No(s):02 i Descriptions (Addition) Reflects installation of vent valve to vent the boron recycle evaporator condenser. Justification: Vent valve is installed to vent the boron recycle .l evaporator condenser. A bypass of the vent condenser 1 is necessary to vent the boron recycle evaporator l condenser.
- Group: 3 FSAR Change Request Number: 89 692 :
Related SER Section: 9.3.4 ! SER/SSER Impact: No Figure 9.3 11 See Sheet No(s):03 ! Description (Correction) Adds heat tracing. Justifications j Heat tracing is added to provide freeze protection i for Boron Recycle System lines which contain concentrated boric acid solution (4% boric acid) to- . maintain the solution at greater than or equal to 65 degrees (fahrenheit) and ensure the operability of that portion of the system. Group 3
- FSAR Change Request Number: 89 689.6 Related SER Section: 9.3.4 SER/SSER Impact: No 9.4 3. 4 Description (Editorial) f Corrects total number of sheets with Figure 9.4 1. '
Justification: Nakes minor editorial correction to the total number of sheets [3] with Figure 9.4 1. Group: 4 ( FSAR Change Request Number: 89 542.1 ! Related SER Section: 9.4.1 [ SER/SSER Impact: No 9.4-5
Description:
(Editortal) Corrects FSAR amendment number in the margin. - Justification: l The FSAR amendment number was corrected in the mergin: this is considered a minor editorial change. l Group: 4 l m_ _.___-____ _ ._ , _ _ _ _ _ _ _ _
l Attachment to TXX 90011 ; January 15. 1990 Page 159 of 304 , FSAR Page l (as amended) Descrintion ; i FSAR Change Request Number: 89-424.1 i Related SER Section: 9.4.1 SER/SSER Impact: No I 9.4 6 Descriptions (Editorial) , Justification l Deletes the specific pressure which the control roon l envelope will be' pressurized to remove duplicate infor- ; mation between this section and section 6.4 ; Group: 4 FSAR Change Request Number: 89 800.06 j Related SER Section: 6.4 ; SER/SSER 1mpact: No j 9.4 12 Descriptions (Correction) ) Clarifies requirements for operation of Control Room i HVAC equipment during a LOOP or a LOCA. 1
- Justification j The operation of Control Room HVAC equipment is clari- !
fled to indicate that only safety related equipment is ] required to operate during a LOOP or a LOCA. Prior to 1 the clarifica^, ion, the text implied that all Control I Room HVAC equipment was required to operate during ! these accident scenarios. Group: 3 FSAR Change Request Number: 89 542.2 i Related SER Section:.9.4.1- ~l SER/SSER Impact: No 9.4 19 Description (Addition) Adds reference tb figure. Justification: Reference to Figure 9.4 2 was added to make the dis-cussion of the supply and exhaust ventilation filtra- I tion units more complete. Group: 3 , FSAR Change Request Number: 89 424.2 ! i Related SER Section: 9.4.3 SER/SSER Impact: No 9.4 19 Description (Revision) An exception has been taken for maintaining 'the ambient temperature in the Train A Component Coolird Water Pump Room during loss of offsite power and LOCA below 122 degrees F. Justification: As described the maximum indoor temperature for Train A Component Cooling Water Pump Room will be kept below 130 degrees F during loss of offsite power and LOCA. This maximum temperature has no adverse effect on the 1 equipments located in this room since all the equipment is environmentally qualified for this environment.
Attachment to TXX 90011 January 15, 1990 Page 160 of 304 ; FSAR Page ! (as amended) Rescrintion l This change has been evaluated under the TV Electric ' 10 CFR 50.59 process as described in TXX 89718, dated
- 9/28/89.
- Group: 2 !
FSAR Change Request Number: SA 89 781 i Related SER Section: 9.4.3 ; SER/SSER Impact: No l 9.4 19
Description:
(Correction) Justifications ! The maximum postulated temperature for safety,related i equipment rooms equipped with emergency fan coil units t during loss of offsite power and LOCA is corrected from l 129 to 130 degrees F to be consistent with the bases described in FSAR section 3.118.1. i Group: 3 ! l FSAR Change Request Number: SA 89 781 i Related SER Section: 9.4.3 i SER/SSER Impact: No , 9.4 27
Description:
(Correction) Corrects inspection and testing requirements for the [ Turbine Building Area Ventilation. System. ; Justification: l Inspection and testing requirements for the Turbine f Building Area Ventilation System are not the same as those for the spent fuel pool area ventilation system: + therefore, the reference is deleted and the applicable ; paragraphs are given in their entirety and other para- i graphs are changed accordingly. The corrected informa- .. tion reflects the following: I (1) Since the Turbine Building Area Ventilation System is a non safety system and does not filter radioactive ; air, the ANSI N510 Standard'is not applicable. , (2) Also, since the Turbine Building Area Ventilation i System is a non safety system, it does not require redundancy of equipment. l Group 3 > FSAR Change Request Number: 89-542.3 r Related SER Section: 9.4.5 l SER/SSER !apact: No 1 ; l 9.4 28
Description:
(Addition) Adds reference to figure and makes minor editorial l- changes. Justification: 4 Reference to Figure 9.4 4 was added to make the dis- !! cussion of the supply and exhaust ventilation units more complete. A minor editorial change was'made to { the text and to an amendment number in the margin. ; Group: 3 i FSAR Change Request Number: 89 424.3 J
l Attach;ent to TXX 90011 ; January 15, 1990 i Page 161 of 304 , FSAR Page j (as amended) Descriction Related SER Section: 9.4.5 l SER/SSER Impact: No - Table 9.4 4 See Sheet No(s):02 l Descriptions (Correction) ! Clarifies HEPA filter design requirements, t Justifications ! When a value of 99% is assumed for HEPA filter i efficiency, a penetration of less than 0.05% at rated j flow is considered acceptable. Likewise, when an ' efficiency of 95% or less is assumed, a penetration , of less than 1% is considered acceptable. Therefore. Table 9.4 4 is clarified to show that the Control ! Room Filtration and Recirculation Units (which have ! an efficiency of 99%) are allowed a penetration of less i than 0.05%. It is also clarified that all other . Filtration Units (which have an efficiency of 95% or j l less), are allowed a penetration of less than 1%. The values listed above for efficiency are consistent ! i with information that was submitted in FSAR Amendment . l 76. The values for penetration are addressed in ' l the current CPSES Unit 1 Technical Specifications , 3/4.7.7 and 3/4.7.8. , Group: 3 ( FSAR Change Request Number:- 89-628.9 Related SER Section: 6.5.1
- SER/SSER Impact: No Table 9.4 6
Description:
(Correction) ! Corrects the number of ESF and non ESF Controlled ' Access Air Cleanup Unitd. Justification: Corrects the number of ESF Filtration Units from two to four and the number of non ESF Filtration U11ts from E fourteen to twelve to be consistent with as built conditions as submitted in a previous FSAR Amendment. t Groups 3 FSAR Change Request Number: 89 675.14 Related SER Section: 9.4.2 SER/SSER Impact: Yes SER indicates that there are two 50% capacity ESF exhaust filtration units when there are currently four ESF exhaust filtration units which make up the Primary Plant Ventilation System. This is consistent with < information submitted in a previous FSAR Amendment. ! Table 9.4 8 See Sheet No(s):02 ,
Description:
(Correction) i Corrects the failure. mode and effects analysis of Control Room HVAC system by changing the comments. associated with electric control, changing 'HVAC instrument' to 'HVAC dampers', and adding the word l
,- 3
Attachment to TXX 90011 ) c January 15. 1990 Page 162 of 304 . l 1 FSAR Page (as amended) Description ;
- 1
' dampers
- to Component No, 8. f i
Justification: ' The table presenting the failure mode anc iffects analysis of the Control Room HVAC system ), corrected l to make it consistent with information presented in l FSAR Section 9.4.1.3. j Group 3 I FSAR Change Request Number: 89 542.7 ! Related SER Section: 9.4.1 4 SER/SSER Impact: No i Table 9.4-10 See Sheet No(s):01 and 03
Description:
(Correction) Deletes damper connecting the ESF filter units and main plenum, and a damper in the recirculation line. Also, makes minor editorial changes to the table. Justification (1) The damper connecting the ESF filter units and main plenum is deleted to make the table' consistent with an 'l FSAR Amendment 76 change to Figure 9.4 9 (LDCR # SA 047 - TUS 89226). (2) A damper in the recirculation line is deleted as a I result of a Design Change. The damper located in the cross-connecting ductwork between the Control Room emergency filtration return air duct and the kitchen & I toilet exhaust duct, was always locked-closed and was < not required to be open in any modes of the Control { Room HVAC system operation. Therefore, the damper was not needed for the system operatiog and is deleted. Group 3 FSAR Change Request Number: 89-542.6 Related SER Section: 9.4.4: SSER4 9.4.4 SER/SSER Impact: Yes + The damper connecting the ESF filter units and main. l plenum (CPX-VADP00 83) was deleted-from F9.4 9 in FSAR l Amendment 76, and is now being deleted from T9.4-10 for- l consistency. This damper is discussed in the SER/SSER '
, section referenced; this discussion is no longer valid. !
Figure 9.4-1 See Sheet No(s) 01
Description:
(Editorial) ! Nakes minor editorial change in the ' Notes' section l of the figure. Justification:
- The minor editorial change is made to the ' Notes' section of the figure to ensure consistency in documentation describing the equ'pment.
Grcup: 4 FSAR Change Request Number: 89 542.4 Related SER Section: 9.4.1 SER/SSER Impact: No
-_-_____ _ =
Attachment
- to TXX-90011 January 16. 1990 Page.163 of 304 FSAR Pepe (as amended) Descrintion Figure 9.4 1 See Sheet No(s):01 and 02
Description:
(Correction) Clarifies air flow rates and flow paths in several areas of the control room, Justification: Air flow rates are clarified to provide a more accurate description of the way the air must flow in order for start-up to complete their testing and balancing packages. Group 3 FSAR Change Request Number: 89 495.1 Related SER Section: 9.4.1 SER/SSER Impact: No Figure 9.4 1 See Sheet No(s):02
Description:
(Correction) Adds class pipe breaks. Justification: Based on the identification of several short sections of copper tubing which tie into carbon steel piping through a coupling. class pipe breaks have been added to the figure as appropriate. Group 3 , FSAR Change Request Number: 89 675.1-l Related SER Section: 9.4.1 SER/SSER Impact: No Figure 9.4 1 See Sheet No(s):02
Description:
(Update) Minor figure updates. Justification: No justification required. See discussion under Figure 9.1-13. l Group: 4 FSAR Change Request Number: 89-726.1 Related SER Section: 9.4 SER/SSER. Impact: No Figure 9.4$ See Sheet No(s):01 and 03
Description:
(Update) Minor figure updates. Justification: No justification required. See discussion under Figure 9.1 13. Group: 4 FSAR Change Request Number: 89 726.1 Related SER Section: 9.4 SER/SSER 1mpact: No l
Attachesnt to TXX 90011 January 15, 1990 Page 164 of 304 FSAR Page (as amended) Descrintion Figure 9.4 2 See Sheet No(s):02
Description:
(Clarification) Makes minor corrections / clarifications to the flow diagrams, Justification: The minor corrections / clarifications to the flow dia-grams are made to ensure consistency in documentation describing the equipment. Group: 4 FSAR Change Request Number: 89-542.5 Related SER Section: 9.4.2 SER/SSER Impact: No Figure 9.4 2 See Sheet No(s) 02
Description:
(Correction) Deletes the word " MAX" from the Auxiliary Building Flow Diagram. Justification: The word " MAX" is deleted from the flow diagram as it provides no design basis restriction relative to flow values it is associated with. These flow values correspond to the design flow and the flow which is used for testing and balancing the system. The word
" MAX" restricts the use of tolerances normally utilized in testing and balancing the system.
Group: 3 FSAR Change Request Number: 89 675.2 Related SER Section: 9.4.3 SER/SSER Impact: No Figure 9.4 2 See Sheet No(s):02
Description:
(Correction) Removes the blade packages from two dampers. Justification: To ensure that negative pressure requirements are. maintained, dampers CPX VADPMC 03 and CPX VADPOC 77 were originally sealed open. In order to provide further assurance that these dampers do not adversely impact the negative pressure requirements, the damper blade packages have been removed so that they can not be inadvertantyly closed. Group: 3 FSAR Change Request Number: 89 675.3 Related SER Section: 9.4.3 SER/SSER Impact: No Figure 9.4-2 See Sheet No(s):03
Description:
(Correction) Modifies figure note and air flow quantities to room 270. Justification: Modifications are made to depict the revised air flow I
l
. Attachment to TXXo90011 !
Jcquery 15. 1990 Fate 165 of 304 j FSAR Page j 133 amended) Description 1 quantities to room 270, and also to the related figure note. The air flow quantities previously designated to ventilate room 271 were redirected to room 271, as the result of a revised calculation. ' Group: 4 I FSAR Change Request Number: 89 490 J Related SER Section: 9.4.2 , SER/SSER Impact: No ! Figure 9.4 2 See Sheet No(s):03- l Description (Correction) .. . Deletes the word " MAX" from the Fuel Handling Building Flow Diagram.. Justification: The word " MAX" is deleted from the flow diagram as.it provides no design basis restriction relative to flow values it is associated with. These flow values correspond to the design flow and the flow which is used for testing and balancing the system. The word
" MAX" restricts the use of tolerances normally utilized in testing and balancing the system.
Group: 3 i FSAR Change Request Number: 89-675.4 Related SER Section: 9.4.2 l SER/SSER Impact: No l Figure 9.4 2 See Sheet No(s):03 Description (Correction) Removes the blade packages from two dampers. Justification: To ensure that negative pressure requirements are maintained, dampers CPX VADPMC-04 and CPX-VADPOC 76 were originally sealed open. In order to provide further assurance that these dampers do not adversely impact the negai:1ve pressure requirements, the damper blade packages have been removed so that they can not be inadvertantly closed.
, Group: 3 FSAR Change Request Number: 89 675.5 Related SER Section: 9.4.2 SER/SSER Impact: No Figure 9.4 3 Description (Correction)
Shows heater as it was installed in the ductwork on the return line in the ventilation DC battery room for the Ventilation Turbine Building. Justification: The heater was not previously depicted on the figure because it was originally intended to be a physical part of the unit. However, since it was not made a physical part of the unit it was installed in the ductwork on the return line in the ventilation DC
i Attachment to TXX 90011 < January 15. 1990 Page 166 of 304 . f FSAR Page ; (as .. amended ) Description battery room for the Ventilation Turbine Building. l NOTE: Figure 9.4 3 was transmitted to the NRC as part of FSAR Amendment 77, and inadvertently included ; the change described above. The detailed description i for this change is being included as part of Amendment ' 78, since the change was processed for this amendment. ; i The figure will not be transmitted again since the > change is already incorporated. ! Group 3 , { FSAR Change Request Number: B M 36 Related SER Section: 9.4.5 SER/SSER impact: No I
, figure 9.4 3
Description:
(Update) .' Minor figure updates. Justification: No justification required. See discussion under Figure 9.1-13. Group: 4 - FSAR Change Request Number: 89 726.1 Related SER Section: 9.4 . SER/SSER Impact: No l j' Figure 9.4 4 See Sheet No(s):01 ! Description .(Revision)- [ Deletes diesel generator building ventilation system ; heaters. " Justification: Calculation shows that the two existing unit heaters in-each diesel generator area, together with the heat generated from'the diesel's keep warm system, provide l sufficient heat to maintain design temperatures in the l Diesel Generator Rooms, the Equipment Rooms.-and the ! Day Tank Rooms during the winter months.- This change has been evaluated under the TV Electric 50.59 program' per TXX 89718 dated September 28, 1989. Group: 2 ,
, FSAR Change Request Number: 89 421.1 Related SER Section: 9.4.5 l SER/SSER Impact: No i l
Figure 9.4-4 See Sheet No(s):01 I
Description:
(Correction) - Changes air. flow rates in the Ventilation and Safeguard area by re pitching fan blades to supply'more condi- ! tioned air. . Justification: During HFT. the design norma 11 maximum temperature.of 104F was slightly exceeded. Since the supply fans were not operating at their full rated capacity the fan blades were re pitched in order to supply more condi-l tioned air to the Ventilation Safeguard and Electrical
. . , . . , . , ...,.n-..,
_, %n , - - - - - ~ U Att ac'hsGnt: to~TXX 90011 January 15, 3990 Page 167 of 304 FSAR Page (as_emanded) hacrintion area. As a result of the re-pitching of the fan blades, the air flow rates changed.
-Group: 31 FSAR Change Request = Number: 89 518 Related SER Section' : 9.4.4: SSER4 .9.4.4 SER/SSER Impact: No Figure'9.4 4 See Sheet No(s):01 and 02
Description:
-(Update) Minor figure updates. Justification: No justification required. See discussion under Figure 9.1-13. Group: 4 FSAR Change Request Number: 89-726.1 Related SER Section: 9.4' SER/SSER Impact: No Figure 9.4-4 See Sheet No(s):02 .
Description:
(Addition). Adds appropriate ^ air flow rates.
' Justification:
Appropriate air' flow' rates are added t'o reflect _ air flow rates . inadvertently left off flow diagrams. Croup:: 3 FSAR Change Request Number:.89-536.1-. Related SER Section: 9.4.4:- SSER4--9.4.4 SER/SSER Impact: No Figure 9.4 4 See Sheet No(s):02 Descriptiont (Correction)_ _ Deletes the word " MAX" from the.Safequard=and Electrical Area Flow Diagram. Justification: The word " MAX" is deleted from the flow. diagram-as it provides no design basis restriction relative to flow values it is associated-with. These flow values-correspond to the design flow-and'the flow which is used for testing ~and balancing the: system. The word
" MAX"; restricts the' use of tolerancas normally utilized in testing and balancing the system.
Group:'3 FSAR Change Request Number:.89-675.6 Related SER'Section 9;4.4 SER/SSER Impact:.No Figure 9.4-5
Description:
(Correction) Adds flow values to the Containment Flow Diagram. Justification: Adds the flow values utilized in conducting the testing and balancing of the system consistent .with CPSES calculations. _ _ _ _ _ _ . _ . . _ - _ - - - _ - _ = _ - - - - - - - - - - - --
Attach 2ent to TXX-90011 January 15, 1990 Page 168 of 304' FSAR Page (as amended) Rescrintion Group: 3 FSAR Change Request Number: 89 675.7 Related SER Section: 9.4 SER/SSER Impact: No Figure 9.4-5 Descriptions (Correction) Deletes instrument valves from figure. Jus ti ficati on s . Based on the fact that the instrument' valves are'an integral part of the pressure indication instruments. ', and are not assigned a unique project tag no., the valves will be deleted as it is unnecessary to depict them on the figure. Group: 3 FSAR Change Request Number: 89-675.8 Related SER Section: 9.4 SER/SSER Impact: No Figure 9.4 6
Description:
(Correction) Corrects depiction of valves: valves shown to be globe ! valves are changed to butterfly valves, as indi~cated. - Justification:- Depiction of certain valves is corrected from globe-valves to butterfly valves, as a result of a review of the referenced specification. ' Group: 3 . 1 FSAR Change Request Number: 89 535.2 Related SER Section: 9.4.4: SSER4 9.4.4 I SER/SSER Impact: No Ffgure 9.4-6
Description:
(Correction) Adds a 3" restrictive flow orifice plate to eliminate the time restriction on the number of-hours'per year the Containment pressure relief valves may be open. Justification: The allowed accumulative opening time'for the 18-inch containment pressure relief discharge isolation valves 1 is changed to be unlimited. -This is-based on redesign :! of the. system which limits the' amount the valve will j open and adds an orifice plate which changes the =! effective diameter of-the valves to 3-inches from~the i combination of these modifications. Therefore. with. the valves essentially being equivalent to a-3-inch valve and being capable of' closure to meet the accident- i analysis assumptions any time, restrictions do not ? apply. Also, a clarification is made to indicate the amount of air flow exhausted equal to 784 cfm. which is ., a nominal value. ' This change was identified and accepted by the staff as-part of Technical Specifications changes in TXX-88780 dated.11-16-88. Attachment 9 pages 4A and 13 of 42. Group: 3
_ _ ___ ._ ___ _ _ __ _ _ _ __ ~ _ . _ _ _ _ _ _ . - _ . _ _ i Attachm3nt to TXX-90011 January 15, 1990 Page 169 of 304 FSAR Page [ (as amended) Description FSAR Change Request Number: 89 523.1 Related SER Section -6.2.3 SER/SSER Impact: Yes - SER Section 6.2.3, page 611', 3rd paragraph 1and- Section 22.2 (II.E.4.2), page 22-54. 7th paragraph are not ' consistent as a result of this change. Figure 9.4 6
Description:
(Correction) . . , Corrects detailsLfor typical. deluge and drain connections for hydrogen purge exhaust filtration units. Justification:= Piping safety class has been revised from 3 to 5 consistent with the declassification'of:the hydrogen purge system (information provided in a previous FSAR Amendment) and a piping classification boundary has been moved consistent with the as-built condition. Note 14 has been deleted since.it is no longer: applicable due;to these changes'in'the figure details'. ! Group: 3 - FSAR Change. Request Number: 89-675.9
- Related SER Section: 6-2.4 .
SER/SSER-Impacts:No Figure 9.4-6
Description:
(Revision) Revises figure toishow valves-1PN-001. -002. -003 and
-004 as locked closed.
Justifications-To ensure that-containment' integrity is maintaine', d local ~ vent, drain,. and test connection valves are locked closed, have capped ends and are under. administrative control. Therefore, to be consistent with.CPSES design documents and GDC 56 requirements, valves IPN-001', -002~ -003 and -004 have been locked closed and will be administrative 1y controlled. These test connection valves already have capped ends.- 1 Group: 3
, FSAR Change Request Number: 89-748.1- I Related SER Section: ~6 .2.3 SER/SSER Impact:JNo Figure 9.4-6
Description:
-(Revision) Figure update. Justification: ' Reflect test connections, vents and drains'inside-containment which are locked closed and' capped for containment integrity. Group: 3 . FSAR Change Request Number: 89-726.2 Related~SER Section:-9.4 SER/SSER Impact: No
?
- - -. ~ . . . . - - .- -
x Attach 2ent to TXX 90011 ~ January 15. 1990-Page 170 of 304 FSAR Page (as amended) Descrintion' Figure 9.4-6
Description:
(Clarification) Makes minor corrections / clarifications to'the flow diagrams. Justification:- The minor corrections / clarifications to the flow dia-grams are made to ensure. consistency'in documentation- l describing the equipment. I Group: 4. FSAR Change Request Number: 89-542.5 Related SER Section: 9.4.2 SER/SSER Impact: No Figure 9.4-7
Description:
(Correction) Adds temperatur'e switches to thermostatically control the SWI exhaust fans. Justification: Temperature switches have been added'to thermostatically control the-SWI exhaust 3 fans. The exhaust fans must be automatically controlled to maintain the design indoor conditions during different accident scenarios considered.under the Fire Safe Shutdown Analyses. Group: 3 FSAR Change Request Number: 89 562.1 -j Related SER Section: 9.4.5 SER/SSER Impact: No. j i Figure 9.4-7
Description:
(Update). Minor figure updates. Justification: 1 No justification required. See discussion under Figure 9.1-13. l Group: 4 ! FSAR Change Request Number: 89-726.1 i Related SER Section: 9.4 ; SER/SSER Impact: No i 1 Figure 9.4-B
Description:
(Clarification) ' l Renumbers the isolation dampers on the figure to match.- the vendor's test configuration. ~ Justification: The isolation dampers will be renumbered in order to ; reflect the vendor's test configuration.- Since these i dampers will be installed in the field in the exact. configuration as they were tested, they must be depicted in the correct order on the figure. Group: 4 FSAR Change Request Number: 89-492 I Related SER Section: 9.4.5 I SER/SSER Impact: No i 1
Attach 3ent - to TXX-90011 January 15, 1990' Page 171 of 304 l FSAR Page 1 (as amended) Descrintion Figure 9.4 8
Description:
(Update) Ninor figure updates. Justification: No justification required. See discussion under-Figure l 9.1-13. ! Group: 4 FSAR Change Request Number: 89-726.1 Related SER Section: 9.4 SER/SSER-Impact: No i Figure 9.4-8
-Description: (Revision)-
~ Justification:
Revises Note 5 and adds' Note 11 and 12. Restraining the dampers as' described in these notes-in their full open positions will ensure the system is balanced-during Unit 2 construction. Also,=the establisment of flow path will ensure-the area adjacent the control room envelope does not-become-pressurized to the point ; to affect the control room pressurization boundary. Group: 3 ! FSAR Change Request Number: SA-89-781 Related SER Section: 9.'4.3 SER/SSER Impact: No Figure 9.4-9
Description:
(Editorial) _ Removes a note and air flows to avoid duplication of L discrepancies pertaining to the primary ventilation supply and exhaust description.' { Justification: l Note was removed, since it was no longer relevant to this figure. The air flows were removed to a' void i duplication of discrepancies which were inadvertently left on when the new figure was_ issued. NOTE: Figure 9.4-9 was' transmitted to the NRC as part of FSAR Amendment 77, and inadvertently included the change described above. The detailed description for this change is being included as part of Amendment 78, since the change was processed for this' amendment. The figure will not be transmitted again since the change is already incorporated. ' Group: 4 FSAR Change Request Number: 89-495.2 Related SER Section: 9.4.1 SER/SSER 1mpact: No Figure 9.4-9
Description:
(Correction) 4 Adds and revises the details for the deluge and drain connections for ESF Filtration Units. Justification: Adds the details for the deluge and drain connections for ESF Filtration Units CPX-VAFUPK-01 & 02 and revises the similar details for ESF Filtration Units l
Attachaont to TXX-90011 January 15, 1990 Page 172 of 304 FSAR Page (as amended) Descrintiga CPX VAFUPL-15 & 16 to be consistent with as-built plant conditions. Revises. Note 18.to identify that ESF Units 15 & 16 will operate during a LOCA and Containment Purge. Note 19 is added to explain.the-revised details provided-for ESF Units 01 & 02. These changes provide consistency with-information submitted'in a previous FSAR Amendment. Group: 3 FSAR Change. Request Number: 89-675.10 l Related SER Section: 9.4.2 SER/SSER Impact: Yes SER indicates ~that there are two 50% capacity ESF exhaust filtration. units when there are currently four ESF exhaust filtration units which make up the Primary. 9 Plant Ventilation. System. This is consistent with '
-information submitted in a previous FSAR Amendment.
Figure 9.4-9 Descripti on: . (Correction) Corrects the flow-rates-associated with-the 4 ESF- i Filtration Units and clarifies Primary Plant ' Ventilation System design flows / operational configurations. Justification: I Corrects the flow rates' associated with ESF Filtration Units CPX-VAFUPK-01, 02, 15 & 16 and adds a reference to Note 18 which has been revised to' identify a. maximum air flow capacity of.15,000 CFM. Secondly, the figure is clarified by adding a table which provides the design flow values used as acceptance criteria for testing and balancing = of the Primary Plant Ventilation , System (PPVS) to ensure that'a slight negative pressure- l 1s maintained within the pressure boundary; This table j replaces a short summary description of the PPVS' .j operational configuration. l Group: 3 ' FSAR Change Request' Number:'89-675.11 ' Related.SER Section: 9.4.2
, SER/SSER Impact:-Yes -
SER indicates that there are two 50% capacity ESF I exhaust filtration units when there are currently.four 1 ESF exhaust filtration' units which make'up the Primary Plant Ventilation System. This is consistent with information submitted in a previous FSAR Amendment.
- Figure 9.4-9
Description:
(Update) Minor figure updates. Justification: No justification required. See discussion under Figure 9.1-13. l j Group: 4 FSAR Change Request Number: 89-726.1 Related.SER Section: 9.4 ' 1
E
- l Attach ent to TXX-90011' l January 15, 1990 1
- l Page_-173 of 304 j
-FSAR Page l (as _mendg[) Description SER/SSER Impact: No Figure 9.4-11 See Sheet No(s):01 . j L
Description:
-(Correction) i Adds _ vents for the. cooling coils in-the Turbine r Building Switchgear area cooler. l' Justification: .
- i. Vents are added for the cooling coils in the Turbine p Building Switchgear area cooler. Vents are required-to provide a path for air when the coils are filled- j with water.' If there is no method to remove this air,- ;
the pressure'in the. coils would build and the pumps- ( could experience cavitation. Thus~,-_the system would.
-be adversely affected and not perform as designed.- ~;
Group: 3 FSAR Change Request Number: 89-493 Related SER Section: 9.4.6- ' SER/SSER Impact: No-Figure 9.4-11 See Sheet No(s):01 . i
Description:
,devision)
Figure update. Justification: Provide _for system isolation between Unit 1- and Unit 2 during Unit 2 construction. Group: 3-FSAR-Change Request Number: 89-726.3- t Related SER Section: 9.4' SER/SSER Impact: No ' Figure 9.4-11 See Sheet No(s):02 j
Description:
(Correction) Deletes locked closed "LC" designation for select-valves in the-figure. Justification: In response to an observation by INP0 concerning excessive' numbers of locked valves.-TU-Electric ' s reviewed requirements for locked. valves and identified valves which-were not required to be, locked. Locked < closed notation'for these' valves is being" deleted. consistent with CPSES design documents. Group: 3 FSAR Change Request Number: 89-675.12 Related SER Section: 9.4 SER/SSER Impact:-No Figure 9.4-11 See Sheet No(s):03
Description:
(Update) Minor figure updates. Justification: i No justification required. See discussion under Figure 9.1-13.
Attach:ent- to TXX 90011 January 15, 1990-Page 174 of 304 FSAR Page. (as amended) Descrintion Group: 4 FSAR Change Request Number: 89-726.1 Related SER Section: 9.4 l SER/SSER Impact: No Figure 9.4 See Sheet No(s):04 l
Description:
(Correction)~ l Justification: Corrects valve tag numbers and adds drain' connection: provided for the auxiliary building ventilation equip-ment room cooling unit cooling coils.- Group: 4 FSAR Change Request Number: SA 89-781 Related SER Section: 9.4.4
-SER/SSER Impact: No-Figure 9.4 12
Description:
- (Correction)
! Deletes locked closed "LC" designationifor select valves in the' figure. Justification: In response to an observation by INP0 concerning
-excessive numbers :ofilocked valves TU Electric' ]
reviewed requirements for locked valves and-identified valves which.were not required to be locked.- Locked closed notation for these valves 11s being deleted ~ consistent with CPSES design documents.- Group: 3: FSAR Change Request Number: 89-675.13 Related SER Section: 9.4.6. i SER/SSER Impact:.No i i Figure 9.4-15
Description:
(Update) i Minor figure updates.. ! Justification: , No justification required. . See-discussion under Figure ; 9.1-13.- -) Group: 4 . _
/ FSAR Change Request Number: 89-726.1 i l Related SER Section: 9.4 SER/SSER Impact: No -i i
i 9.4C-1, 2
Description:
(Correction) l Justification: ; Clarifies the system description of the Diesel i Generator Building. Ventilation System. Group: 3 i FSAR Change Request Number: 89-410 '! 4 Related SER Section: 9.4.5 ; 4
- i l
' Attach::Gnt- to TXX-90011'
-January; 15, 1990- 1 Page 175 of 304
]
[ FSAR Page j (as ameridad) Description SER/SSER Impact: Yes SER states that each diesel' generator. room has a ' ventilation system with an_ exhaust fan when there. are actually 4 exhaust fans-for.each room's ventilation- > system. However, the CPSES design' basis remains unaffected by this clarification. l 9.4C-2
Description:
(Addition) -; Adds. description of several actions which will be taken to ensure that design. temperatures.-will be: maintained. Justification: r Provides additional assurance that the Diesel' Generator Rooms, the Equipment. Rooms, and the Day Tank. Rooms will be maintained within design temperatures during the winter months. . Grcup: 3. . FSAR Change Request Number: 89-421.2 Related SER Section: 9.4~.5 ..4 SER/SSER Impact: No 9.4C 4
Description:
~(Correction) Revises the. testing-requirements for the ductwor'k in the Diesel Generator Building. Justification:.
- The requirements concerning the testing of the ductwork-in the Diesel Generator Building have been revised.
This ductwork is not associated with any atmospheric ' air cleanup unit. Therefore, the requirement of. AN5I N510 is not applicable. -j Group: 3 FSAR Change Request. Number: 89-562.2- " Related SER Section: 9.4.5' , SER/SSER Impact: No 9.4C-10
Description:
(Correction) l Deletes the word " constant". describing the relative i i humidity-percent by revising the text to reference both-the environment' temperature and relative humidity of- > the laboratories and other areas to' Table 9~.4-2.
- Justification: ,
The text has been revised to delete the word " constant" describing the relative humidity. percent by referencing both the environment temperature and relative humidity 1 of the laboratories and other areas to Table 9.4-2. This resolves-the-differences between the text and Table 9.4-2 for the percent relative humidity factor. j Group: 3 FSAR Change Request Number: 89-501 Related SER Section: 9.4.5 SER/SSER Impacts:No ( 4 3 4
- pwMest January Page 176 of 30415. 1990to TXX 9001 FSAR Page 1RL 2 )
9.4E-1, 2 \ DitsIlefJan
\
s See Page No(s):05
Description:
06 and 08 Justification:(Clarification) ' Ventilation Chilled WClarifies in co editorial ater System through minpre Group:rrect use ofand technical 4 changes to as reflect or FSAR terminology and u b ilthe 9.5-12 Related SER SectionChange : 89 422 tRequest conditions. Number SER/SSER Impact: : 9.4.6 No
Description:
Justification:(Correction) 330 ft to 300 ftCorrect is ey pump total value for jock A total th sufficient to Group:roughout 4 the systemmaintain dynam1c requithe head of 300 fdynamic h FSAR Change Request at all times. red water press,ure t 9.5-18. 19 Related Impact: SER/SSER SER Section:9.5.1: 89 429 Number: No
Description:
SSER)2 9.5.1 Justification:(Editorial) te Editorial corrections Group:xt was inserted in theto Amendment 4 nge. 76 cha wrong place. 9.5-26 Related SER SectionFSAR Change
- Number:
Added Request SER/SSER Impact: 9.5.1.1 89 439 No
Description:
Removal of (Revision) exposed structural ofsteel ithe description Justification: Originally, the fire n the turbine buildingthe the firepro support fire damexposed structural ste lproofing w e spreading rooms. perindeviations (SSER on the dampers TU Electric the turbine 12) buildi ng to eliminating with thePullman dampers (hasforreplaced the cable the the three hour building from er ng. barriin This the turbine the thereby buildineed to safe change doesstructural steel shutdown any adjacent structurewhich ability of unit equipment, one not effect separates the turb applicable or unit and does ne oil system not which impair contains the or the hydrogensafety functions. two to perform th to the three hour bu arrierb cooling systemNeither the turbine l Group:ilding 3 from the rest of are adjacent ube the plant.which separates ne the turbi
,w~~' ,-r ' -'
.- . -- .- - . . . - - . - _ ~ -
]
Attach ent to TXX-90011- ! January 15. 1990- ) Page 177 of 304' ; FSAR.Page (as amended) Descrintion FSAR Change Request Number: 89-525 SER/SSER Impact: No' , 9.5-48 -Description: (Clarification) Justification: In the-comparison of the CPSES fire protection program to BTP APCSB 9.5-1 App A, this' change clarifies that procurement may be performed by either TU Electric or the f$re protections system supplier. Group: 4-FSAR Change Request _ Number: 89-478 l Related SER Section: 9.5.1 SER/SSER Impact:'No 9.5-79
Description:
(Correction) _ Change Capacity of Fire Protection Water Storage
-Tanks Justification:.
Change to-adequately reflect the designed nominal capacity of the fire protection water storage tanks. Group:-3 : FSAR Change Request Number:- 89-625.1 Related SER Section:'9.5.1.5: SSER21-SER/SSER. Impact: Yes i Page 9-12 in SSER 21 lists the capacity of'the Fire Protection Water Storage Tank as 504.000- gall ons . -The-value in the FSAR has been. changed to 524,500 gallons j nominal, j i 9.5-92
Description:
(Revision)- ! Storage of Portable Fire-Extinguishers utilized for ! the Containment Building Justification: l Allows flexibility in the storage of portable fire extinguishers used-for the containment building j Group: 3 : FSAR Change Request Number: 89-625.3 i 3 Related SER Section: 9.5 SER/SSER Impact:'No. 9.5-96 Descript1on: (Correction) .: Allow for the installation of metal clad cabling.used j for low voltage, non' class IE system' rework. ' Justificationc ' These changes do not involve changes in license and do ! not result in failure to complete the fire protection program as approved by the commission. Metal clad j si cabling is-jacketed with Hypalon-for physical j protection of the aluminum sheathing, and its use is limited to 6 conductor No.- 10 cable size and smaller. ! l Installation of metal clad cabling in the Control. ! ! Room does not affect the approved Fire Protection-i l
Attach ent- to TXX-90011 January 15. 1990 Page 178 of 304 FSAR Page (as amended) Descrintion Program due to the following: 1)-Metal clad cabling is used primarily for rework of non clas IE lighting,-communications, fire detection and heat tracing, all of which require limited' amounts of isolated cabling. Single,-separated runs of. metal clad cable do:not represent significant a fire propogation paths.
- 2) Hetal clad-cabling is not being used in-significant concentrations. The quantities being used are,.
insignificant compared to scheduled cables and other. combustibles in the plant.
- 3) Metal clad cabling has been demonstrated to meet the IEEE 383 flame spread test requirements and is- ,
limited to low power systems applications. . -l These changes correct the FSAR to reflect changes previously transmitted in Amendment 77. Group: 3 FSAR Change Request Number: 89-617 SER/SSER Impact: No ; 9.5-113
Description:
(Addition) ! Expand description for carpet installation in the
. control room envelope. '
Justification: ..
^
Areas outside the " horseshoe" area of the control room have been identified as needing soundproofing. These-areas include the entry hallway,~ shift supervisor's office and the Jechnical Support Center which is located on elevation 840'6. These areas are in the control room " complex" and are supported by the same HVAC system. This is also fire area E0. This change i is consistent with letter TXX-89590 dated A'ug.. 30, 1989 ' which requested NRC review of the addition of carpet to these areas. ' Group: 3 FSAR Change Request Number: 89-575' Related SSER Section: SSER12 9.5.1 j SER/SSER Impact: No ^ 9.5-117
Description:
(Revision) Installt. tion of data link for Data Acquisition System Justification: Installation of a small amount of non IEEE-383 cable used in the Control Room / cable spreading room for Data j Acquisition System is justified as follows: '
- The fire hazard impact-is of a minor-nature with 3 cable runs totalling.195 feet of cable-installed in the Control Room and Cable Spreading Room to link the Data ;j Acquisition System (DAS) computer. 'l
- Cable is constructed of 24 - 26 gauge conductors l
insulated with .014 inches of PVC and jacketed by .035 ' inches of PVC.
Attach 2ent to TXX 90011 January- 15,'1990 Page 179 of 304 FSAR Page (as amended)- Descrintion
- The rooms through which non IEEE-383 cables travel.
are Control Room (Fire Zone- 65) equipped with hand held Halon and water extinguishers, and the Cable: Spreading Room (Fire Zone 64) equipped with fixed automatic Halon System and Fixed Water Suppression System.
- A low. impedance cable is required to meet data-transfer rates.- No.!EEE-383 cable. construction-providing the impedance values required was available.
- If the cable spreading- room and control room are affected by a fire, alternate shutdown is achievable.
from the Alternate. Shutdown Panel. This change does not affect _the ability of the plant-to-achieve and maintain safe shutdown in~the event of a fire. This change has been evaluated under the TU Electric 50.59 program per_TXX-89718_ dated September _ 28, 1989. Group: 2 FSAR Change Request Number: SA-89-777 Related SSER Section: SSER12 9.5.1 SER/SSER Impact: Yes SSER 12 page 9-23 explicitly describes the non-IEEE-383 4 cable in the cable spreading room and-its intended use. The SSER requires revision to include the Data 1 Acquisition System cabling which is'also non'-IEEE-383 < qualifYed. See above description, d 9.50 18 Description (Clarification). Justification: This change is= required to make the.FSAR consistent 1' with Deviation 10 of section V of the Fire Protection Report relative to the availability of~AC essential or DC emergency lighting for the control room during a fire. This change doen not affect the ability of the plant to achieve and maintain safe shutdown in the event of a fire. Group: 3 i
, FSAR Change Request Number: SA-89-786 i Related SSER Section: SSER21 9.5.1-SER/SSER Impact: No '
9.5-122, 123 See Page No(s):128, 129
Description:
(Clarification) 5 Justification: - Intraplant communication. system (public address system) clarified to identify type: Gaitronics Page/ Party. Description of Gaitronics clarified. Group: 4 i FSAR Change Request Number: 88-735.1 Related SER Section: 9.5.2 SER/SSER Impact: No e
Attach 2ent to TXX-90011 January 15, 1990-Page 180 of 304' FSAR Page-(as maanded) Descrintion 9.5-123, 124
Description:
(Clarification) Justification: Clarify description of Intraplant Telephone system and; correct referenced subsection. Group: 4 FSAR Change Request Number: 88-735.2-SER/SSER Impact: No 9.5-125, 126 See Page'No(c):129,'130' Descriptions (Clarification)- Justification: Clarify description of Plant Radio Transmitter Receiver System (Both plant and plant-to offsite). Reworded. sentances to provide clarity.- Group:-4 FSAR Change Request Number: 88-735.3 SER/SSER Impact: No ~j 9.5 126, 127
Description:
(Correction) -- Correct description of the Plant-to Offsite Emergency Telephone. systems. Justification: The PBX System has Northern Telecom XT with Dual! CPU's' '! in warehouse 'A' communications-center. Remote Peripheral- Equipment' (RPEL is ' located in the NOSF, OPS Admin -CPE and SSG bui, dings. Outdial trunks- ' are directed into the NOSF and warehouse 'A' -These trunks feed through the switches'via powerfail_ devices. ( During-normal operations, all ph'ones dial 9+ numbers. l Programed PBX.-options are available. Operator consoles have a " Red Button" that can be pushed during emergency operation.- ' When pushed. . all telephones designated as Emergency. Telephones have , a high priority. If the. PBX loses power,-relays i activate and Emergency Telephones are tied to Glen Rose l or Dallas dial tone. . In normal and emergency circumstances, the trunks j through the switches (PBX /RPE) have proven reliab1>e 4 and efficient. The user has enhanced functions such ! as call pickup. ring again, call' forward. etc.- Group: 4 FSAR Change Request Number: 88-735.4 i SER/SSER Impact: No 9.5-129, 131
Description:
(Clarification) Justification: Clarify description of sound-powered. telephone system. l Include descriptive words " refueling and' emergency ; loops of the sound-powered. telephone system." : Group: 4 FSAR Change Request Number: 88-735.5 SER/SSER Impact: No
ittach;ent- to TXX 90011 , January 15, 1990 ,i Page 181 of.304- . , FSAR Page ; (as amended) Description 3 9.5-133
Description:
(Correction) . . I Corrects the description for non-Class IE lighting inside containment. Justification: As previously' described in FSAR Amendment 77 the , containment lighting transformers have two Class 1E_ , circuit breakers in series, which meets the electrical' : separation requirements of FSAR:Section 8.3. .The "S" .l trip of the breaker has-been removed (it is not needed for separation).- The description of the AC-- lighting inside containment is being; revised consistent with the previous change to indicate that 't the system will no longer be shed during a LOCA from -- i the Class IE 480V System _(which is powered from the-
- diesel. generator during.a Loss of Offsite Power)..
Group: 3 i FSAR Change Request Number: 89-711.2 l Related SER Section: 8.4.5 SER/SSER' Impact: No The-AC lighting inside the containment has not been specifically discussed in the SER in either Sections 8.4.5 - 9.5.3.- The separation method discussed above has tw eviewed by the-NRC. , r l 9.5-140
Description:
(Editorial) l Justification: ! Removes sh'eet number reference for Figure.9.5-52-as a result of revised figures. Group:~4 FSAR Change Request Number: SA-89-710 Related SER.Section: 9.5.4 SER/SSER Impact: No 9.5-142. 144
Description:
(Revision) Revises the description of-the fuel oil storage tank , capacity of each diesel generator.'
' Justification:-
Minimum volume ef fuel oil in the Emergency Diesel Gen-erator' storage system.is revised from 100,000 gallons to 86,000 gallons.-This fuel oil volume.is~. based on the volume required for seven days at continuous rated load of the Diesel Generator in accordance with NRC Regulat-- ory Guide 1.137 Revision 0, and ANSI'N195-1976, plus the volume of unusable oil'in the storage tank. Fuel oil suction lift calculation is revised to remove the overconservative head loss penalty taken for the head - loss, which does not effects the pumps ability to reach its rated lift. Therefore, unusable volume of the fuel oil at the bottom of the. storage tank is reduced which , does not affect the safety of the plant. As the storage tank capa_ city remains unaltered._the
1
- Attach ent to TXX 90011 '
January 15, 1990 Page 182 of 304-l 1 FSAR Page (as amended) Descrintion reduction in the unusable volume of the fusi oii will . increase the allowable margin of fuel oil to permit 1 periodic testing. Based on the revised calculation. . this allowable margin of fuel-oil amounts to approxima- , tely 15 percent of the_ total fuel oil storage tank vol - use. j This change has been evaluated under the TV Electric 10CFR50.59 program per TXX-89718 dated Sept 28. 1989.. Group: 2 FSAR Change Request Number: 90-006.1 Related SER Section: 9.5.4.2 SER/SSER Impact: No , 9.5-154
Description:
(Editorial) Justification: Removes reference to FSAR figure to be consistent with : the revised drawings. .I Group: 4 FSAR Change Request Number: SA-89-710 - Related SER Section: 9.5.4 SER/SSER Impact: No-Table 9.5-11
Description:
(Clarification) Justification: Clarifies Diesel Generator (DG) Failure Modes and Effects Analysis-table by. revising 1the title of this , DG Auxiliary System te be consistent with the FSAR text and figures.
- Group: 4 FSAR Change Request _ Number: 89-430.1 Related SER Section: 9.5.4.2 <
, SER/SSER Impact:.No i Table 9.5-11
Description:
(Clarification)' Justification: - Clarifies Diesel Generator (DG) Failure Modes and Effects' Analysis table to ensure that it is clear-j that.the table applies to Diesel Nos. 1 4'2 for both Units 1 & 2. + Group: 4 FSAR Change Request Number: 89-430.2 Related SER Section: 9.5.4.2 SER/SSER Impact: No-Table 9.5-11
Description:
.(Correction)
Clarifies the diesel generator oil storage tank function. Justification: See justification provided in the previous justificati-on for 90-006.1. deleted. Group: 3
.._,..,,,s , . , , , , . , _ _ , , ,.,___m , _..,y r , .
Attachm2nt' - to TXX 90011 January. 15, 1990 Page 183 of 304-FSAR Page (as amended) Description-FSAR Change Request Number: 90-006.2 Related SER Section: 9.5.4.2' SER/SSER Impact: No Table 9.5-12
Description:
(Clarification) Justification: Clarifies Diesel Generator (DG) Failure Modes and-Effects Analysis table by revising the title of-certain DG Cooling Water System components to be consistent with_the FSAR text and figures. Group: 4 FSAR Change Request Number: 89-430.4 Related-SER Section:.9.5.5 SER/SSER Impact: No i Table 9.5 12
Description:
.(Clarification) Justification: Clarifies Diesel Generator (DG) Failure Modes and - Effects Analysis-table to ensure that it is clear that the table applies to Diesel Nos. 1 &'2_for-both Units 1 & 2. Group: 4 FSAR Change Request Number: 89-430.5 Related SER Section: 9.5.5 SER/SSER Impact: No' Table 9.5-12
Description:
(Revision) ~ Revises the 'Effect-on System'-from diesel IEG1'is ; available to diesel IEG2 is available. : Justification: . l The failure of Cooling Water System-jacket water keep warm pump-or standby electric heater _potentially renders the diesel inoperable. Therefore, the 'Effect. on System' is revised from 1EG1 is available to IEG2 is I available, j Group: 3 ! FSAR Change Request Number: 89-653.1 l j Related SER Section: 9.5.5 j SER/SSER Impact: No Table 9.5 13
Description:
(Clarification) Justification: l Clarifies' Diesel Generator (DG). Failure Modes and ! Effects Analysis table to ensure that it is clear that the table app 111es to Diesel Nos. 1 & 2'for both Units 1 & 2. Group: 4 FSAR Change Request Number: 89-430.3 l Related SER Section: 9.5.6 SER/SSER Impact: No i
L l Attachagnt .to TXX 90011 January 15. 1990 Page 184 of 304-FSAR Page (as amended) Description Table 9.5-14 Description (Clarification) Justification: Clarifies Diesel Generator (DG) Failure Mode and Effects Analysis table by revising the title of-this DG Auxiliary System and certain of its components to be consistent with the FSAR text and figures. L Group: 4 i . FSAR Change Request Number: 89-430.6 Related SER Section: 9.5.7 SER/SSER 1mpact: No Table 9.5-14
Description:
(Clarification)' ' Justification:' I Clarifies Diesel' Generator-(DG) Failure Modes and Effects Analysis table to ensure that it is clear that the table applies to Diesel Nos. 1 & 2 for-both Units 1 & 2. Group: 4 . FSAR Change Request Number: 89 430.7 Related-SER Sectiun: 9.5.7 SER/SSER Impact:: No -! Table 9.5-14
Description:
. (Revision) l Revises the 'Effect on System' from diesel-1EG1 is Jl available to diesel IEG2 is available.- y Justification: . .
, j The failure of Lube'011 System-lube oil heater or pre-lube pump potentially-renders the diesel inoperable.
Therefore, the "Effect on System' is revised from'1EG1 is available to IEG2 is available. Group: 3 FSAR Change Request Number: 89-653.2 I Related SER Section: 9.5.7' j SER/SSER Impact: No Table 9.5-15
Description:
(Clarification) Justification: Clarifies Diesel Generator (DG) Failure Modes and-Effects Analysis table by revising the title of-certain DG Combustion Air Intake and Exhaust System-figures. j ' Group: 4 i FSAR Change Request Number: 89-430.8 ! Related SER Section: 9.5.8 i SER/SSER Impact: No Table 9.5-15 See Sheet No(s):01. 02 and 03 -
Description:
(Clarification) ! Justification: Clarifies Diesel Generator (DG) Failure Modes and Effects Analysis table to ensure that it is clear that the table applies to Diesel Hos.1 & 2 for both i i.. . _ , _ _ _ _ _ _ ___ ------e--- - - - "M
Attach;ent' to TXX-90011 January 15.-1990 Page 185 of 304 l FSAR Page (as amended) Descrintion Units 1 & 2. Group: 4 FSAR Change Request Number: 89 430.9' Related SER Section: 9.5.8 SER/SSER Impact: No-Figure 9.5-43
Description:
(Clarification) Justification:- Minor changes-to_FSAR Figures provide a consistent level,of detail between FSAR figures and station flow diagrams. Added drain lines, updated Title block on Figure 9.5-45 SH 1. Group: 4 FSAR Change Request Number: 89-484 ' Related SER Section: 9.5.1 SER/SSER Impact: No Figure 9.5-43 See Sheet No(s):01 1
Description:
(Clarification) Justifications- j Label fire protection supply line on Figure 9.5 61. j Add 4QA boundaries to Figures 9.5 43:Sh 1 and 9.5-61.- Group: FSAR Change Request Number: 89-435' Related SER Section: 9.5.1-SER/SSER Impact: No Figure 9.5
Description:
(Clarification) Justification:. -j Minor changes to'FSAR Figures provide a consistent level of detail between'FSAR figures and station flow diagrams. -Added drain lines, updated Title block.on ; Figure 9.5-45 SH 1. l Group: 4 ; FSAR Change Request Number: 89-484 ; Related SER Section: 9.5.1 1 SER/SSER Impact: No ' i e Figure 9.5-44 See Sheet No(s):01
Description:
(Clarification) Justification: , Minor changes clarify piping numbers and drawing references. -L Group: 4 FSAR Change Request Number: 89-486 Related SER Section: 9.5.1 SER/SSER Impact: No
1 Attach;snt to TXX 90011 j January- 15, 1990 -A Page 186 of 304 j i FSAR Page (as. amended) Descrintion Figure 9.5-45 See Sheet No(s):01 and 02 ,
Description:
(Clarification) Justification: , Minor changes to the figures reflect as-built condition and provide consistency with the text. Group: 4 - FSAR Change Request Number: 89 463 r Related SER Section: 9.5.1- i SER/SSER Impact: No - Figure 9.5-45 See Sheet No(s):01 and 02 *
Description:
(Clarification): ; Justification: Minor changes to FSAR Figures provide a consistent
~
level of detail between FSAR figures and station flow diagrams. Added drain lines, updated Title block on Figure 9.5-45 SH 1. Group: 4 FSAR Change Request Number: 89-484 . Related SER Section: 9.5.1 l SER/SSER Impact: No-f Figure 9.5-46 See Sheet No(s):01
Description:
(Clarification) Justification:- Minor changes to FSAR Figures provide- a consistent ! level of detail between FSAR figures and station flow diagrams.- Added drain lines -updated Title block on Figure 9.5-45 SH 1. Group: 4-
. FSAR Change Request, Number: 89 484 Related SER Section: 9.5.1 SER/SSER Impact: No i
Figure 9.5-47 See Sheet No(s):02
Description:
(Clarification)- Justification: i j Minor changes to FSAR Figures provide a consistent: . , , level of detail between-FSAR figures and station-flow
- diagrams. Added drain lines, updated Title block on i Figure 9.5-45 SH 1. '
Group: 4
- FSAR Change Request Number: 89-484 Related SER Section: 9.5.1 '
SER/SSER Impact: No Figure 9.5-47 See Sheet No(s):02
Description:
(Clarification) Justification: Minor changes to the figures reflect as-built condition and provide consistency with the text.
; Group: 4
i Attachment to TXX 90011- f* January: 15. 1990 ' Page 187 of 304 . FSAR Page (as amended). -Descrintion j FSAR Change Request Number: 89-463 !' Related SER Section: 9.5.1 L SER/SSER Impact: No l-Figure 9.5-52 See Sheet No(s):01 and 02 I
Description:
(Revision) ! l Deletes. locked-closed designation from valves.on Sheets 1 & 2. Adds differential pressure device for , l duplex filterL(on engine), and changes name from
' duplex strainerto ' duplex filter'.
. Justification: *
(1) The locked-closed designation is deleted from-valves on Sheets 1 & 2, since locking provisions are
]
not-required for_ diesel fuel oil fill valves. These < provisions are not required as a result of.the }
' existence of other administrative and design control-features. '
(2) A diffe'rential pressure device fo'r the duplex fil-
.ter (on engine) is now.-shown=in response to-a request made by an NRC technical reviewer, l (3) The term ' duplex strainer' is corrected to read ' duplex filter' per referenced-drawing.
Group:.3 FSAR Change Request Number: 89-654 i Related SER Section: 9.5.7
. SER/SSER Impact: No '
L Figure 9.5-52 See Sheet No(s):01 and-02 L
Description:
(Editorial) L Justification:- These drawings have been redrawn and consolidated to 1: show each diesel subsystem on each drawing series. Group: 4- . i FSAR Change Request Number: SA-89-710 Related'SER Section: 9.5.4 SER/SSER_ Impact: No Figure 9.5-54 See Sheet No(s):01 and 02.-
Description:
(Editorial)
-Justification:
These drawings have been redrawn and consolidated to -j show each diesel subsystem on each drawing' series. 1 Group: 4 FSAR Change Request, Number: SA-89-710 Related SER Section: 9.5.4 , SER/SSER Impact:.No. , Figure 9.5-55 See Sheet No(s):01 and 02 '
Description:
(Editorial) Justification: ' These drawings have been redrawn and consolidated to show each' diesel subsystem on each drawing series. -
Attach ent' .to TXX 90011 i January 15. 1990 -! Page'188 of 304 I l I 1 FSAR Page
- (as amended) Description l 1 l
l Group: 4 FSAR Change Request Number: SA 89 710 , Related SER-Section: 9.5.4 SER/SSER Impact: No Figure 9.5-56 See Sheet No(s):01 and 02 ;
Description:
(Editorial)- Justification: ~ These drawings'have been redrawn =and consolidated 1to d show each-diesel subsystem on each drawing series. Group: 4 . 9 FSAR Change Request Number: SA-89-710
- l Related SER Section: 9.5.4 SER/SSER Impact: No j Figure 9.5-57 See Sheet No(s):01 and 02 Description (Editorial)
Justification: These drawings have been redrawn and consolidated to show each diesel subsystem on each drawing series. Group: 4 FSAR Change Request Number: SA 89-710' Related SER Section: 9.5.4 SER/SSER Impact: No . Figure 9.5-61 See Sheet No(s):01 ~
Description:
(Clarification) l Justification: l- Label fire protection supply line on Figure'9.5 61. L Add QA boundaries to Figures.9.5'43 Sh I and 9.5-61. - Group: 4 FSAR Change Request-Number: 89 435 Related SER Section:-9.5.1 1 SER/SSER' Impact: No . 10.2-37
Description:
(Addition): . . . Adds discussion of LP turbine disk inspection.
, Justification:
By letters dated September 11, 198'4 and' July 15, 1985 TV Electric described ultrasonic-inspections to be performed on bore'and keyway. areas.of the=LP turbines. The NRC requested that this information-be included in the FSAR. Group: 3 FSAR Change Request Number: 89-805.1 ' Related SER Section: 10. 2 : . SSER21 1.9 SER/SSER Impact: Yes SSER 21 Section 1.9 contains ' License Condition 2 which' is expected to be removed by this FSAR change. " i
--_m__________________.____________.___.______.m
' Attach 3.ent to TXX 90011' j January 15, 1990 1 Page 189 of 304 ;
e
-)
FSAR Page (as amended) Descrintion ] J 10.2-41 Description (Addition) _ I Adds LP turbine inspection references , Justification: ) Includes . Utility. Power Corporation Engineering Reports' ' ER 8401 and ER-8402 as new references 4 and 5 which describe the technical bases and the frequency'of the 4 ultrasonic' inspection of LP. turbine disks., Group: 3 FSAR Change Request Number: 89-805.2' ! Related SER Section: 10.2: SSER21 1.9 . SER/SSER' Impact: Yes ; SSER 21 Section 1.9 contains licensing condition 2-which is expected to be removed by this FSAR revision. t 10.3 2. 7 Description (Clarification) The words "at least" were added to clarify the' ' description of no-load steam flow through the' steam-generator-power-operated relief valves, i Justification: Group: 4 FSAR Change Request Number: 89-560.2 SER/SSER Impact: No
- 10.3-8
Description:
(Correction) !~ Changes trip switch positions from " trip and auto" to -+
"close, auto, and reset": clarifies description of. trip i 1
switches. Justification: Correct this section to-reflect as-built conditions. . l' Group: 4 FSAR Change Request Number: 89-292.2 SER/SSER Impact: No 10.3-22 Description (Revision). Fracture toughness of'the'feedwater isolation valves , (additional information provided after-the discussion - with NRC on previous FSAR change submitted in FSAR Amen
, ment 77)-
Justification: ' Revises the FSAR section based on the discussion with-NRC and the work performed as per engineering report ER-DBE-ME-045. Supplemental impact testing performed on ' portions of representative samples of the valve body, neck. and bonnet of the feedwater isolation valves yie- , ided results which were not in accordance with the ASME-code requirements for fracture toughnesss for material - (NC-2300), based on a minimum service temperature of 40 F. The results of the supplemental testing are discus- . sed in Engineering report ER-DBE-ME-045. In addition a-fracture mechanics analysis is detailed in calculation ' 16345-ME(B)-274 R/1 " Resistance of feedwater valves to brittle fracture".
.g.4,-w .:a ,.wa. _,. 4 e u.4..- e.-ea m a
-.a. -
ass , ,m.g, Attach:ent to TXX 90011
~ January 15. 1990 q
. Page 190 of 304 .
FSAR Page igi amended) Description The fracture toghness requirements are satisfied with a metal temperature of 90:F for the valve body and neck. . therefore this portion will be maintained above 90 F prior to full pressurization of the valves. The~ valve bonnet fracture toughness has-been demonstrated by the [ fracture mechanics analysis calculation in ceajuction ' with a volumetric non-destructive examination which-determined that there are no significant material flaws which could lead to fracture p'ropogation. As a result, minimum temp limitations will be imposed, on the feedwater isolation valves 1HV-2134'.2135.2136, 2137. The feedwater isolation valves must bo verified to be above 90 F prior to entering MODE.3. RCS Tavg:)- 350 F, which corresponds to approximate 140 150 psig. The maximum presssurization during cold conditions > (valve temp < 90.F) should be limited to no more th'an' 20 % of the valve hydrostatic test pressure _(3375x205-675 psig)~which exceeds the condensate pump' dead head discharge pressure (Ref: ER-DBE-ME-045). During plant startup it is possible_to cold pressurize ' the valves from the condensate. pumps / feed pumps'or back pressurization from-the steam generators. Imposing the MCDE 3 limitation.will prevent-the back-pressuriza- , tion from the steam generators.' Pressurization from the condensate pumps 1s-normally ' prevented ----continued to next page------------------ Grcup: 2-FSAR Change' Request Number: 89-807 Related SER Section: 10.3.3-SER/SSER Impact: Yes The NRC is in the process of reviewing.the design in FSAR Amendement 78 . 10.3-22
Description:
.(Revision)..
Justification:
-------continued from previous page-------------------
due to the manual isolation' valves upstream of each FIV -
, being closed anytime'the feedwater headers are pressur- !
ized 'during long cycle condensate' flush operation or, i condensate pump minimum flow operation. ! Steam Turbine driven ~ feed. pumps are started during MODE J 2 when sufficient steam is ava11ble for pump operation. .) Pressurization of the FIV from the Main Feed Pumps will. 1 therefore occur only' after MODE 3 with :the metal tempe-rature of the FIV's being at or above.90 F. This change has been' evaluated under the--TU Electric 10 CFR 50.59 process as described in TXX-89718. dated 9/28/89. Group: 2 FSAR Change Request Number: 80 807 Related SER Section: 10.3.3 SER/SSER Impact: No-
Attach;ent- to TXX 90011 January 15. 1990 Page 191 of-304 FSAR Page (as amended) Description Table 10.3 3
Description:
(Clarification) The word " minimum" was added to clerify the description of steam flow at no load.-
~ Justification:
Group: 4 FSAR Change Request Number: 89-560.1 SER/SSER Impact: No Table 10.3 11 See Sheet No(s):01 and 02
Description:
(Correction) Revises Table items to reflect as built conditions.. Justification: .. { Items in the Table were revised to reflect as-built-conditions. In order to reduce leakage paths, restriction orifices were replaced with steam traps. --R and fail-open bypass valves were changed'to fail, closed for condensate removal paths upstream of turbine stop valves. Group: 3 FSAR Change Request Number: 89-560.3 Related SER Section: 10.3.2 SER/SSER Impact: No' l l Figure 10.3-1 See Sheet No(s):01, 02, 04 and 05' j Description (Correction)- Deletion of locked closed (LC) and locked open (LO) notation for selected valves in the figure.-- Justification: In response to-an observation by INPO concerning excessive numbers of locked valves,..TU Electric reviewed requirements for locked valves and identified -i valves which were not required to be locked. Locked ! notation for these-valves are being deleted. Group: 3 FSAR Change Request Number: 89-596 .i Related SER Section: 10.3.1 j
, SER/SSER Impact:.No -!
Figure 10.3-1 See Sheet No(s):02
~
Description:
(Addition) i Add vendor supplied pressure indication for the high pressure turbine Justification: added the vendor supplied pressure indication instrume-nt to high pressure turbine for' clarity. Group: 3 - FSAR Change Request Number: 89-775 Related SER Section: 10.2 SER/SSER Impact: No I d O
Attach ent to TXX-90011~ January-15, 1990-Page 192 of 304 FSAR Pege (as amended) Descrintion Figure 10.3-1 See Sheet No(s):03
Description:
(Correction)- Replaces vendor tag numbers for the pressure and temperature transmitters with unique CPSES tag numbers. . Justifications ! Equipment should have unique CPSES tag numbers rather than vendor tag numbers. Group:-4 FSAR Change Request Number: 89-431 SER/SSER Impact: No Figure 10.3-1 See Sheet No(s):03
Description:
( Revi si on)
. Deletes instruments PS 2111A & B, PS 2112A & B, PS-6590. 6591, & 6592, and Note 13.
Justification: Deletes instruments and note as they are duplicates and. are shown on other referenced' drawings. This justification was inadvertantly omitted from FSAR. Amendment 76 and is being provided now to support'the- . revised Figure 10.3-1 (Sh,~3) which was submitted in FSAR Amendment 76. Group: 3 FSAR Change Request Number.: 88-228.1 Related SER Section: 10.4.4 ; SER/SSER Impact: No 1 1 Figure 10.3-1 See Sheet No(s):04
Description:
(Revision) Deletes instruments PS-6590, 6591, and 6592. Justification: > Deletes instruments es they are-duplicates and ! are shown on other referenced. drawings. 1 This justification was inadvertantly omitted from:FSAR ! Amendment 76 and is being provided now to support the revised Figure 10.3-1 (Sh.'4)'which was submitted in , FSAR Amendment 76. R
, Group: 3 i FSAR Change Request Number: 88-228.2. :
Related SER Section: 10.4.4 i SER/SSER Impact: No. A 10.4-8
Description:
(Correction) Clarifies the number of radiation monitors provided for ! the measurement of condenser off-gases. 1 Justification: ; The'FSAR has been revised to clarify that there is only i one radiation monitor provided on the condenser vaccuum pumps discharge'line. This change'is consistent with o as-built plant conditions and FSAR Sections 10.4 and 11.5. Group: 3 7' it I i
Attachment -to TXX 90011 January 15.-1990 .l
' Page 193 of 304 l 1
J FSAR Page (as amended)- Descrintion FSAR Change Request Number: 89-731.1 ; Related SER Section: 10.4.2 .
- l. SER/SSER Impact: No 10.4-10 See Page No(s):13 and 35 ,
l
Description:
(Addition) Adds vacuum breaker to Circulating Water System ' L Justification: l An air operated vacuum breaker is added to the main condenser outlet waterboxes to protect the. tube side r components-from transients (such as waterhammer) in-the event of simultaneous trip of all four Cire water-pumps : , Group: 3 L FSAR Change Request Number: 89-754.1 Related SER Section: 10.4 ' l SER/SSER Impact: No l < 10.4 14
Description:
(Correction) Clarifies the description of the radiation monitor which measures the radiation level of the. condenser off-gases.
- Justification
- {
i The description-is revised to identify that a sample. pump. diverts-a portion;of the-condenser'off-gases-through the radiation monitor and.back'to'the discharge. line. Also, the change deletes the words " exhaust" &
"CEV. pump suction. header" and replaces them with
" discharge" to be consistent with FSAR Sections l 10.4.1.1.5 & 10.4.2.3. These changes are consistent with as-built plant conditions.- ,
! Group: 3 FSAR Change Request Number: 89-731.2' s Related SER Section: 10.4.2 j SER/SSER Impact: No 10.4-31
Description:
(Clarification)
-Clarifies text to specify that steam dump valves met o a
, certain previously stated requirements during initial shcp testing. '
4 Justification: The text was clarified to specify that the referenced tests on the steam dump valves were performed as vendor 4-shop tests not as startup'or operational tests. Listing of the tests without the clarification may be confusing, since the FSAR section mainly discusses' site' testing and infers a periodic performance of the tests listed. Group: 4 FSAR Change Request Number: 89-790 Related SER Section: 10.4.4 d SER/SSER Impact: No ' 1
IAttachasnt to TXX-90011: January 15 1990-Page 194 of 304 FSAR Page (as amended)- Description 10.4 35, 37
Description:
(Correction) j Removes references to sodium bromide addition to the circulating' water, and reflects the as built condition of the sodium'hypochlorite system-at the time _of fuel load. Justification: The reference to sodium bromide addition to the circulating water has been removed.- These changes' reflect the plant configuration for . chemically controlling the organic fouling at the time of fuel-load. Group: 3 FSAR Change Request Number: 89-598.3 Related SER Section: 10.4.5 SER/SSER Impacts:No 10.4 36
Description:
(Correction) Deletes the initial hydrostatic test requirementifor- ' the Circulating Water Pumps-(CW), and clarifies the performance test'of the CW Pumps. Justification: Circulating Water System is-not a safety related system-and there is.no safety function' involved;with this-system. There'is no-safety related equipment located j in the vicinity of the CW Pumps. so~that leakage . through the pumps cannot-impact the operability ofEthe safety related equipment._ In.the event'that-the CW Pumps leak, it is contained in' one intake _ structure ' and the plant will _ operate at a reduced load. The' CWi Pumps run as a low pressure application and.have been operating since 1980 without any-leakage. TV Electric feels that the initial hydrostatic testing of the pumps-is not required and hence:it is not specified in the specifications-or purchase order.- However the model I tests of large CW Pumps were performed per.the . Hydraulic Institute Standards. Group: 3
, FSAR Change Request Number: 89-761 Related SER Section: 10.4.5 SER/SSER Impact: No a
10.4-63
Description:
(Correction) I Changes the-low pressure heater bypass valve opening { time from two seconds to two and a half seconds. ' Justification: ., The low pressure heater bypass valve opening. time was ' changed to 2.5 seconds in Section 10.4.7.2.1 in a pre-vous Amendment. The change is being made'to Section 10.4.7.5 to be consistent with the previous' change' . q Group: 4 FSAR Change Request Number: 89-574 i I Related SER Section: 10.4.7 :i 1 1
Attachm2nt to TXX 90011 ) January 15; 1990 i Page 195 of 304 FSAR Page (as amended) Description SER/SSER Impact: No 10.4 67 Descriptions (Editorial) Corrects typo. Justifications-Group: 4 : FSAR Change Request Number: 89 292.1 l l SER/SSER Impact: No i 10.4-69 Description (Clarification) ! Clarifies description of operation of the feedwater i 4 isolation bypass valve and feedwater is01stion valve ! with respect to water hammer permissives. [ Justifications t Group: 4 : FSAR Change Request Number: 89 292.3 i SER/SSER Impact: No i I , 10.4 92 Descriptions (Revision) ! Revises Auxiliary feedwater turbine overspeed setpoint. Justifications Overspeed set point is reduced from 125% to 116.6% of i ' rated speed on the mechanical overspeed trip device. The reduction was necessary to prevent exceeding the i discharge piping design pressure during a maximum overspeed condition. . TU Electric letter TXX 89494 ' dated Jul) 31, 1989 reported the condition to the NRC 6 as part of a review to determine reportability : under 10CFR50.55(e). The condition was determirmd to ! be not reportable, however, the reduced overspeed { setpoint will ensure the maximum design discharge
- pressure is not exceeded.
J Group 3 ' i FSAR Change Request Number: 90 008 Related SER Section: 10.4.9 i SER/SSER Impact: No 10.4 131 , Det.riptions (Correction) inserts statement to reflect ANSI B31.1 testing performed on the Hydrogen Supply System. Justification: : The Hydrogen Supply System was pneumatically tested . to 1.2 times the design pressure. ANS! B31.1 allows ' pneumatic testing in place of hydrostatic testing. ! Group: 3 FSAR Change Request humber: 89 760 SER/SSER !apact: No e
'k
Attachment to TXX+90011 ! January 15. 1990 Page 196 of 304 . FSAR Page (as. amended) Descristion i Table 10.4 8 See Sheet No(s):01 ! Descriptions (Correction) )
- Revises the motor driven auxiliary feedwater pump j runout flow. J Justifications !
The runout flow for the motor driven auxiliary pumps 1 has been revised. The auxiliary feedwater pressure. ) control valves were switched to automatic control to i provide protection for the a m or-driven auxiliary ! feedwater pumps by limiting the duration of excessive i pump discharge flow when a faulted loop occurs or the i pumps are started against a low pressure in the i discharge lines. -The automatic control process ; setpoints have been based upon the hydraulic condition at pump Best Efficiency Point (BEP) of 800 gpe. ; Therefore, the high flow process setpoint is 800 ope. , From the vendor performance curves at an operational
- limitation of 800 gpe, there is ample NPSHA to meet i the NPSHR of each motor driven auxiliary feedwater l pump to avoid pump cavitation and any deleterious- ;
affects on the pump. In addition, the brake horsepower is well within the. service factor. The Design Base i i_ Document already identifies 800 ppm as the runout flow for the motor driven auxiliary feedwater pumps. Group 3 , FSAR Change Request Number: 89 558 l>
- Related SER Section
- 10.4.9 SER/SSER Impact: No Table 10.4 10 See Sheet No(s):01 >
Descriptions (Correction) Corrects the vslues for total cooling water flowrate > for the Generator Seal Oil Unit. Justification: ' The total cooling water flowrate for the Generator
- Seal.011 Unit has been increased from 66 gpm to 99 gpa and from 46 gpm to 99 gpm for the air side coolers j and H2 side coolers, respectively. These changes '
provide consistency with the manufacturer's equipment performance data. Group: 3 . FSAR Change Request Number: 89-709.1 i Related SER Section: 10 l SER/SSER Impact: No i SER does not discuss the Turbine Plant Cooling Water System which is located in FSAR Section 10.4.12. . Table 10.4-10 See Sheet No(s):02
)
Description:
(Correction) i' Corrects the value for the total. cooling water flowrate for the Service Air Compressor. - Justification: 4-f
Attachment to TXX 90011 January 15, 1990 : Page 197 of 304 r FSAR Page ; (as amended) Descrintion i i The total cooling water flowrate for the Service Air Compressor has been increased from 70 ppm to 77. gpm .i to provide consistency with the manufacturer's t equipment performance data. ; Group 3 FSAR Change Request Number: 89 709.2 j Related SER Section: 10 l SER/SSER Impact: No SER does not discuss the Turbine Plant Cooling Water System which is located in FSAR Section 10.4.12. Figure 10.4 3
Description:
(Addition) Adds vacuum breaker to Circulating Water System ' Justification: ' An air oper d ed vacuum breaker is added to the main i condenser outlet waterboxes to protect the tube side ; components from transients (such as waterhammer) in the ; event of simultaneous trip of all four Cire water pumps Groups 3 FSAR Change Request Number: 89 754.3 Related SER Section: 10.4 SER/SSER !apact: No Figure 10.4 3 See Sheet No(s):01 and 02 Description (Update) ' Minor figure updates. Justification: { No justification necessary. These figures contain ! changes of the following type !
- 1. Nanual vant or drain valves addition, removal, re- !
location, valve number
- 2. Hanways or handways !
addition, removal, or re- 1 location.
- 3. Editorial - spelling, editorial or drafting errors which cannot impact technical meaning of the diagram l
- 4. Line numbers or line sizes 1
- 5. Flanges or reducers - addition.. removal or re-location.
- 6. Piping or instrumentation physical interconnection i changes which have no impact on the operation /func-tion of system and equipment.
- 7. Manual valves - valve numbers or physical location.
changes which have no impact on the operation /func- i tion of system and equipment, j
- 8. Elevation changes. .;
Group: 4 FSAR Change Request Number: 89-732 SER/SSER Impact: No
l .. Attachment to TXX-90011 January 15. 1990 Page 198 of 304 F5AR Pepe (as amended) Descrintion Figure 10.4 4 See Sheet No(s):01 and 02
Description:
(Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 10.4 3. Group: 4 FSAR Change Request Number: 89 732 SER/SSER Impact: No Figure 10.4-5 See Sheet No(s):01 and 03
Description:
(Revision) Minor revision Justification: Reflects additional valves required to be locked in position. Groups 3 FSAR Chhnge Request Number: 89 799.1 Related SER Section: 10.4 SER/SSER Impact: No Figure 10.4 5 See Sheet No(s):01, 02 and 04 Description (Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 10.4 3. Group: 4 FSAR Change Request Number: 89-732 SER/SSER Impact: No Figure 10.4 5 See Sheet No(s):03
Description:
(Correction) Removes line 3 CW X-901-152G, which was used to supply fire protection water as an alternate source of circulating water pump bearing lubrication water. Justification:
, Fire protection water can no longer be used as the alternate lube water source due to chemical additives in the fire protection water. Water can be obtained from an alternate source through existing piping.
Group 3 FSAR Change Request Number: 89-420 Related SER Section: 10.4.5 SSER4 10.4.5 SER/SSER Impact: No Figure 10.4-5 See Sheet No(s):03 Description (Correction) Reflects the plant configuration for chemically contrciling organic fouling at the time of fuel load. Justification:
- - a
I Attachment to TXX 90013 January 15. 1990 Page 199 of 304 FSAR Page (as amended) Descrintion These changes reflect the plant configuration for chemically controlling organic fouling at the time of fuel load. Group: 4 FSAR Change Request Number: 89 598.4 Related SER Section: 10.4.5 SER/SSER !apact: No Figure 10.4 6
Description:
. (Correcti on)
Ref'lects the plant configuration for chemically controlling organic fouling at the time of fuel load. Justification:
'These changes reflect the plant configuration for chemically controlling organic fouling at the time of fuel load.
Group: 4 FSAR Change Request Number: 89 598.5 Related SER Section: 10.4.5 SER/SSER lapact: No Figure 10.4-7 See Sheet No(s):01 thru 05 Descriptions (Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 10.4-3. Group: 4 FSAR Change aequest Number: 89 732-SER/SSER Impact: No Figure 10.4 8 See Sheet No(s):01 and 03 Description (Correction) Addition of Pressure Indication Switches (P!S) to reduce main feedwater pump trips. Justification: Added additional (two) Pressure Indication Swithces on
, the condensate and turbine lubrication system to provide two'out of three logic, which reduces the main feedwater pump and main turbine trips. The reduction of trips will improve the reliability of the balance of the plant system.
Group: 3 FSAR Change Request Number: 89 736.1 Related SER Section: 10.4.7 SER/SSER Impact: No Figure 10.4-8 See Sheet No(s):01 thru 03 Description s- (Update) Minor figure updates. Justification: No justification necessary. See discussion under
Attach:Gnt to TXX-90011 January 15. 1990 Page 200 of 304 , i I FSAR Page ! (as amended) Descr1DtiOR { Figure 10.4 3. ; Group: 4 ; 4 FSAR Change Reauest Number: 89-732 ; SER/SSER 1mpact: No ; Figure 10.4 8 See Sheet No(s):1 J
Description:
(Revi s t or.) Changes position of valve 100 0196 to normally open. .l ' Justification: Changes position of valve 100-0196 to normally open to ! prevent overpressurization of piping affected by any l 1eakage of 100 0195. l Group: 3 FSAR Change Request Number: 89-798.1 Related SER Sections 10.4
- SER/SSER Impact: No f
Figure 10.4 9 See Sheet No(s) 01, 02 and 03 i Description (Correction) ! Deletion of locked closed (LC) and locked open (LO) . i notation for selected valves in figure. t Justification: - In response to an observation by INPO concerning excessive numbers of locked valves, TV Electric , reviewed requirements for locked valves and identified
- valves which were not required to be locked. Locked -
notation for these valves are being deleted. < Group: 3 t FSAR Change Request Number: 89 597 Related SER Section: 10.4.7 ; SER/SSER Impact: No l Figure 10.4-9 See Sneet No(s):02 ' Description (Revision) t Add note to the Feedwater isolation ~ valve, which indica tes that the external heaters are added to the FIV Justification:
, External heaters are required to maintain the correspo- ~
nding valve body above the low temperature brittle fracture threshold during feedwater system start-up , conditions ( see justification for section page.10.4 22) i Gr.up: 2 F3AR Change Request Number: 89-807 Related SER Section: 10.3.3 SER/SSER Impact: Yes The NRC is in process of reviewing the design as decri- ' bed in FSAR Amendment 78. , I
, ,.r _._ ,
i AttachmOnt to TXX-90011 l January 15. 1990 i Page 201 of 304 j FSAR Page ! (as. amended) Description j Figure 10.4-10 See Sheet No(s):01 !
Description:
(Addition) ! Justification: ! Adds Temperature Well and Test Connection to allow for [ the monitoring of the Steam Generator Blowdown System .t as part of the Test Data Acquisition System. l Group: 3 ! FSAR Change Request Number: 89-660.1 ! Related SER Section: 14 SER/SSER Impact: No l Figure 10.4 10 See Sheet No(s):01 Descriptions (Revision) i Adds a temperature switch to the steam generator f blowdown line. - Justification: Utilizing condensate coolant. the steam generator (SG) blowdown heat exchanger reduces the temperature of the SG blowdown from approximately 567 to 130 degrees fahrenheit. The loss of condensate supply to the heat exchanger would result in significantly increased temperatures that could potentially damage piping ' downstream of pressure-reducing throttling valve , PV 5180. The installation of the temperature switch ; would provide a means for automatically activating the necessary containment isolation / containment , isolation valves on high temperature such that the ? SG blowdown is isolated and the piping damage is prevented. ' Group: 3 l FSAR Change Request Number: 89-746 Related SER Section: 10.4.8 SER/SSER 1mpact: No > Figure 10.4 10 See Sheet No(s):01 ' l Descriptions (Revision) Minor revision ' j Justification: Reflects additional valves required to be locked in position. Group 3
- FSAR Change Request Number: 89-799.2 -
Related SER Section: 10.4 ! SER/SSER Impact: No Figure 10.4 10 See Sheet No(s):02 6 Description (Update) Minor figure updates. Justification: 4
, No justification necessary. See discussion under '
Figure 10.4 3. Group: 4 . T
- - - - - ,_. ._.....,m , , , . , . . <.,.,,_-.7 , _ . _ . .
Attachment to TXX 90011 l Jantary 15, 1990 Page 202 of 304 FSAR Page ! (as amended) Descrintion FSAR Change Request Number: 89-732 SER/SSER Impact: No Figure 10.4-11
~
See Sheet No(s):01. 02 & 03 Description (Correction) Deletes the locked closed (LC) and locked open (LO) notation for selected valves in the figure. , Justification: -l In response to an observation by INP0 concerning : excessive numbers of locked valves. TU Electric ; reviewed requirements for locked valves and identified ! valves which were not required to be-locked. . Locked . open and locked closed notation for these valves is 2 being deleted. Group: 3 FSAR Change Request Number: 89 644 Related SER Section: 10.4.9 ; SER/SSER Impact: No f Figure 10.4-11 See Sheet No(s):03 .
Description:
(Correction) , Justifications Corrects figure to properly show the vent configuration for the Condensate Storage Tank. Groups 3 ; FSAR Change Request Number: SA 90 007 : Related SER Section: 9.2.6 SER/SSER Impact: No Figure 10.4-11 See Sheet No(s):3 Descriptions (Revision) : Changes position of valve 100 0196 to normally open. Justification: Changes position of valve 100 0196 to normally open to , prevent overpressurization of piping affected by any leakage of 100 0195. Group: 3
, FSAR Change Request Number: 89 798.2 Related SER Section: 10.4 SER/SSER Impact: No Figure 10.4 13 See Sheet No(s):01 and 02
Description:
(Update) Minor. figure updates. Justification - No justification necessary. See discussion under Figure 10.4-3. t Group: 4 . FSAR Change Request Number: 89-732 SER/SSER 1mpact: No , I i
,, -w ir 9,,7. . . .
- D '-t- *' "Y *'W' "-N
-)
Attachment to TXX 90011' !
' January 15. 1990 Page 203 of 304 I
FSAR Page (as amended) Descrintion Figure 10.4 14 See Sheet No(s):01 ( Description (Clarification) : Add note to roove heater drain strainer before 100% ! power, t Justification: i Strainers are temporary, and provided to clean the sys- . l tem during post construction period, these strainers ! will be removed before 100% power of the plant. t Group: 4 i FSAR Change Request Number: 89 792 ! Related SER Section: 10.4 i j SER/SSER Impact: No l i Figure 10.4-14 See Sheet No(s):01 thru 03 l l
Description:
(Update) i Minor figure updates. Justification l No justification necessary. See discussion under l Figure 10.4-3. Group: 4 - FSAR Change Request Number: 89-732 ; SER/SSER impact: No i Figure 10.4 14 See Sheet No(s) 02 thru 05
Description:
(Revision)
- Minor revision Justification:
Reflects additional valves required to be locked in position. Groupt 3 FSAR Change Request Number: 89-799.3 f Related SER Section: 10.4 SER/SSER Impact: No i i Figure 10.4-14 See Sheet No(s):04 and 05 t
Description:
(Addition) Justification:
, Adds Temperature Well to allow for the monitoring of ,
the Heater Drain System performance as part of the Test Data Acquisition System. Group: 3 FSAR Change Request Number: 89 660.2. Related SER Section: 14 ' SER/SSER Impact: No Figure 10.4-15 See Sheet Ho(s):01 *
Description:
(Correction) Corrects the plant cooling water pump seni leakoff piping details. Justification: The plant turbine cooling water pump seal leakoff , piping was added to provide an appropriate pathway
Attache:nt to TXX 90011 January 15. 1990 Page 204 of 304 l FSAR Page j (as amended) Descrinti on l for the seal leekoff to the equipment drains. The ! figure has been revised coraistent with the as built l
- plant condition. !
Group: 3 l FSAR Change Request Number: 89-758 i l Related SER Section: 10.4 ; SER/SSER Impact: No Figure 10.4-15 See Sheet No(s):01 and 02 l Descriptions (Update) Ninor figure updates. [
~
Justification:
, No justification necessary. See discussion under ;
Figure 10.4-3. -! Group: 4 i FSAR Change Request Number: 89 732 i SER/SSER 1mpact: No Figure 10.4 15 See Sheet No(s):03 i
Description:
(Correction) The relief valves shown in the Figure were not installed in the field. Justification: The Figure is being revised to reflect the as built l conditions, i Group: 4 r FSAR Change Request Number: 89 423 SER/SSER Impact: No t Figure 10.4-16 See Sheet No(s):01 thru 05
Description:
(Update) - Ninor figure updates. Justification: ' No justification necessary. See discussion under ! Figure 10.4 3.
- Group: 4 j FSAR Change Request Number: 89 732. '
i f SER/SSER Impact: No Figure 10.4-17 See Sheet No(s):01 thru 04 e i
Description:
(Update) Hinor figure updates. Justification: No justification necessary. See discussion under-Figure 10.4-3. Group: 4 ; FSAR Change Request Number: 89 732 SER/SSER Impact: No " I l _
Attachment to TXX 90011 , January 15. 1990 ! Page 205 of 304 .i l
.FSAR Page l (as amended) Descrintion ,
i Figure 10.4 17 See Sheet No(s):02 ;
Description:
(Currection) Modifies Turbine Oil Purification and Demineralized ' Water System to eliminate the presence of l Microbiological 1y Induced Corrosion (MIC) bacteria. , Justification: The Turbine 011 Purification and Demineralized Water ! System was modified to eliminate the presence of MIC ' bacteria found to be present in low flow. high moisture , regions of the mechnical filtration purification - (Bowser) unit.. Therefore to eliminate the presence of MIC bacteria, two centrifuge units have been installed , as a temporary modification. The inherent design of ; these units minimizes low flow and stagnant regions. , within the lube oil purification. cycle, , Group 4 j FSAR Charge Request Number: 89-766.3 , i SER/SSER Impact: No ; Figure 10.4 17 See Sheet No(s):03
Description:
(Correction) l Addition of Pressure Indication Switches (PIS) to reduce main feedwater pump trips. !- Justification: Added edditional (two) Pressure Indication Switches on ; the condensate and turbine lubrication system to i provide two out of three logic which reduces the main ; l feedwater pump and main turbine trips. The reduction of trips will improve the reliability of the balance of the plant system. l Group 3 l FSAR Change Request Number: 89 736.2 ; l Related SER Section: 10.4.7 . l SER/SSER Impact: No Figure 10.4 18 See Sheet No(s):01 and 02
Description:
(Update)
, Minor figure updates.
Justification: No justification necessary. See discussion under Figure 10.4-3. Group: 4 FSAR Change Request Number: 89-732 ' SER/SSER Impact: No Figure 10.4 18 See Sheet No(s):01 and 02 Descript1on:-(Revision) Minor revision Justification: ' Reflects additional valves required to be locked in position. Group: 3
Attachment to TXX 90011 January 1bo 1990 Page 206 of 304 FSAR Page las amended) Descrintion FSAR Change Request Number: 89 799.4 Related SER Section: 10.4 SER/SSER Impact: No Figure 10.4-19
Description:
(Update) Minor figure updates. Justification: No justification necessary. See discussion under Figure 10.4 3. Group: 4 FSAR Change Request Number: 89 732 SER/SSER Impact: No Figure 10.4-19
Description:
(Revision) Minor revision Justification: Reflects additional valves required to be locked in position. Group: 3 FSAR Change Request Number: 89 799.5 Related SER Section: 10.4 SER/SSER !spect: No Figure 10.4 20 See Sheet No(s):01, 03 and 04
Description:
(Update) Minor figure updates. Justification: No justification necessary, See discussion under Figure 10.4-3. Group 4 FSAR Change Request Number: 89 732 i SER/SSER Impact: No Figure IJ.4 20 See Sheet No(s):02 t
Description:
(Revision) Adds check valve / existing line configuration, corrects tag numbers, and changes gate valve to globe valve for the secondary sampling system. Justification: Revises figure to be consistent with the as built conditions. This justification was inadvertently omitted from FSAR Amendment 76 and is being provided now to support the revised Figure 10.4-20 (Sh. 2) which was submitted in FSAR Amendment 76. Group: 3 FSAR Change Request Number: 88 001 Related SER Section: 10.4.2 SER/SSER Impact: No
n , Attachment to TXX 90011 3 January 15, 1990 , Pace 207 of 304 l l rsiR e... ini_ amended) Descrintion ; l ! Table 11.2 5 See Sheet No(s):01, 05 & 06 j-
Description:
(Correction) I l Revises portions of Table 11.2 5 dealing with the following Liquid Weste Processing System instrumen-i tation: F1-1008. LI-1001. LI-1010. LI 1012. LI-1077A. > LI 10778. LI 1082 and LI 1083. ! l Justification: , The Alarm and Control Setpoint information previously-l 'in the table did not agree with setpoints established by Westinghouse or through design changes resulting from system testing. l l Group: 3 r FSAR Change Request Number: 89 749.1 Related SER Section: 11.2.1 SER/SSER Impact: No - Table 11.2-5 See Sheet No(s):07 o Description (Correction) i , Modifies sh. 7 of Table 11.2 5 by deleting radiation i instruments RE 5251 & RE 5252. Justifications i This change reflects the current design of the Liquid ; Weste Processing System wherein processed liquid rad- ' waste will no longer be recycled to the condensate , storage and laundry tanks, thus eliminating the nef.d for these two process radiation sonitors. -(Information ! regarding this waste processing change was identified , previously in Amendment 77; see changes in Chapter 11.5.) Groep: 'l l FSAR Change hquest Number: 89 749.2 Reinted SIR Section: 11.3 l SER/SLE3 Inipact. Yes Table 11.6 of the SER shculd be revised las indicated ! in the description of changes to Chapter 11.5 for l Anmdmont 77) to reflect the deletion of the monitors on tha laundry end hot shower recycle stream,and an the weste moMtor tank input recycle stream. . ; i Figure 11.2 2
Description:
4 Correction) Liquid Weste Processing Flow Diagram Reactor Coohnt Orain Tank Subsystem Delete "LO" from vaive #1 Woc 0234
- j. Justification:
L in response to an observation by INPO concerning excessive numbers of locked valvez, Til Electric reviewed requirements for locked valvet end identified valves which were not required to be lochd. ,
"LC", "LO". and " LIP" notations for these velves are being deleted. In some cases locked vilve requirements are being added. "LC-2" notation is being added to denote those valves-which serve as a boundary for Unit 1 during Unit 2. construction.
1
.w.- , .- ~ - --
l .? Attache:nt to TXX 90011 January 15. 1.190 t Page 208 of 304 - FSAR Page ! (as.amanded) Descrintion j Group: 3 l FSAR Change Request Number: 89 613.01 : Related SER Section: 11.2.1 l SER/SSER Impact: No i Figure 11.2-3 See Sheet No(s).01 ! Description (Correction) l Flow Diagram Liquid Weste Processing " Drain Channel A"- ! Adds "LC" to Valve #7251. t Justification: ! Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2-2. Group: 3 ; FSAR Change Request Number: 89 613.02 i Related SER Section: 11.2.1 ', SER/SSER Impact: No . Figure 11.2 3 See Sheet No(s):01 ,
Description:
(Correction) l Flow Diagram Liquid Weste Processing " Drain Channel A"- l Changes "LC" to " LIP" to Valve #XWP 7250, t Justifications Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2-2. Group: 3 FSAR Change Request Number: 89-613.03 > Related SER Section: 11.2.1 ' SER/SSER Impact: No i l Figure 11.2-3 See Sheet No(s):01 i Descriptions (Correction) Flow Diagram Liquid Waste Processing " Drain Channel A"- Adds "LC-2" to Valve #XWP 0193. i Justification: F Reflects valve locking conditions as identified in the l justification for the changes to Figure 11.2-2. Group: 3
, FSAR Change Request Number: 89-613.04 Related SER Section: 11.2.1 SER/SSER Impact: No Figure 11.2-3 See Sheet No(s):01
Description:
(Correction) Adds heat tracing. Justification: Heat tracing is added to provide freeze protection for Liquid Watte Processing System lines which contain concentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal to 65 degrees (fahrenheit) and ensure the operability of that portion of the system.
' Group: 3-
I Attachment to TXX-90011 l January 15, 1990 I Page 209 of 304 i FSAR Page 1 (as amended) Descr1DtiAR i FSAR Change Request Number: 89 689.7 Related SER Section: 11.2.1 ! ., SER/SSER Impact: No l Figure 11.2 3 See Sheet No(s):02 )
Description:
(Correction) Adds heat tracing, i 1 Justification: Heat tracing is added to provide freeze protection for 1 Liquid Waste Processing System line: which contain i concentrated boric acid solution (4% boric acid) to~ ] maintain the solution at greater than or equal to 65 i degrees (fahrenheit) and ensure the operability of that portion of the system. Group 3 ; FSAR Change Request Number: 89 689.8 l Related SER Section: 11.2.1 SER/SSER Impact: No Figure 11.2-4 See Sheet No(s):01 I
Description:
(Correction) i Flow Diagram Liquid Haste Processing " Drain Channel B"- 3 Adds "LC 2" to Valve #XWP 7448 and Valve #XWP-0160. l Justification: ' Reflects valve locking conditions as identified in the 1 justification for the changes to Figure 11.2 2. l
, Group: 3 i i FSAR Change Request Number: 89-613.05 '
Related SER Section: 11.2.1 j SER/SSER Impact: No-Figure 11.2-4 See Sheet No(s):01
Description:
(Correction) J Flow Diagram Liquid Waste Processing " Drain Channel' B"- , Adds " LIP" to Valve #XWP 0033. i Justification: Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2-2. Groups 3 FSAR Change Request Number: 89 613.06 ' Related SER Section: 11.2.1 SER/SSER Impact: No l Figure 11.2-4 See Sheet No(s):02
Description:
(Correction) Flow Diagram Liquid Waste Processing "Prain Channel B"-- l Deletes "LC" from Valve #XGH 0001. Justification: Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2-2. ! Group: 3 FSAR Change Request Number: 89 613.07'
I Attachment to TXX 90011 January 15, 1990 i Page 210 of 304 FSAR Page (as amended) Descristien Related SER Section: 11.2.1 SER/SSER Impact: No ; See Sheet No(s):02 Figure 11.2-4
Description:
(Correction) i Adds beat tracing. ! Justification: Heat tracing is added to provide freeze protection for Liquid Weste Processing System lines which contain concentrated boric acid colution (4% boric acid) to
- maintain the solution at greater than or equal to 65 degrees (fahrenheit) and ensure the operability of that >
portion of the system. + Group: 3 i FSAR Change Request Number: 89-689.9 i Related SER Section: 11.2.1 SER/SSER Impact: No l Figure 11.2 4 See Sheet No(s):03
Description:
(Correction) ! Adds heat tracing. Justification: Heat tracing is added to provide freeze protection for - Liquid Weste Processing System lines which contain concentrated boric acid solution (4% boric acid) to maintain the solution at greater than or equal to 65
- degrees (fahrenheit) and ensure the operability of that portion of the system.
Group 3 FSAR Change Request Number: 89 689.10 Related SER Section: 11.2.1 SER/SSER Impact: No , Figure 11.2-5
Description:
(Correction) Flew Diagram Liquid Waste Processing Drain Channel "C"- Adds " LIP" to Valve (XWP-0226 and Valve #XWP 7402. Justification:
,- Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2-2. ,
Group: 3 ' FSAR Change Request Number: 89 613.08 Related SER Section: 11.2.1 SER/SSER !apact: No + Figure 11.2-6 Description (Update) Ninor figure updates. Justification: No justification necessary. These figures contain changes of the following type:
- 1. Manual vent or drain valves - addition, removal, re-location, valve number,
- 2. Nanways or handways - addition, removal, or re-
-- - -~ _ . _ _ . . . - -- ,.m_ ., y._,. . . . - . _ y . , .... , - -. .. .. -
Attachment to TXX 90011 ! January 15, 1990 Page 211 of 304 l
'l
)
FSAR Page l (as amended) Des crintion : location. l
- 3. Editorial - spelling, editorial or draf ting errors i which cannot impact technical meaning of the diagram ;
- 4. Line numbers or line sizes, j S. Flanges or reducers - addition, removal or re- l location.
- 6. Piping or instrumentation - physical interconnection '
changes which have no impact on the operation /func-tion of system and equipment.
- 7. Manual valves valve numbers or physical location ,
changes which have no impact on the operation /func-tion of system and eqJipment.
- 8. Elevation changes. 3 Group: 4 -
FSAR Change Request Number: 89-732 SER/SSER Impact: No ; Figure 11.2-7 Descriptions (Correction) l Flow Diagram Liquid Weste Processing Disposal Subsystem
- Adds "LC 2" to Valve #XWP 0174.
Justification: Reflects valve locking conditions as identifistd in the justification for the changes to Figure 11.2 2. Group: 3 ; FSAR Change Request Number: 89 613.09 Related SER Section: 11.2.1 i SER/SSER Impact: No Figure 11.2 8
Description:
(Correction) ' Tag numbers are incorporated into Figure 11.2 8. XWP 7483 near to 2 WP X-587-151R S CPX WPTNCA-01 to Chemical Addition Tank: Agitator CPX WPBLCT-01 near I Weste Conditioning Tanks and CPX WPFNVB 01 to Mixer l Feeder Vapor Blower. Justification: l The subject tag numbers were inadvertently omitted from. ; the figure. '
, Group: 4 FSAR Change Request Number: 88 922 '
Related SER Section: 11.3 SER/SSER Impact: No Figure 11.2-8 Description (Correction) Liquid Radwaste Management System Flow Diagram Liquid. # Waste Processing Disposal Subsytem - Replace existing Chemical Drain Tank valve. Justification: The existing Chemical Drain Tank valve has a very small port and clogs when the CDT is drained. The existing , valve will be replaced with a diaphragm type valve with a larger port diameter. The valve will be supplied ' with "0" rings in the bonnet and handwheel-to prevent L
----m - . _ _ _ _ _ _ _ _ . _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ . _
l Attach;ent to TXX-90011 January 15. 1990 Page 212 Jf 304 i i ' I FSAR Page , i (as. amended) Deserintion I chemical leaks. This modification will not adversely impact the original design basis of the system. Group: 3 FSAR Change Request Number: 89 785 l Related SER Section: 11.2.1 , SER/SSER Impact: No > l ' Figure 11.3 1 See Sheet No(s):01 thru 05 '
Description:
(Correction) . ! Gaseous Waste Management Flow Diagram Gaseous Waste Processing System - Revise Figure 11.3 1 . i Justification: : Revise Figure 11.3-1 tc reflect the "as-built" and ! normal operating conditions for the gaseous waste ; processing system. Many valve postions were erroneously designated in the opposite position. The correct , positions of the valves were reflected in the Westinghouse Operating Manual but were never transposed , to the flow diagram. Group: 3 ! l FSAR Change Request Number: 89-774.1 . Related SER Section: 11.2.2 ! SER/SSER Impact: No Figure 11.3-1 See Sheet No(s):01. 05 and 06
Description:
(Update) Minor figure updates. Justification: See justification for changes to Figure 11.2 6, Group: 4 , FSAR Change Request Number: 89-732 SER/SSER Impact: No Figure 11.3-1 See Sheet No(s):02 Description (Correction) Flow Diagram Waste Processing System (Gas) - Deletes l
"LC" from Valve #XGH-0036. ,
l Justification: t Reflects valve locking conditions as identified in the , justification for the changes to Figure 11.2 2. Group: 3 FSAR Change Request Number: 89 613.10 Related SER Section: 11.2.2 SER/SSER Impact: No Figure 11.3-1 See Sheet No(s):02 and 03
Description:
(Correction) i Gaseous Waste Management - Flow Diagram Gaseous Waste Processing System - Revise Figure 11.3-1 Justification: Revise Figure 11.3-1 to reflect the "as built" and t normal operating conditions for the gaseous waste 4 I
. ._. - - - - - - . =. -- - _ - . - .
I Attache;nt to TXX-90011 January 15. 1990 Page 213 of 304 I l FSAR Page ! (as amended) Descrintion , processing system. The nitrogen purge lines to the gas , analyzer racks were added because the analyzer panels i require nitrogen purge to prevent moisture build up in j the cells. These changes were added to the l Westinghouse Operating Manual via DCA 16612, but were ; never reflected on the flow diagram. ; Group 3 i FSAR Change Request Number: 89 774.2 , Related SER Section: 11.2.2 ; SER/SSER Impact: No i e Figure 11.3 1 See Sheet No(s):03 Descriptions (Correction) ' Flow Diagram Waste Processing System (Gas) - Deletes i "LC" from Valve #XGH 0037. Justification: Reflects valve locking conditions as identified in the ; justification for the changes to Figure 11.2 2. Group: 3 FSAR Change Request Number: 89 613.11 Related SER Section: 11.2.2 ; SER/SSER Impact: No i Figure 11.3-1 See Sheet No(s) 04 - Description (correction)
- - Flow Diagras Weste Processing System (Gas) - Changes "LC" to "LC-2" on Valve #2GH-7894.
Justification: j Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2-2. Groups 3 FSAR Change Request Number: 89 613.12 I i Related SER Section: 11.2.2 :
- l. SER/SSER Impact: No 1
, Figure 11.3-1 See Sheet No(s):04
)
Description:
(Correction)
, , Flow Diagram Weste Processing System (Gas) - Deletes "LC" from Valve #2GH 7935 and Valve #XGH-0023. ,
Justification:
- 3 Reflects valve locking conditions as identified in the justification for the changes to Figure 11.2 2.
Group: 3 FSAR Change Request Number: 89 613.13 - Related SER Section: 11.2.2 i SER/SSER Impact: No j 11A-1
Description:
(Correction) 6 Modifies the first paragraph of the text in Section 11A.1, " Critical Pathways" by deleting reference to ' exposure from accidents. Justification:
1
-Attachment to TXX-90011 i January 15. 1990 ;
Page 214 of 304 ; i i FSAR Page 1 (as amended) Descrintion I This change is made to reflect the requirements of ; Appendix I to 10 CFR 50, which only includes ,
... effluents produced during normal reactor operations ;
including erpected operational occurrences." ; Group: 3 , FSAR Change Request Number: 88 652.01 , Related SER Section: 11.2.2.5
- SER/SSER Impact: No '
11A-1
Description:
(Clarification) Modifies the third paragraph of the text in Section , 11A.1, " Critical Pathways," by indicating that..even I though the ingestion of crops actually cultivated on : irrigated land is not considered a significant pathway, the exposure was conservatively included in the cales. . Justification: This change is made to reflect the calculations that , were performed and is also intended to demonstrate the maximum potential dose impact. Group: 4 FSAR Change Request Number: 88 652.02 l Related SER Section: 11.2.1.3 SER/SSER Impact: No , 11A 2 See Page No(s): Table 11A 2, sh. 2-
Description:
(Addition) Modifies the discussion of the results of a reenalysis of the liquid pathway doses by indicating that the crop irrigation pathway is minor unless Squaw Creek Reservoir water was to be used for irrigation. Justification: This change is made to reflect the results of the reenalysis of the exposure from the different pathways, ' Group 3 FSAR Change Request Number: 88 652.03 Related SER Section: 11.2.1.3- e SER/SSER Impact: No . 11A-2 ' See Page No(s): Tables 11A-3 & 11A-6 Description (Revision) Modifies the discussion of the results of the gaseous ; i pathway dose calculations to indicate that the cow milk ' i pathway yields the maximum organ dose to the thyroid .' gland of an infant. Justification: This change is made to reflect the results of the ' reanalyis of the gaseous exposure pathways for the . purpose of demonstrating conformance to 10CFR50, Appendix I. Group: 3 FSAR Change Request Number: 88 652.04 Related SER Section: 11.2.2.5 s -- - - e , , , , , , , - - a -,-< a -e.. ..- c. ..- ~ ...v.m,.
- Attachment to TXX 90011 !
January 15, 1990 > Page 215 of 304 l
- i FSAR Page l (as amended) Description !
l SER/SSER Impact: No , 11A-5
Description:
(Clarification) l Adds the constraint on the term Csub0 when fresh makeup ' water is used. Justification: , 1 This change is made to incorporate a term which was inadvertently omitted during the processing of Amend- ! ment 10. Group: 4 ! FSAR Change Request Number: 88 652.05 t Related SER Section: 11.2.1.3 I
- SER/SSER Impact
- No i 11A-5 Descriptions (Editorial) s Nodifies the equation for OsubBo.
Justification: ' i This change is made to correct an oversight made during ! the processing of Amendment 10 wherein the mathematical ; definition inadvertently omitted.the term "qsubs": the ! correct expression already appears on page 11A 4. ' Group: 4 FSAR Change Request Number: 88 652.06 Related SER Section: 11.2.1.3 . SER/SSER Impact: No lt 11A 5
Description:
(Correction) Adjusts the value for the annual average flow rate in the Brazos River downstream from Lake Granbury, i.e., OsubB. Justification: 1 This change is made to reflect the value used in the , reanalysis of the liquid pathway doses. ' Group: 4 FSAR Change Request Number: 88 652.07 Related SER Section: 11.2.1.3 SER/SSER Impact: No 11A-6
Description:
(Correction) Nodifies that portion of the text in Section 11A 3,
" Estimated Doses from Liquid Effluents." which '
describes the pathways used in calculating doses to individuals in order to assess compliance with Appendix
! to 10CFR50.
Justification: l
- This change is made to reflect the dose pathways used i
in the reenalysis of compliance with Appendix Is the pathways are consistent with those required (and as applicable) in Regulatory Guide 1.109. Group: 3 FSAR Change Request Number: 88 652.08-- Related SER Section: 11.2.1.3
. - - - , , - , , n,
Attachment to TXX-90011 January 15. 1990 Page 216 of 304 FSAR Page (as assended) Descrintion SER/SSER Impact: No 11A-6 Descriptions (Correction) Changes the assumption regarding the time that would elapse between withdrawal of water from each source and uptake. Justification: This change is made to conform to the minimum transit time identified in Regulatory Guide 1.109 for the potable water pathway (see Appendix A. item 2a and Table E IS. item tsubp). Group 3 FSAR Change Request NL'abtt" 88-6S2.10 Related SER Section: 11.E.1.3 SER/SSER !apact: No 11A 6. 8 See Page No(s):13 Description (Clarification) Modifies that portion of the text in Sections 11A.3 and 11A.4 discussing the estimated doses from liquid and gaseous effluents which identifies the particular computational method used to obtain these pathway doses. Justification: This change is made to reflect the fact that the rean-alysis was performed using the computational techniques and certain input data from Reg. Guide 1.109, except for the value to represent the midpoint of plant life, which is taken from the LADTAP !! computer code users manual (Reference (9]). . Group: 4 FSAR Change Request Number: 88 652.09 Related SER Section: 11.2.1.3 SER/SSER lapact: No 11A-7 Description (Correction) Deletes use of a 24 hour decay period in the f calculation of the exposure from recreational activities. Justification: This change is made to reflect the dose model used in the reanalysis of this exposure pathway; Regulatory Guide 1.109 does not provide for such a decay allowance in the assessment of the dose from this pathway. Group: 3 FSAR Change Request Number: 88-652.14 Related SER Section: 11.2.1.3 SER/SSER Impact: No
Attachm0nt to TXX-90011 January 15. 1990 Page 217 of 304 FSAR Page (as amended) Descrintion 11A-7 See Page No(s): Tables 11A 2 (sh 2 & 3) & 11A 5 Descriptions (Revision) Modifies the maximum predicted total single organ (the skin) and total body doses from recreational activity at Squaw Creek Reservoir. Justification: This change is made to reflect the results of the reanalysis of the exposure from this pathway. This change has been evaluated under the TV Electric 50.59 process as discussed in TXX 89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 88 652.15 Related SER Section: 11.2.1.3 SER/SSER Impact: No 11A 7 See Page No(s) Tables 11A 2 (sh 2) & 11A 5 Description (Correction) Modifies the description of the ingestion pathway (i.e. changes " fish" to " aquatic food"). Justification: This change is made to be consistent with the terminology and the scope of the ingestion pathway as defined in Regulatory Guide 1.109. Groups 3 FSAR Change Request Number: 88 652.12 Related SER Section: 11.2.1.3 SER/SSER !apact: No 11A 7 See Page No(s) Tables 11A 2 (sh 2) & 11A 5
Description:
(Revision) Modifies the maximum calculated doset from the aquatic food ingestion pathway. Justification: This change is made to reflect the results of the reentlysis of the liquid pathway doses. This change has been evaluated under the TU Electric 50.59 process as discussed in TXX-89718 dated 9/28/89.
, Group: 2 FSAR Change Request Number: 88 652.13 Related SER Section: 11.2.1.3 SER/SSER Impact: No 11A 8
Description:
(Correction) Deletes reference to use of the GASPAR computer code-for obtaining the doses from pathways involving gaseous effluents. Justification: This change is made to reflect the fact that the reanalysis was based directly on the calculational techniques defined in Regulatory Guide 1.109. Group: 3 FSAR Change Request Number: 88 652.18
b l Attach =nt to TXX 90011 ; January 15. 1990 Page 218 of 304 FSAR Page j (as _amettded) Descrintion l Related SER Section: 11.2.2.5 j SER/SSER 1mpact: No 1 1 11A 8
Description:
(Correction) f Adds an additional exception taken to the use of data ' , defined in Regulatory Guide 1.109. Justification: I This change is made to reflect the fact that a more I conservative value was chosen to specify the midpoint l of plant life (i.e. 20 years vs. the 15 year value ! cited for the term 't sub b* in Equation C 1 of Appendix C to Regulatory Guide 1.109). Group: 3 FSAR Change Request Number: 88 652.19 Related SER Section: 11.2.2.5 i SER/SSER Impact: No
]
11A 8 See Page No(s): Tables 11A-2 (sh 3). 11A 3 & 11A 5 l
Description:
(Revision) Modifies the maximum doses expected from the contami- .) nated food pathway based on consumption of vegetation i that was irrigated with contaminated water. l Justification: I This change is made to reflect the results of the reanalysis of the exposure from this pathway. This i change has been evaluated under the TU Electric 50.59 ? process as discussed in TXX 89718 dated 9/28/89. ; Group: 2 FSAR Change Request Number: 88-652.17 Related SER Section: 11.2.1.3 SER/SSER 1mpact: No ) j 11A 9 See Page No(s): Table 11A 3 (sh 1) l Descriptions (Revision) ' Hodifies the maximum doses estimated to an individual from submersion in a cloud of radioactive noble gas effluents. Justification: These changes are made to reflect the results of I reanalysis of the total body and skin exposure from l this pathway. This change has been evaluated under the 1 TV Electric 50.59 process as discussed in TXX 89718' I dated 9/28/89. 1 Group: 2 . 1 FSAR Change Request Number: 88-652.20 ) Related SER Section: 11.2.2.5 SER/SSER Impact: No l
Attachmant to TXX 90011 January 15, 1990 Page 219 of 304 FSAR Page (as amended) Descrintion 11 A 9 See Page No(s): Table 11A-3 (sh 1) Descriptions (Revision) Modifies the doses calculated to an individual as a. result of irradiation from activity deposited on ground surfaces. Justification: These changes are made tn reflect the results of rean-alysis of the total body and skin exposure from this pathway. This change has been evaluated under the TV Electric 50.59 process as discussed in TXX 89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 88 652.21 Related SER Section: 11.2.2.5 SER/SSER Impact: No 11A 10 See Page No(s): Table 11A 3 (sh 1) Descriptions (Revision) Modifies the maximum individual doses calculated from the exposure pathway involving vegetable consumption. Justification: These changes are made to reflect the results of rean-alysis of the organ and whole body doses as a result of this exposure pathway. This change has been evaluated under the TU Electric 50.59 process as discussed in TXX-89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 88 652.23 Related SER Section: 11.2.2.5 SER/SSER Impact: No 11A 10, 11 See Page No(s) Table 11A 6 (sh 1 & 3) Descriptions (Correction) Modifies the text in two places that identify the major isotopic contributor to the organ and total body doses from those exposure pathways involving vegetable con-sumption and cow milk ingestion.
, Justification:
These changes are made to reflect the'results of reanalysis of this exposure pathway. Group: 3 FSAR Change Request Number: 88 652.24 Related SER Section: 11.2.2.5 SER/SSER Impact: No 11A 10, 11 See Page No(s): Tables 11A 3 & 11A 6 Description -(Revision) Modifies the maximum organ and total body doses calculated from the cow milk exposure pathway. Justification: These changes are made to reflect the results of reanalysis of this exposure pathway. This change has
l-Attachment to TXX 90011 January 15, 1990 Page 220 of 304 l t FSAR Page 135 amended) Descrintion i been evaluated under the TV Electric 50.59 process as [ ! discussed in TXX 89718 dated 9/28/89. ' Group: 2 FSAR Change Request Number: 88 652.25 ; Related SER Section: 11.2.2.5 SER/SSER 1mpact: No : l ; l 11A 10 See Page No(s): Tables 11A 3 (sh 1). 11A 6 (sh 2. 3)
Description:
(Revision) : l Modifies the maximum individual doses calculated as a i result of the air inhalation pathway. ; Justification: l These changes are made to reflect the results of ; reenalysis of the organ doses received as a result of ' this exposure pathways the calculations also resulted ; in a change of the critical individual (i.e., from adult to teen). This change has been evaluated under : the TU Electric 50.59 process as discussed in TXX 89718 > dated 9/28/89. ! Group: 2 ; FSAR Change Request Number: 88-652.22 Related SER Section: 11.2.2.5 r
- SER/SSER Impact
- No '
l 4 11A 11 See Page No(s): Table 11A 3 (sh 2) l Descriptions (Revision) ' Modifies the maximum organ and total body doses calculated from the goat milk exposure pathway. Justification: These changes are madt to reflect the results of reanalysis of this exposure pathway. This change h6s been evaluated under the TV Electric 50.59 process as discussed in TXX-89718 dated 9/28/89. Group: 2
- FSAR Change Request Number:- 88-652.26 Related SER Section: 11.2.2.5 SER/SSER lupact ho 11A 11 See Page No(s): Table 11A 3 (sh 2)
Description:
(Revision) Modifies the. maximum organ and total body doses calcu-lated from the meat ingestion pathway and changes the . critical organ. Justification: . These changes are made to reflect the results of reanalysis of this exposure pathway. This change has been evaluated under the TV Electric 50.59 process as discussed in TXX-89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 88 652.27 Related SER Section: 11.2.2.5 SER/SSER Impact: No L 1,
Attachment to TXX 90011 ! January 15. 1990 l Page 221 of 304- l l 1 FSAR Pepe ; (as amended) Descripting i 11A 13 See Page No(s):6 & 8 :
Description:
(Clarification) ; , Adds a reference also used to obtain input data for , calculating the estimated doses from liquid and gaseous . effluents. (The reference previously.had be2n men- f tioned in the text but no citation was provided.) i Justification: . See justification for the changes identified on pages ; 11A 6, 8. ; Group: 4 FSAR Change Request Number: 88 652.09 Related SER Section: 11.2.1.3 SER/SSER Impact: No i 11A 6, 7 See Page No(s): Tables 11A 2 (sh 1) & 11A 5 [ Descriptions (Revision) , Modifies the maximum calculated doses from the drinking water pathway. ; Justification: This change is made to reflect the results of the i reanalysis of the liquid pathway doses. ,I Group: 3 FSAR Change Request Number: 88-652.11 . Related SER Section: 11.2.1.3 ' SER/SSER Impact: No l ' 11A-7, 8 See Page No(s): Tables 11A 2 (sh 3) & 11A 5 , Descriptions (Revision) Modifies the descriptions of the assumptions used in l calculating the doses from the contaminated food pathway, and includes using all three water sources. Justification , This change is made to reflect the fact that the assumptions used in the reenalysis of this exposure pathway are in accord with those contained in para-graph 2d of Appendix A to Reg. Guide 1.109. Groups 3 , FSAR Change Request Number: 88 652.16 l Related SER Section: 11.2.1.3 ' SER/SSER Impact: No , Table 11A 1 See Sheet No(s):01 & 02 -i l
Description:
(Revision) > Completely revises the isotopic data listed in this table and indicates that the new values represent the annual releases from both reactors (rather than being . on a per reactor basis). Justification: This change is made to reflect the expected long term isotopic concentrations in each of the three bodies of water that could potentially receive plant discharges.
=i .- _. .,. . . ~ . . - _ . . _ _ . _ . . . _ _ . . . . . - . _ . - . _ , . _ . __ __ -.-
Attachment to TXX 90011 y January 15. 1990 Page 222 of 304 FSAR Page (as amended) bacription as obtained in the reanalysis to establish compliance with Appendix 1. (The new values are approximately twice the previous entries, due to the fact that the releases were revised to represent both units.) Group: 3-FSAR Change Request Number: 88 652.28 Related SER Section: 11.2.1.3 SER/SSER Impact: No Table 11A-2 See Sheet No(s):01, 02 & 03
Description:
(Revision) Modifies this table by incorporating revised organ and total body doses that resulted from reanalysis of the liquid pathway exposures revises the critical organ as appropriates adds the infant dose from the_ crop irri-gation pathways and includes Squaw Creek Reservoir. Justification: These changes reflect the results of the reenalysis of various liquid exposure pathways to assess compliance with Appendix 1. This change has been evaluated under the TU Electric 50.59 process as discussed in TXX 89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 88 652.29 Related SER Section: 11.2.1.3 SER/SSER Impact: No Table 11A-3 See Sheet No(s):01 & 02
Description:
(Revision) Modifies this table by incorporating revised organ and total body doses, and revises the critical organ as appropriate. Justification: These changes reflect the results of the reanalysis of-various gaseous exposure pathways to assess _ compliance-with Appendix 1. This change has been evaluated under the TV Electric 50.59 process as discussed in TXX 89718
, dated 9/28/89.
Group: 2 FSAR Change Request Number: 88 652.30 Related SER Section: 11.2.2.5 SER/SSER Impact: No Table 11A 3, sh 01 See Sheet No(s): Table 11A 6 (sh 1) Descriptions (Correction) Revises the distance to the point of dose evaluation-for the gaseous effluent calculations. Justification: These changes are made to be consistent with the distance specified in Section 11A.4 which is the value 4 that was actually used in the calculations. Group: 3 1 i seso,
. - -.. ~. . . .- . _ . .. - -- . .-. --
i Attachtsnt to TXX 90011 l January 15,'1990 i
- Page 223 of 304 FSAR Page I.Ls__gmended ) Descrintion 1
FSAR Change Request Number: 88-652.35 Related SER Section: 11.2.1.3 SER/ W 1 Impact: No l Table 11A-4 Det
- 2t1Jn: (Addition). . )
~ Mjitms this table by. adding the pertinent _ data for -
~
i 1 C-14 and Ar-41; ! Justification: These changes are'made to include the annual-releases- i and expected exclusion area boundary concentrations for l' two isotopes that were not included in the earlier analysis. (Their annual release l rates wereitaken from; , NUREG-17, Rev.-.0.) Group: 3 -i FSAR Change Request Number:- 88 652.31- ,; Related SER Section: 11.2.2.5
- SER/SSER Impact: No
- Table 11A-5
Description:
.(Revision) 4 Modifies this table by revising the calculated liquid' effluent doses, the points of dose evaluation.-the
- .identifi. cation. of both _the. critical organ and the indi-vidual with the reported organ dose, and indicates that the total body' dose includes the irrigation: pathway.
Justification: These changes are made to reflect the increasediscope and results of the reanalysis to assess compliance.with Appendix 1. l Group: 3 FSAR Change Request Number: 88-652.32 Related SER Section: 11. 2.1. 3 ':
- SER/SSr ' 15 pact
- - No i
l Table 11A-6 See o<et No(s):01 and 03 i Descriptions (Revision)- Modifies this table by revising the calculated doses i from gaseous effluents. Justification: These- changes are made'te r eflect: the res'ults of thi reanalysis to assess compliance with Appendix 1. This I change has been evaluated under the TV Electric 50.59 1 process as discussed in TXX-89718' dated 9/28/89. ] 1 Group: 2 FSAR Change Request Number: 86-652.33 Related SER Section: 11.2.2.5 : { SER/SSER-Impact: No I l Table 11A-6 See Sheet No(s):02 and 03
Description:
(Revision) iiodifies this table by. revising the calculated dose to' l any organ from.all pathways by considering:radioiodines j and particulates released to the atmosphere:. revises-1 l 1 ) d
Attach;snt : 'to TXX-90011 January 15. 1990 Page 224 of 304' l l l FSAR Page 1 (as amended) Description l the critical organ and the individual with the reported L organ dose; and revises the point of dose evaluation. l Justification: 1 These- changes are made to respond to the requirement in ' l Appendix I to calculate the dose contribution from l radiciodines and particulates with half lives greater
- than 8 days. This. change has been evaluated under the l TV Electric 50.59 process as described in TXX-89718 1
dated 9/28/89. Group: 2 FSAR Change Request' Number: 88-652.34 Related SER Sections.11.2.2.5 SER/SSER Impact: No Table 11A-6 See Sheet No(s):03
Description:
(Addition) Adds C 14.to Note 5. Justification: This change is made to reflect the increased. scope and I results of the reanalysis to assess compliance with Appendix I. Group: 3-FSAR' Change Request Number: 88-652.38 Related SER Section: 11.2.2.5 SER/SSER Impact: No i a Table 11A-6 See Sheet No(s):03
Description:
(Revision) Changes the critical organ from " infant thyroid" to
" child's. bone" and adds " vegetation" to the-exposure 1
pathway. ; Justification: l This change reflects the fact that both the critical- ! organ and the contributing exposure piSways changedias 1 a result of the reanalysis. Group:,3 FSAR Change Request Number: _88-652.39 i
, Related.SER Section: 11.2'2.5 .
SER/SSER Impact: No Figure 11A-3
Description:
(Correction) q Nodifies this figure by correcting the equation- i representing the evaporation from Lake Granbury, Justification: This change is made to. reflect the fact th'at. during. y the processing of Amendment 10,1the tera'"qsubs" was' j erroneously placed in the i.ake-.Granbury: evaporation ; equation. (The dispersion model, as displayed, clearly " shows this term as an input to Whitney Reservoir.)_ : Group: 3 . j FSAR Change Request Number: 88-652.36-Related SER Section: 11.2.1.3' -ll 1 i & 2.-
Attach:ent to TXX-90011' January 15, 1990 Page 225 of 304 FSAR Page (as amended) Description SER/SSER Impact': No 12.2-13 See Page No(s):14 thru 16
Description:
(Revision)' Reevaluation of Airborne Radioactivity - Methodology Justification: , These sections have been rewritten to reflect current
~
t radioactive airborne concentration calculation, to l remove unnecessary information which does not pertain to the analysis,,and to provide clarity.: The new
- calculation uses new methodology, assumptions,. and parameters..
Similar'information was transmitted to-the NRC via letters TXX-89221 and TXX-89476.. The 50.59 evaluation.
- has been completed for this change. This section;was 1 updated to support the revised calculations which;were j required-since the original calculations were nott i available. .
Some-of the specific changes: to abbreviate the-list i of potential-leak paths to a list?of examples of leak .i paths: the int cs. fon was edited >to summarize the ' current pro ess f or valuating the airborne' concentra-' tions: and tte methooelogy'(expressed in TXX-89476) has been include Group: '2- I FSAR Change Request Number: 89-468 j Related SER.Section: 12.2 SER/SSER Impact: Yes l
'I The section on airborne: concentration calculations has !
been updated (includes both the assumptions and the j tables). I Table 12.2-25 See Sheet No(s):01 thru 08
Description:
(Revision) Reevaluation of Airborne- Radioactivity - Tablulated :i Results= i Justification: -
, This table is being replaced to reficct the 'j assumptions, parameters, and'results of the current airborne concentration analysis. ]
Group: 2 o l FSAR Change Request Number:.89-468 , Related SER Section: 12.2 'i SER/SSER Impact: Yes . ' The section.on airborne. concentration' calculations has been updated. t Table 12.2-26 See Sheet No(s):01 thru 03 i
Description:
(Revision) _ Reevaluation of Airborne Radioactivity - Tablulated ! Results Justification:
Attachaont- to TXX 90011-January 15.1 1990 Page 226 of 304 FSAR Page (as amended) Dgacrintion This table is being replaced to reflect the assumptior.s. parameters, and results of the current airborne concentration analysis. Group: 2 FSAR Change Request Number:: 89-468 Related SER Section: 12.2 SER/SSER Impacts Yes. The section on airborne concentration calculations has been updated. 12.3-50. 51 See Page No(s):58
Description:
'(Revision) Deletion of references to and descriptions yof critical-ity accident monitors from Section 12.3.. Justification: Physical arrangement of facilities and detection capa - bilities of the monitors preclude the. ability to' detect a criticality accident. Exemption.fron' requirement to maintain criticality alarm system requires-these-deletions. This change is consistent with'the exemption to 10CFR70.24 requested in TV Electric letter TXX-89438 dated June:30. 1989, Group: 3 FSAR Change Request Number: 89-071 Related SER Section: 12.3.4 SER/SSER' Impact: No Table 12.3-8 See Sheet No(s):01 thru C6
Description:
(Revision) Deletion of descriptive ters
- criticality monitor' from monitor descriptions in. Table 12.3 8. 1' Justification:
Physical arrangement of facilities and detection' capa ' bilities of the monitors preclude the abilityLto detect a criticality accident. Exemption'from requirment to maintain criticality alarm system requires these. deletions. This change'is consistent with the y exemption to 10CFR70.24 requested in TV Electric-letter TXX-89438 dated JuneR30.- 1989. Group: 3 FSAR Change Request Number: 89-071 Related SER Section: 12.3 SER/SSER Impact: No 13.1-6
Description:
(Update) Update responsibilities of Manager of Projects Justification: Responsibilities of Nanager of Projects updated to include < cost, planning. and scheduling support for'all NEO departments. Organizational realignment to. support transition from contruction phase to operation mode. Group:.4 1
-Attach 2ent .to TXX-90011 January 15. 1990 Page 227 of 304 FSAR Page-(as amended) Descrintion FSAR Change Request Number: 89-780.1 Related SER Section: 13.1-SER/SSER Impact: No 13.1-8. 9
Description:
(Update) Deletion of Summary Discusion of Director of' Projects Justification: Summary discussion of-Director of Projects (Director of Management Services, LDCR SA-89 725) deleted since functions moved to Manager. Projects. Group: 4-FSAR Change Request Number: 89-780.2 Related SER Sectiont 13.1 SER/SSER Impact: No 13.1-8 See Page No(s):09
Description:
(Update) Chapter 13 Organizational' Changes Justification: Update to reflect changes in Engineering organization titles. Grouce 4 FSAR Change Request Number: 89-681.1 Related SER Section: 13.1 SER/SSER Impact: No 13.1-22
Description:
(Update) Chapter 13 Correction Justification: to correct incorrect section reference 13.1.2.2.1- . reference should be to section 13.1.2.1.2. Group: 3 FSAR Change Request' Number: 89-717.1 SER/SSER Impact: No Table 13.1-2
Description:
(Correction) Justification: Corrects incorrect.section reference 13.1.2.2.1. reference should be to.section 13.1.2.1.2. Group: 3 FSAR Change Request Number: 89-717.2 SER/SSER Impact: No Figure 13.1-2
Description:
(Uodate) Chapter 13 Organizational Changes Justification:- Update to reflect changes in Engineering organization titles. Group: 4 FSAR Change Request Number: 89-681.3 i Related SER Section: 13.1 , SER/SSER Impact: No j
L AttachD:nt to TXX-90011 January 15, 1990 Page 228 of 304 FSAR Page (as amended) Rgicription 13.1A-1, 3 See Page No(s):04 and 20
Description:
(Update) __ Shift Operations Nanager Personnel Change Justification: . . Change in personnel described in FSAR- section 13.1A Group: 4' FSAR Change Request Number: 89-772 Related SER Section:-13.1 SER/SSER_ Impact: No 13.1A-1, 38 See Page No(s):39,46, 54 & 55 _;
Description:
(Update) __ _ Chapter 13 Organizational Changes Justification: Update to reflect changes in Engineering organization titles. Group:-~4 FSAR Change Request Number:.89-681.2 Related SER Section =13.1 SER/SSER Impact: No 1 i 13.2-1
Description:
-(Update) . . I Nuclear training progran update'- Justification:- Clarification of " job" task analysis in~11eu of task ( analysis. Editorial and' typographical changes.: ; Group: 4 FSAR Change Request Number:-89-623.1 Related SER Sections 13.2 SER/SSER 1mpact: Yes. Discussion in the SER may~need to be updated.to reflect the current CPSES program. 13.2-1 See Page No(s):02 thru 08 and 22 Descriptions (Correction) NRC Request-for Additional ~Information, Aug.:l'. 1989 . Justification: j J Change addresses response to NRC request for additional
.information pertaining to, training and qualifications. .
.The NRC requested contained 11 questions. This' change
~
makes the FSAR consistent with thecresponses provided to the NRC on August 29 and' September 5, 1989.
- Group: 3 FSAR Change Request Number:'89-649 l3 Related SER Section: 13.2 l SER/SSER Impact: No:
{
Attachunt to TXX-90011 January 15. 1990 + (. Page 229 of 304 , FSAR Page i Descrintion (as amended) i ! 13.2-7
Description:
(Correction) .
'[
l Nuclear training program and organization update.- l Justification:
- The word " administered is added.
Group 3 i l-FSAR Change Request Number: 89-623.2 : Related'SER Section: 13.2 l- SER/SSER Impact: No ! i l 13.2-9. 22
Description:
(Update) , Nuclear Training Program and organization update. ( Justification: Change consistent with organization changes outlined in ' ; Section 13.1. Group: 4 FSAR Change Request Number: 89-623.3 Related SER Section:.13.2 SER/SSER Impact: No' 13.2-9
Description:
(Update) Correct cross-section references. Justification: Specific references within the section were dropped due to the section being reorganized. Group: 4 4 FSAR Change Request Number: 89-623.4 Related SER Sec+.1on: 13'.2 SER/SSER Impact: No 13.3-2
Description:
(Correction) NEO Organization Changes - CPSES Fire Protection - Program Justification: Change ' Fire Protection Technical Specifications' to
' Fire Protection Report.- Fire protection has been removed from the Technical ' Specifications.
Group:-3 i FSAR Change Request Number: 89-623.5'- Related SER Section: 13.3B SER/SSER Impact: No 13.3-3 See Page No(s):5. 6. and 10
Description:
(Update) NEO Organization Changes - CPSES Fire Protection ' Justification: Change consistent with organization changes-outlined in Section.13.1. Group: 4 s FSAR Change Request Number: 89-623.3 Related GER Section: 13.38 SER/SSER Impact: No
.L-_.-------_--_._--._--___.~ ,_ - ,,- - . .n. ..N...,..., ~ - . - , , -
- - _ - - - .~._ . . .
AttachIent. to TXX-9 )011 'l January 15, 1990 Page 230 of 304 i FSAR Page ., (as amended) Description '
?
13.4-1, 2
Description:
(Update) . i NEO Organization Changes - Review and Audit Justification: Assistant Radiation Protection Manager. is assigned'as a.
~
member of SORC. Reference to APRM is/added to 50RC 'i membership qualification section. Makes this section . consistent with Section 13.1.
- Group: 4 '!
FSAR Change: Request Number:' 89 623.6 Related SER Section: 13.4 SER/SSER Impact: Yes . l SER may need to be revised to ensure consistency. 13.4-4
Description:
~(Update) NE0 Organization Changes - Review and Audit Justification: , Clarification of SORC requirement to reviewall reportable events.' CPSES Technical Specifications , Sec. 6 requires SORC to review all REPORTABLE EVENTS.
- Reportable event defined in 10CFR50.73. ,
Group: 4 FSAR Change' Request Number:. 89-623.7- ' Related SER Section: 13.4 SER/SSER Impact: No 13.4 5
Description:
(Update) . ISEG reporting responsibility. consistent;with T/S. ., Justification: ( j Illustrate the reporting.. requirement.to the.Vice-Pres., Nuclear Engineering to be consistent'with the T/S.' ' (See also, TXX-89753.) Group: 4 FSAR Change Request Number: 89-623.8 Related SER Section: 13.4;. SSER1 .13.4 SER/SSER' Impact: No 13.5-5 Descripti on: . (Update) y NEO Organization Changes - Plant Procedures'and Instructions Justification: .l Delete reference to ' test department' since it'is now under the Technical-Support Department. This' change is consistent with the organization changes outlined.in Section 13.1. Group: 4 fr FSAR Change Request Number: 89-623.9-Related SER Section: 13 5 . SER/SSER Impact: No 4 4 7' ,
.c . . . - .
=
I Attach:Gnt to TXX-90011 : January 15, 1990 $ Page 231 of 304 l FSAR Page (as amended) Descriptin 13.5-10. 15
Description:
(Update) NEO. Organization Changes - Plant Procedures and Instructions Justification: _ . i Changes to.make consistent with organizational changes outlined.in Section 13.1. 's Group: 4 FSAR Change Request Number: .89-623.3 :* Related SER Section: 13.5 SER/SSER Impact: No 13.5-11
Description:
(Update) - Nuclear Organization Changes - Plant Procedures and Instructions Justification: Outage plan concept has been upgraded. . This philosophy'is no longer appropriate. Group: 4 . FSAR Change Request Number: 89-623.13 Related SER Section: 13.5 ' SER/SSER Impact: No 13.5 11
Description:
(Update) NEO Organization Changes - Plant Procedures and. - Instructions Justification: Insert information concerning managed maintenance I program:from Section 13.1. Group: 4 y FSAR Change Request Number:. 89-623.10 Related SER Section: 13.5 SER/SSER Impact: No-
- . 13.6-1
Description:
(Update)
- NEO Organization. Changes - Security i Justification
Delete: paragraph describing management organization
, since it reiterates information in Section 13.1'.
Replace with a reference to Section 13.1.2. Group: 4 FSAR Change Request Number:' 89 623.11 [ Related SER Section: 13.6 SER/SSER Impact: No 13.6-3, 4
Description:
(Correction) NEO Org:nization Changes - Security Justification: ' Delete item 4 and' renumber rema-ining items. The road noted in Item-4 doesn't follow along the entire -i
. perimeter of the protected area.
Group: 3 . FSAR Change Request Number: 89-623.12 2
'l
Attach;ent- to TXX-90011 l January 15, 1990 Page 232 of 304 j FSAR Page (as amended) Description
)
Related SER Section: 13.6 i SER/SSER Impact: No l 14 2-17
Description:
'(Clarification)' Clarifies Section 14.2.3.3 to provide an update to the Manager, Startup responsiblities inadvertently omitted in the previous amendment. ; (~ Justification: The Moaager, Startup is responsible for. the final I approval of- the preoperational test procedures in lieu , I of all preoperational and test. procedures. This change provides consistency within Section 14.2 text as-updated in the previous amendment. ' Group: 4- , FSAR~ Change Request Number: 89-666 Related SER Section: 14 SER/SSER Impact: No 14.2-24
Description:
- (Clarification) Revises Section 14.2.5 to state that the Plant Manager' authorizes the release to proceed to a higher power l 1evel following completion of major power plateau "; testing.. ' '
-Justification:
g Section 14.2.5 has been revised per NRC request'to- I to provide consistency with previously provided information.
-Group: 4
'FSAR Change Request Number: 89-662.2 Related SER Section: 14 SER/SSER Impact: No l 14.2-34
Description:
(Clarification) Clarification of relative power distribution and - instrumentation testing to. be performed.during the Low Power Testing Program. Justification:- j The word " concurrent" is deleted since.it implie's simultaneous performance of the relative power. , distribution test and-the nuclear instrumentation 1 calibration ~ tests. ! There is no regulatory requirement or testing basis I for the simultaneeus performance of these tests. Thes j intermediate-and power range nuclear channels need to
- be calibrated at.the low power ranges prior to the H performance of relative power. distribution testing. 'j Group: 4 FSAR Change Request Number: 89 605 i Related SER Section: 14 i SER/SSER Impact: No
'l
a Attach 2snt- to TXX-90011- ! January- 15, 1990 !
.Page 233.of 304
1 FSAR Page (as amended) Description J Table 14.2-2 See Shee+.-No(s):03a, O5a, 09a and~11a !
Description:
(Clarification) i
. Clarifies the Acceptance Criteria to prevent the D misinterpretation that pressures which exceed. design requirements are acceptable.
Justification: . In the' resolution cf Inspection Report Open Item . #
- 8940 O'02, the Acceptance Criteria for T14.2-2. Sheet i 5a was identified as requiring clarification to prevent the misinterpretation that pressures which exceed. ,
design requirements are acceptable. . The-Acceptance Criteria now states that1the Station Service Water. . pumps meet design requirements-and the system flow and. pressure requirements are satisfied. In1 addition,
-T14.2-2,. Sheets.3a, 9a and 11a were found to requira similar clarifications.
Group: 4 FSAR Change. Request Number: 89-791 Related SER Section: 14 . SER/SSER Impact: No Table 14.2-2 See Sheet No(s) 08A
Description:
-(Update) Update the process used to test and' certify the Halon-Fire Suppression ' system. Justification: i Add the option to allow acceptance of Halon Suppression System' testing performed-by TU Electric (or. designated
' vendor), reviewed by JTG and approved by the Manager, Startup.
Group: 4 FSAR Change Request Number: 09-529 SER/SSER Impact: No . Table 14.2-2 See Sheet No(s):28
Description:
(Clarification) Clarifies T14.2, Sheet 28. Test Methoi 4, to delete
, chlorine gas' detector.
Justification: Removes chlorine gas detector for autonatic isolation of. Control Room HVAC system. This clarification. provides consistency with FSAR sections revised int a
' previous amendment which removed the service water and circulating water chlorination system and the O subsequent removal of all significent onsite chlorine storage.
Group: 4 FSAR Change Request Number: 89-500 Related-SER Section:-14 SER/SSER Impact: No
Attachment to TXX-90011 January 15. 1990 Page-234 of-304
~FSAR Page (as amended) Descrintion
. Table 14.2 2 See Sheet No(s):30a
Description:
(Correction) Deletes " filters" from testing description. Justification: Neutron Detector Well Cooling Coils do not have permanent filters. .Therefore " filter" is beir.g deleted from the testing description as it is not applicable. Group: 3 FSAR Change Request Number: 89-675.15 Related SER section: 9.4 _ i SER/SSER Impact:.No i Table 14.2-2 See Sheet No(s):34
Description:
(Correction) Corrects the inconsistency between FSAR Table 14.2-21 (Sht. 34) and FSAR Section 8.3.1.1.11 by eliminating the testing.of non-existent trip functions on the diesel generator sets. Justification: Section 8.3.1.1.11 correctly lists the CPSES diesel generator' trip functions. Table 14.2-2.has been corrected to be consistent with Section 8. 3 .1.1.' 11. Group: 3 _ p FSAR Change Request Number: 89-419 Related-SER Section: 8.3.1 - SEP./SSER Impact: No' Tablo 14.2 2 See Sheet No(s):41
Description:
(Clarification)- Modifies T14.2-2 Sheet ~41;to addressicommitments made in response to NRC Question 423.2(2)(a). Justification: w Provides a clarification to'T14.2 2. Sheet 41, test method to address commitments made in R423.2(2)(a) in a previous FSAR amendment. Group: 4 4 FSAR Change Request Number: 89-581 Related SER Section: 14 SER/SSER Impact': No Table 14.2-2 See Sheet No(s):50 and 50a
Description:
(Clarification) Clarifies the intent T11.2-2,,Shts. 50 & SOA to specify the operations applicable-to the main steam and feed-water isolation valves to_ eliminate confusion in the text. Justification: The operation of the main feedwater isolation' valves , can be demonstrated only from/the Control. Room; the ; ) shutdown panel does not'have the capablity to actuate these valves. In addition Test' Method 3 has been:
=
-i
-Attachmnt to-TXX-90011 January 15.-1990 !
Page 235'of 304 FSAR Page , (as amended) Deserintion. j clarified to specify that the main feedwater isolation valve have a minimum and maximum closure time Land that ! the uain steam isolation valves have a maximum allowed .- closure. time. ' Group: 4 FSAR Change Request Number: 89-545 ' Related SER Section:'14" ' SER/SSER Impact: No' Table 14.2-2 See Sheet No(s):56 ,
Description:
(Revision). Relocates; test requirement to demonstrate pressurizer ' spray and' heater effectiveness;from Preop' Test Summary T14.2 2-(Sht. 56) to'the ISU Test Summary.T14.2 3 l (Sht. 2). Justification: Pressurizer spray flow depends on the delta-pressure across the reactor core and the internal full. delta-pressure is not tw eloped until after the core is loaded. Full core load. configuration is not available- > during the Preop Test phase. . Group: 3 FSAR Change Request Number: 89-753 , Related SER Section: 14 SER/SSER Impact: 'No Table 14.2-2 See Sheet No(s):56a
Description:
-(Clarification) Clarifies Table 14.2-2. Integrated Hot Functional Test. Sheet 56A, Test Method #7, with the deletion of'the-requirement to verify the proper.feedwater control' I system response. Justification:- The verfication of proper-feedwater control system response is. performed during the testing of the main steam and feedwater isolation valves in Table 14.2-2, ' Sheet 50. j Group: 4' . FSAR Change. Request Number: 89-544. Related SER Section: 14-SER/SSER Impact: No Table'14.2-3 See Sheet No(s):02 and 02a'
Description:
(Revision) Relocates test requirement to demonstrate' pressurizer spray and heater effectiveness from Preop. Test Summary T14.2-2 (Sht. 56) to the ISU Test Summary T14'.2-3. ; (Sht. 2). ' Justification: > See Description for T14.2-2. Sheet 56. Group: 3 75AR Change Request Number: 89-753
.. . n .. ..
..- . ..-- - - . . - . -a - . . - a .-.. -. .
Attach 22nt' to TXX 90011 January 15. 1990 ; Page 236 of 304 FSAR Page (as amended) Descrintion i Related SER Section: 14 i SER/SSER; Impact: No Table 14.2-3 See Sheet No(s):23 '
Description:
-(Update) Revises Table 14.2 2, Sheet 23. to include 10% load transient at approximately 30% power following
- completion of 50% power plateau testing.
Justification: See Description for p. 1A(B)-45. Added "approximately"- to Test Method 2. s
- Group: 3 .
FSAR Change Request Number:- 89-662.1
- Related SER Section: 14 SER/SSER Impact: No Figure 14.E-4
Description:
(Clarification) , l Clarifies Figure 14'.2-4 for Control Rod Tests to indicate the schedule for completion of testing at 50% + i power. Justification: The Control Rod Drive Tests on Figure 14.2-4 covert . both the Control Rod Drive Test Summary (T14.2-3 ' l Sht. 4) and the Automatic Reactor Control System-Test ,
- Summary (T14.2-3. Sht. '33). This clarificationi reflects a change-to the time duration for the Control Rod Drive l
Tests from ending at_" Initial Criticality" to "50% Power". A pre-requisite for the Automatic Reactor.- Control System initial.startup testing-is 50% power. Group: 4- - FSAR Change Request Number: 89-720 i Related SER Section:.14' SER/SSER Impact: No
'15.0-15
Description:
(Correction) Modifies the text in Section 15.0.6. " Trip Points'and Time Delays to Trip Assumed in-Accident Analyses", and
, deletes Section 15.0.7', " Instrumentation Drift and-Calorimetric Errors - Power Range Neutron Flux". 'v Justification:
These changes reflect the fact-that.the nominal power r range neutron flux trip setpoint'is calculated in.a: like ht*ntr as for other trip'setpointscof the Reactor Protection System, and refers to Section 7.1.2.1.9 and-
. the technical specifications for relevant information.
Group:-3 FSAR Change !!cquest Number: 89'672.01 - Related SER Section: 15.1~1 . SER/SSER Impact: No L e i S,s --<,---.---e - a- .--------J a ..a-a
+ .-h--- - ,. w- ~ ww& "
t
Attach ent 'to TXX-90011
' January 15, 1990 Page 237 of 304 FSAR Page (as amended) Description 15.0-27
Description:
(Update) Updates the reference for the LOFTRAN Code. Justification: This change reflects the, fact that the Westinghouse report describing the LOFTRAN Code has been approved by the NRC. Group: 3 FSAR Change Request Number: 89-672.34 Related-SER Section: 15.1.2 SER/SSER. Impact: Yes Section:15.1.2 should be revised to reflect the fact that the LOFTRAW code has been approved. Table 15.0-3
Description:
(Correction) Changes-the value of the reactor coolant loop ~ flow rate used in accident analyses-and deletes the associated-footnote. Justification: This change modifies the reactor coolant loop flow rate to-reflect the fact that all of the accident analyses of record now incorporate the.95,700 gpm value. Group: 3 . FSAR Change Request Number: 89 672.02 ; Related SER Section:-15.1.1 i SER/SSER-Impact: No Table 15.0-4 See Sheet No(s):01 ! l
Description:
(Correction) Modifies this' table,by deleting the 1945 psig low pres- .i surizer pressure entry and the associated-footnote. 1 Justification: This change is made to reflect the fact that the 1945 psig value for low pressurizer pressure is not the-limiting trip point as called for in the table. Group: 3 FSAR Change Request Number: 89-672.51 Related .SER Section: 15.1.1
, SER/SSER Impact: No ;
Table 15.0-5 Descriptions (Correction) Deletes Table 15.0-5 in its entirety. Justivication: 1 This change reflects the fact that the:re.ameters -! listed in the table are incorporated into the nominal
}
high range neutron flux trip set point in.a like_ manner. I as for other uncertainties thetiare incorporated in other Reactor Protection. System trip setpoints: .the , basic. methodology is discussed in- Section 7.1.2,1.9. Group: 3 ' FSAR Change Request Number: 89-672.03 i Related SER Section: 15.1.1 SER/SSER Impact: No
. ~. . -. __--- _. --
l Attach:ent1 to TXX 90011 t January 15, 1990 , Page 238 of 304 FSAR Page- - i (as amended)- Descriction ; l ' i- ! Table 15.0 6 See Sheet No(s):04 Figure 15.019 L
Description:
. (Revision)' Modifies Table 15.0-6 by deleting the listing for the j- Startup of an Inactive Reactor Coolant Loop ~at an-Incorrect Temperature and deletes the associated L cequence of events diagram in Figure 15.0 19. I Justification: l This change reflects the fact that CPSES technical i- specifications require all four reactor coolant loops to be in operation whenLthe plant is in Modes 1 or-2. Group 3 l FSAR Change Request Number: 89-672.04 ' Related SER Section: 15.2.1 SER/SSER Impact: Yes Section 15.2.1 should be revised to' remove the Startup of an Inactive Reactor Coolant Pump at.an Incorrect' Temperature ever.t from the list of events that have been analyzed.- : Figure 15.0-10
Description:
(Revision) f Modifies this figure by deleting the reason' stated in the sequence cf events diagram for:the injection of borated water during recovery from the Depressurization of a Main Stein System event. ' Justification: _ This change is made to be consistent with'the change identified in Amendment 16 which deleted'the Boron In-jection Tank from the plant design, and with it any reference to preventing the return to: criticality. 'The- , change also reflects the fact that Section 15.1.5 of NUREG-0800, Rev. 2, contains no specific requirement-for preventing the return to criticality:-~rather, it' requires that (1) the primary reactor: coolant' system be maintained in a safe status. and (2). fuel design' limits not be exceeded. (These' criteria are met-for.this " case.) ,
, : Group: 3 FSAR Change Request Number: 89-672.05 '
Related SER Section: 115.3.5 SER/SSER Impact: No-Figure 15.0-11
Description:
(Correction) Changes the figure to substitute the'P-9 permissive for= l P-7. Justification:
'This change is made to reflect the current plant design.-(This reference to P-7 was inadvertently.
overlooked in preparation of the change in~ Amendment 77). Group: 3 FSAR Change Request Number: 89-672.06- 4 I r
.._____m.___:__-_w.-_
. _ . . - ~ . . ,. .. . . - - . . . . - . _ . - - . - ._ ___ ,
Attach:ent to TXX-90011 January 15, 1990 Page 239 of 304 FSAR Page (as amended) Description ; Related SER Section: 15.2.2 ; SER/SSER Impact: No. l Figure 15.0 19 See Sheet No(t): Table 15.0 6, sh 4 '
Description:
(Revision) . I Deletes this. figure in its entirety. Justification: , See justification provided for the change to Table
- 15.0 6. sh 4.
Group 3 FSAR Chatge Request Number: 89-672.04 Related SER Section: 15.2.1 SER/SSER Impact: Yes ._ See impact described as a result of the change to Table - 15.0-6, sh 4. , 15.1-15
Description:
(Revision) . . . Modifies that portion of the text in Section 15.1.4.2 which discusses the analyses performed for the Inadver- ! tent Opening of a Steam Generator Relief or Safety-Valve event. Justification: See justification for the change to Figure .15.0-10, above. Group: 3 FSAR Change Request Number: 89-672.07 Related SER'Section: 15.2.1 ! SER/SSER Impact: No-
- 15.1-16
Description:
(Addition) Modifies cne of the conditions assumed to exist in l order to provide a minimum capability for injection of 1 concentrated boric acid'during .the Inadvertent Opening of a Steam Generator Relief or Safety: Valve event. Justification: . _ l , This change reflects the fact-that the'added automatic valve realignment,must be_ completed prior'to the !;) j delivery of' borated water to the reactor coolant-1 l system. 1
- Group
- 3 .l j FSAR Change Request Number:^ 89-672.08
- Related SER Section: 15.2.1 l SER/SSER Impact: No I l
i L 15.1-16, 17
Description:
(Correction) ;
' Modifies the value of the steam flow rate used in;the i analysis:of the Inadvertent Opening of a steam-Generator Relief or Safety Valve event. l
' Justification:
These changes are made to reflect the current value of .i the steam flow rate used in the analysis. l Group: 3' 14 l
r-- Attachxnt to TXX 90011 January 15. 1990 Page 140 of 304 FSAR Page (as amended) Description FSAR Change Request Number: 89-672.09 I Related SER Section: 15.2.1 SER/SSER Impact: No
.15.1-23
Description:
.(Addition)
Modifies one of the conditions assumed to exist-in-the analysis of the. Steam System Piping Failure event. j Justification: This change reflects the fact that the added automatic valve realignment must be completed prior:to the delivery of borated water to the reactor coolant' system. Group 3 FSAR Change Request Number: 89 672.10 Related SER Section:,15.3.5 SER/SSER Impact: No 15.1-30 M Page No(s): Table'15.'l-3. sh 2 1 Der cripti on: (Correction)' ' Changes the partition factors assumed for elemental ; iodine in the steam generators, which were used in evaluating the radiological consequences of the Main a Steam Line Break event. Justification: This change is made in order to. conform the FSAR to the assumption that was used in the analysis; the need for this- change was apparently overlooked during the prepa-ration of the amendment.that reported the -analysis. Group: 3 FSAR Change-Request Number:_89-694- ! Related SER Section: 15.4.1'_ SER/SSER Impact: No 15.1-33
Description:
-(Update) Updates the reference for the-LOFTRAN Code. Justification: This change reflects the fact that the Westinghouse report describing the LOFTRAN Code has been approved-by the NRC. Groun: 3 F%R Change Request Number: 89-672.34 Related SER Section: 15.1.2 i SER/SSER Impact: Yes ! Section 15.1.2 should be' revised to reflect' the ' fact-that the LOFTRAN Code has been approved. 3 Table 15.1-3 See Sheet No(s) 021
Description:
(Correction) l See description for change on page 15.1-30. Justification: See , justification for change on page 15.1-30. ' f Group: 3 ' i
e Attach;ent- to TXX-90011 January 15, 1990 Page 241-of 304 F5AR Page (as amended) Descrintion FSAR Change Request Number: 89-694
'Related SER Section: 15.4.1 SER/SSER Impact: No 15.2-16
Description:
(Correction) Modifies the text in Section 15.2.6.2.1 to indicate that the event being considered is the Loss of Non-Emergency AC Power, Justification: This change corrects the text to reflect.the actual ! event that is evaluated. ! Group: 3 . FSAR Change Request Number: 89-672.11 Related SER Section: 15.2.2 SER/SSER Impact: No Figt re 15.2-9 See Sheet No(s): Figures 15.2-10, 11 and 12- '
Description:
. (Correction)
Replaces Figures 15;2-9 through~15.2-12: these were inadvertently not replaced in the processing of Amendment 76 with the result that the.old figures were labeled as Amendment 76,'thus indicating thatLthey represented the rtvised figures. Justification: This substitution is made to rectify the error which occurred during the processing of' Amendment 76. Group: 3 FSAR Change Request Number: '89 672.12 , Related SER Section: 15.2.2 1 SER/SSER lapact: No Figure 15.2-13 I See Sheet No(s):Fioures 15.2-14 through 26A
Description:
.(Correction) l Replaces Figures 15.2-13 through 15.2-26A: these were : inadvertently not replaced in the processing of Amendment'76 with the result'that the old figures were labeled as Amendment 76, thus indicating that they-j represented the revised figures. ! Justification: 1 This substitution is made to rectify the error which occurred during the processing of Amendment 76.- ' Group: 3 FSAR Change Request Number: 89-672.12-l Related SER Section: 15.3.6 ' SER/SSER Impact: No 1l 15.3-4, 5
Description:
(Correction) l Modifies the second and third paragraphs-in the section discussing the results of the Partial Loss of Forced i Reactor Coolant Flow event by indicating that onlyl one J case was analyzed. i Justification:
Attech snt to TXX 90011 January 15, 1990' Page 242 of 304 FSAR Page
' ist reended) Descrintion This change reflects the fact-that'the CPSES technical' specifications require all-four reactor coolant. loops to be in operation when the plant is in Modes 1-or 2.
Group: 3 FSAR Change Request Number: .89-672.13 Related SER Section: 15.2.2 SER/SSER Impact: No 15.3-11 Descriptions (Revision) . . Modifies the value of the rod power at the hot spot (i.e.. FsubO) used in the evaluation of peak cladding temperature during the Reactor Coolant Pump Shaft Seizure (Locked' Rotor) event. Justification: -i This change is made to be' consistent with the current
~
i analysis which used a value for Fsub0 of 2.5 (vs. 2.32). (See FSAR Table 15.3.2.) This change, has t,een evaluated under the TU Electric-50.59 process as dis-cussed in TXX 89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 89-672.32 Related SER Section: 15.3.7
'SER/SSER Impact: No 15.3-14
Description:
(Editorial). Modifies the discussion of the. Reactor Coolant Pump; Shaft' Break event. , Justification: This chenge is made to reflect the current: analysis methodology in which this event is no longer specifi- 4 l cally analyzed because it=is bounded byLthe Locked ' Rotor event. Group: 4 FSAR Chf.nge Request Number: 89-672.33 Related SER Section:' 15.3.7 SER/SSER Impact: No j 15.3-15 j
Description:
-(dpdate) Updates the reference for the LOFTRAN Code. Justification: This change reflects the. fact that the Westinghouse . report describing the LOFTRAN Code has been approved by I the NRC. Group: 3 FSAR Change Request Number: 89-672.34 Related SER Section: 15.1.2-SER/SSER Impact:'Yes Section 15.1.2 should be revised to reflect the fact that~the LOFTRAN Code has.been approved, t b
Attach ent to TXX-90011-- January 15. 1990 ; Page 243 of 304 .i FSAR Page . . (as amended) Descrintion i l
- Table 15.3 1 See Sheet No(s):2, Table 15.3 2 '
L
Description:
(Correction) Modifies the time sequence of events obtained from re-analysis of.the Reactor Coolant Pump Shaft Seizure (Locked Rotor) event. 1 Justification: These' changes are made to reflect the results of the current analysis that used a revised value for FsubO. i This change has been evaluated under the TU Electric-
. 50.59. process as discussed in TXX-89718 dated 9/28/89. ,
. Group: 2 q FSAR Change Request' Number: 89-672.35 i Related SER Section: 15.3.7 SER/SSER Impact: No .
ll Section 15.3.7 should be revised to indicate that the i peak RCS pressure during the Locked Rotor event is 2648 psia (rather than 2590 psia) and the maximum (fuel]-cladding temperature is 1795 degrees F (rather-than 1809 degrees F). Table 15.3-2 -See Sheet No(s): Table ~15.3-1 (sh 2)' ; l
Description:
(Correction) -i
. Modifies the results obtained for certain core para-I meters based on reanalysis of the Reactor Coolant Pump l
Shaft Scizure (Locked Rotor) event.. Justification: 4 See justification for-the change to Table 15.3-1..sh.2. .] Group: 2 i FSAR Change Request Number:i89-672.35 Related SER Section: 15.3.7 SER/SSER Impact: Yes _ _ . . { Section 15.3.7 should be revised to indicate that the peak Reactor Coolant System pressure achieved during the Locked Rotor event is 2648 psia (rather than 2590 psia) and the maximum [ fuel]L cladding temperature is - 1795 degrees F (rather than 1809 degrees F), i Figure 15.3;17, 17A See Sheet No(s): Figures 15.3-18, 19, 19A. 198 &'20 l
Description:
(Correction) ! Provides new figures depicting the transient response of certain parameters resulting from the' reanalysis of the Locked Rotor event. ! Justification: ? The new figures reflect the results of the current analysis that used a revised value for Fsub0. This change has been evaluated under the TU Electric 50.59 j process as discussed in TXX-89718 dated 9/28/89. 4 Group: 2 . . FSAR Change Request Number: 89-672.36 Related SER Section: 15.3.7
)
i _i
. Attach 2ent to TXX 90011. ,
January 15, 1990 Page 244 of 304 FSAR Page (as amended) Descrintion SER/SSER Impact: Yes Section 15.3.7 should be revised to be consistent with the 2648 psia peak RCS pressure indicated in FSAR Figure 15.3 18. 15.4-26 See Page No(s):T15.4-1 Sh 3., F15.4-16 thru 20
Description:
(Revision) Modifies the text-in Section 15.4.4 as well as Table 15.4-1 (sh 3) and Figures 15.4 16 to 20 by deleting material related to plant operation with less than four reactor coolant loops and adding the bases for not analyzing the specified events. Justif6 cation: These changes reflect the fact that the CPSES technical specifications require all four reactor coolant loops to be in operation when the plant is in Modes 1 or 2. Group: 3 FSAR Change Request Number: 89 672.14 Related SER Section: 15.2.1 > SER/SSER Impact: Yes Section 15.2.1 should be revised to remove-the Startup- ' of an Inactive. Reactor Coolant Pump at an. Incorrect. Temperature from the list of' events that have been analyzed. 15.4-32
Description:
(Clarification) Modifies the text' describing the conditions that are-assumed in the analysis-of Chemical and Volume Control System malfunctions that result-in. boron dilution events occurring during hot =and cold shutdown and hot
. standby, Justification:
These changes reflect the fact that, although the supplied boron concentration is a very conservative ; estimate, it is not intended to represent a " maximum" ' i value, as had been= stated. Group: 4' ' FSAR Change Request Number:: 89-672.15 Related SER Section: 15.2.3.1 SER/SSER Impact:-No ' 15.4-54
Description:
(Correction)- Provides the results of a reanalysis of the ejected rod ' worth and hot channel factor for the-end of cycle, zero. power case. . Justification: l This change is made to reflect the results of a ; reanalysis of'the Rod Cluster Assembly Ejection . . j Accident for the end of cycle, zero power case using plant specific (vs. Westinghouse generic) core ; parameters. Whereas'the value of the rod' worth de- I creased as a result of the reanalysis, the. hot channel- ' n 1
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Attachm2nt to TXX-90011 January- 15. 1990 Page 245 of-304 FSAR Page (as amended) Description factor did increase slightly;ihowever.' the peak clad and fuel center temperatures decreased.'thus indicating = that the resulting transient was less severe-than-in j the earlier case.- Group: 3 FSAR Change Request Number: 89 672.16 Related SER Section: 15.3.4 SER/SSER Impact: No 15.4-63
Description:
(Update) Updates the reference.for the LOFTRAN Code. Justification: This change reflects the fact that the Westinghouse report describing the LOFTRAN Code has been approved by the NRC. Group: 3 FSAR Change Request Number: 89-672.34 Related-SER Section: 15.1.2 SER/SSER Impact: Yes Section 15.1.2 should be revised to reflect the fact that the LOFTRAN Code has been approved. Table 15.4 1 See Sheet No(s):03 pg 15.4-26. F15.4-16 thru 20
Description:
-(Revision) Deletes the entire entry for "Startup of an inactive reactor coolant loop at an_ incorrect temperature". Justification: These changes reflect the fact that the CPSES technical specifications require all four reactor coolant loops to be in operation when the plant is in Modes 1 or 2. Group:.3 FSAR Change Request Number: 89-672.14 Related SER Section: 15.2.1 SER/SSER Impact: Yes See SER/SSER Impact described for the change to-pgs. 15.4 26 to 30. Table 15.4-3
Description:
.(Clarification) Modifies this table by adding a clarifying footnote regarding the End of Life zero power entries for. Ejected rod worth and Fsubq after rod ejection. Justification: This change is made in order to clarify that the listed ralues for the Ejected rod worth and Fsubq after rod f ejection bound those used (i.e. 0.5% delta k and 20.0) ( in subsequent reanalysis of the Rod Cluster Control Assembly Ejection Accident. Group: 4 FSAR Change Request Number: 89-672.52 Related SER Section: 15.3.4 SER/SSER 1mpact: No
, Attach:ent to TXX 90011 L = January 15, 1990 : Page 246.of 304 t 'I 1 i l FSAR Page l (as amended) Description Figure 15.4 16 See Sheet No(s):and Figures 15.4-17 thru 20 i
Description:
(Revision) Deletes Figures 15.416 to 20 in their entirety. Justification: These changes reflect the fact that the CPSES technical i' specifications require all four reactor coolant loops to be in operation when the plant is in Modes 1 or 2. Group: 3 ' l FSAR Change Request Number: 89-672.14 Related'SER Section: 15.2.1 SER/SSER-Impact: Yes See SER/SSER Impact described for the change to pgs. - 15.4-26 to 30. 15.5-7
Description:
(Update) Updates the reference for the LOFTRAN Code. Justification: This change reflects the fact that the Westinghouse report describing the LOFTRAN Code has been approved by the NRC. Group: 3 ' FSAR Change Request Number: 89-672.34 Related SER Section: 15.1.2 ' SER/SSER Impact: Yes t Section 15.1.2 should be revised-to reflect the fact that the LOFTRAN Code has been approved. . 15.6 6
Description:
(Clarification) Modifies the text of the introductory paragraph of - Section 15.6.3.1 by specifying the: purpose for analy-zing the Steam Generator Tube Rupture event namely, to i demonstrate that~the radiological doses are within the-guideline values of 10CFR100. Justification: l This change is made to clarify the acceptance criteria for this events it conforms with the criteria specified in Section 15.6.3 of NUREG-0800. Group: 4 : FSAR Change Request Number: 89-672.46 Related SER Section: 15.4.4 SER/SSER Impact: No 15.6 7
Description:
(Clarification) Modifies the text in Section' 15.6.3.1 to clarify the term " ruptured steam generator". Justification: This change is made to avoid misinterpretations that were possible with the terms used' earlier. Group: 4 FSAR Change Request Number: 89-672.37 Related SER Section: 15.4.4 SER/SSER Impact: No
t Attach ent to TXX-90011 1 January 15, 1990 . Page 247 of 304 ! I FSAR Page. (as amended) Descrintion . 15.6 9, 10
Description:
(Correction). '6 Modifies the description of the operator actions to be-taken to terminate the primary-to secondary break flow and the Steam Generator Tube Rupture event as well.
- Justification:
l -These changes are made to clarify the descriptions of the operator actions and to achieve consistency with the-instructions contained in the emergency: operating procedures. Group: 3 FSAR Change Request Number: 89 672.38 Related SER Section: 15.4.4 SER/SSER Impact: LNo 15.6-11
Description:
(Clarification)' . Modifies a portion of the text in the subsection,
" Method of Analysis", which describes the major analy- 'l ses assumptions involving the Initial Operating Con- i ditions used in evaluating the Steam Generator Tube Rupture event.
Justification - j This change is made-in order to provide a more general description which is appropriate for all single active failure scenarioc that are evaluated or analyzed. Group: 4 FSAR Change Request Number: 89 672.39 Related SER Section: 15.4.4 SER/SSER Impact: No 15.6-11
Description:
(Clarification) Changes the introductory' portion of the subsection
" Method of Analysis" by~ adding a paragraph which'ampli-fies upon the analysis process.
Justification: This change is made to more fully describe the general ; analysis methodology and, in particular, to indicate that several cases were analyzed in order to confirm that the ruptured steam generator does not fill with liquid. l Group: 4 FSAR Change Request Number: 89-672.53 l Related SER Section: 15.4.4 i SER/SSER Impact: No l 15.6-12
Description:
(Clarification) ! Modifies the text in the subsection, " Method of Analysis," which describes the major analysis assumptions involving Equipment Availability used in evaluating the Steam Generator Tube Rupture event. Justification: This change is made to clarify the reasons supporting
Attach 2;nt to.TXX 90011 January 15, 1990 l Page 248 of 304 1 l j ! FSAR Page , (as amended) Description j i l the analysis assumptions concerning use of the atmospheric relief valves and the main steam safety. valves. Group: 4 FSAR Change Request Number: 89 672.40 Related SER Section: 15.4.4 SER/SSER Impact: No < 15.6-12
Description:
(Clarification) Modifies a portion of the text in the subsection,
" Method of Analysis", which describes the major analy-sis assumptions involving ESF System Capacities used in l evaluating the Steam Generator-Tube Rupture event.
Justification: This change is made to more clearly describe the impact of the use of the conservative ESF system capacities, i Group: 4 FSAR Change Request Number: 89-672.48 Related SER Section: 15.4.4 , SER/SSER Impact: No l 15.6 13
Description:
(Clarification) Modifies a portion of the text in the subsection, ( " Method of Analysis", which describes the major analy-sis assumptions involving Protection and Control Systems used in evaluating the Steam Generator Tube Rupture event. Justification: This change is made to more clearly describe the be-havior of the water level in the ruptured steam gewnerator given the different protection and control l actions that are discussed. Group: 4 i FSAR Change Request Number: 89-672.49 Related SER Section: 15.4.4 SER/SSER' Impact: No 4 15.6-14
Description:
(Revision) Modifies the text in the subsection, " Method of l Analysis," which describes the major analysis assumptions involving the Single Active ~ Failure l used in the Steam Generator Tube Rupture event'. Justification: This change reflects the results of a reanalysis that-l incorporated the effects of plant modifications not previously considered; in addition, the change provides information concerning the assumptions relevant to the limiting single active failure scenario for steam generator overfill as identified during the analysis. Group: 3 f FSAR Change Request Number: 89-672.41 Related SER Section: 15.4.4 I
t Attach ent to TXX-90011 !
~ January 15. 1990 l Page 249 of 304 ,
FSAR Page (as amended) Descrintion ; SER/SSER. Impact: No 15.6 14
Description:
(Editorial) , Hodifies the text in the subsection titled."Results" by' i removing superfluous wording and deleting other infor- , mation that is' contained elsewhere. Justification: This change is made to reduce repetition of infor . I mation. 'all of which is adequately described in Section 15.6.3.1. and te eliminate text containing-unnecessary ' detail. Group: 4 FSAR Change Request Number: 89 672.43 Related SER Section: 15.4.4 SER/SSER Impact: No 15.6 14
Description:
(Addition). Modifies the last paragraph of Section 15.6.3.2 by a general rewording provides the results of the , reanalysis of the Steam Generator Tube Rupture event and specifies an additional acceptance criterion for this event. Justification: This change is made to reflect the results of the reanalysis of this event which show that the available l volume before overfill decreased (from 320 cu. ft to 228'cu. ft). This change has been evaluated under the TV Electric 50.59 process as discussed in TXX 89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 89-672.44 Related SER Section: 15.4.4 SER/SSER Impact: No-15.6-14 See Page No(s): Figures 15.6-3, 3A, 3B &-3C
Description:
(Correcticn) Modifies the subsection, "Results", by referring to the revised figures that present the transient response of the pressurizer and ruptured steam generator ' pressure and the ruptured steam generator liquid volume; deletes two other. figures. Justification: This change is made to incorporate the results'of the reanalysis of the Steam Generator Tube Rupture event and to delete information that is not relevant.to demonstrating conformance to one of the acceptance criteria for this event. i.e., preventing steam generator overfill. -This change has been evaluated under the TV Electric 50.59 process as discussed in TXX-89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 89-672.42 e- y e, we,
Attach ent to TXX 90011 i January 15. 1990- .l Page 250 of-304 5 FSAR Page i (as amended) Descrintion Related SER Section: 15.4.4 SER/SSER Impact: No 15.6 15
Description:
(Addition) _. Modifies that portion of the text in Section 15.6.3.3 which discusses the single active failure that is assumed to accompany the Steam Generator Tube Rupture. event in order to maximize the amount of radioactivity- , released to the environment. Justification: This change is made to provide the basis for selection of the single active failure,that was used in the analysis of the radiological' consequences of the Steam - Generator Tube Rupture event. , Group: 3 FSAR Change Request Number: 89-672.47. Related SER Section: 15.4.4 , SER/SSER Impact: No 15.6-15
Description:
(Clarification) Changes a portion of the text in Section 15.6.3.3 to indicate that it is the free volume available in the ruptured steam generator that is greater than for the scenario described in Section 15.6.3.2. Justification: This change is made to conform to the' terminology used < elsewhere. Group: 4 FSAR Change-Request Number: 89-672.50' Related SER Section:-15.4.4 ; SER/SSER Impact: No ~ i 15.6-23
Description:
(Revision) The time at which hot leg switchover should'be initiated has been revised from 18 to 16 hours. Justification: Increasing the upper limit on the RWST. boron concentra-tion (from 2100 to 2200 ppm) has been determined by-calculation to decrease the time at which switchover should occur. This revised time will result in adequate-safety injection flow to provide continued long. term [ cooling of the reactor core without boron precipi-tation. The impact of this change has been evaluated under the TU Electric 50.59 process as discussed in
- i. TXX-89718 dated 9/28/89.
! Group: 2 l FSAR Change Request Number: SA-89-779 l Related SER Section: 6.3.3 SER/SSER Impact: No (
Attach;ent to TXX-90011 January 15, 1990 Page 251 of 304-FSAR Page (as amended) Description 15.6-28
Description:
(Clarification) l Adds a clarifying, introductory sentence to Subsection 15.6.5.3.3, "[LOCA) Results". Justification: . This change is made to clarify that both the base case-analyses and the PCT. penalties that resulted from sub-sequent' safety' evaluations are described-in-the text of f this subsection, t f Group: 4 FSAR Change Request Number: 89-680.5 Related SER Section: 15.3.8 ' SER/SSER Impact:-No 15.6-28 See Page No(s): Figure 15.6-47A
Description:
(Editorial) Adds Figure 15.6-47A to the list of figures that, for the Large Break LOCA. presents the transients for the principle parameters (i. e., those of. interest). ' Justification: This change is made to reflect the fact that different safety injection flow rate curves were used for the large break and small break analyses. -(It is'to-be noted that only-one curve had been included :in the FSAR up until this amendment. Further, it should be pointed out that the curve depicted in Figure 15.6 47A. is in reality, the same-curve as had been shown in ' , Figure 15.6-47 except that the axes have been reversed l in the new figure. (The-fact that no technical change t is involved, led to the selection of the Editorial i classification.) Group: 4 FSAR Change Request Number: 89-680.7 Related SER Section: 15.3.8 l SER/SSER Impact:-No 15.6-29, 31
Description:
(Clarification) Nodifies the text in Subsection 15.6.5.3.3, "[LOCA) Results", to clarify that the PCT values of 2311-deg. F and 1788 deg.-F represent the base case results for the large break and small break LOCA's, respectively.: Justification: , These changes are made solely for the purpose of clari-fying which values represent the base case analysis results, so as to clearly differentiate them from those values which incorporate the PCT penalties that re-sulted from subsequent safety evaluations. Group: 4 FSAR Change Request Number: 89-680.6 Related SER Section: 15.3.8
'Attachtent .. to TXX-90011 I January 15,11990 ;
Page 252 of 304 ;
'i i
FSAR Page (as. amended) Description ; SER/SSER Impact: Yes Section 15.3.8 of the original SER should be revised to correct the peak cladding temperature specified for the Large Break LOCA: the value of 2001 deg. F should have been 2011 deg. F to be consistent both with the value stated in FSAR Am. 6 and, inferentially, in SSER 3. 15.6-30
Description:
(Correction) . Adds information to the Large Break LOCA analysis. results based on data from Unit 1: safety evaluations-that modified the peak cladding temperature. Justification: This change is made.to reflect the results of the current analysis of the peak cladding temperature for Unit 1 fuel. This change has-been evaluated under the TU Electric 50.59 process, as described in:TXX-89718, dated 9/28/89. , Group: 2 FSAR Change Request Number: 89-680.1 Related SER Section: 15.3.8 SER/SSER Impact: Yes
- Section 15.3.8 should be revisod to reflect'the current value for the peak cladding temperature for Unit I fuel, based on the Large Break LOCA, 1 e., 2058.5 deg. F.
15.6-30
Description:
(Editorial) 5 Changes'the list of figures-for the Small.8reuk (LOCA) that presents the principle-parameters of interest for
- the ECCS analyses, ,
l Justification: See the justification for'the change to pg'15.6-28 ' which addresses the. addition of Figure- 15.6 47A. Group:<4 FSAR Change Request Number: 89 680.8 Related SER Section: 15.3.8. SER/SSER Impact: No ' 15.6-31
Description:
(Correction) Adds information to the Small Break LOCA analysis results based on data from Unit I safety evaluations that modified the peak cladding temperature. i Justification: This change is made to reflect the results of the-current analysis of the peak cladding temperature for Unit I fuel. This change has been evaluated under the TV Electric 50.59 process as described in TXX-89718 dated 9/28/89.
- Group: 2 FSAR Change Request Number: 89-680.2-Related SER Section: 15.3.8
Attach:ent . to TXX-90011 January 15, 1990 l_ Page 253 of 304~ i I l FSAR Page ' (as amended) Descrintion SER/SSEC Impact: Yes. . Section 15.3,8 should be revised to reflect the current-l value for the peak cladding. temperature for Unit 11
- fuel, based on the Small Break-LOCA 1, e., 1895.5 deg. F.
15.6 35
Description:
(Revision) ;
-Modifies one of the assumptions used in the analysis of-the radiological consequences of post-LOCA leakage from-ESF equipment located outside the containment. ;
Justification: This change is made to conform with the guidance pro-vided in SRP 15.6.5, Appendix B with regard to the value to be used for ESF equipment leakage outside the containment, Group: 3 FSAR Change Request Number:'89 638,01 :' Related SER Section: 15.4.5 , SER/SSER Impact: No , 15.6-38
Description:
(Clarification) Modifies the text describing the air intake flow rates utilized in the reanalysis of the radiological con-sequences to control room occupants from the loss-of-coolant accident - , Justification: These changes more clearly reflect the analysis assump-t tions used to represent the. emergency recirculation mode of operation of the control room air-conditioning 1
- system when evaluating'the dose to control room occu-l pants from the loss-of coolant accident.
l Group: 4 l FSAR Change Request Number: 89-638.02 Related SER Section: 6.4 SER/SSER Impact: Yes SER Section 6,4 should be revised to indicate that-when the control room ventilation system switches to the emergency recirculation mode of' operation either 800 or 1600 cfm of filtered air will pressurize the control room, depending on whether one or both trains operate. 15.6-39, 40
Description:
(Addition) Modifies the description of certain of the_ assumptions used in the reanalysis of the dose to control room occupants from the loss-of coolant accident. Justification: The changes provide conservative data that are used in analyzing the component of the control room; dose that is due to ESF equipment leakage: these values had not been specified previously in the FSAR, Group: 3 - FSAR Change Request Number: 89-638.03 1
- - - , , . , - - - , , - . - r -e.
i Attach cnt
'to TXX-90011 - '
January 15, 1990 Page 254 of 304 FSAR Page (as amended)- Descrintian , Related SER Section: 6.4 SER/SSER Impact: No ? 15.6-41
Description:
(Revision) Adds an assumption regarding the unfiltered infiltra-tion rate into the control room that is used in the re-analysis of the dose to control room occupants from the loss of-coolant accident. .
-Justification:
This change reflects the results of measurements per-formed to determine the extent of bypass leakage into - the control room. Group: 3 FSAR Change Request Number: 89-638.04 > Related SER Section: 6.4 SER/SSER Impact: No q 15.6-41, 42
Description:
(Correction) Changes the radiation exposures incurred by control room occupants as a result of reanalysis of the radio-logical consequences of the loss-of-coolant accident. Justification: The revised doses reflect the results of a conservative reanalysis of the exposure contribution from ESF equipment leakage generated during_the course of the-loss-of-coolant accident. This change has been i evaluated under the TU Electric 50.59 process as ! discussed in TXX-89718' dated 9/28/89. Group: 2 FSAR Change Request Number: 89-638.05 Related SER Section: 6.4 SER/SSER Impact: No 15.6-44
Description:
(Update) Updates the reference for the LOFTRAN Code. Justification: This change reflects the fact that the Westinghouse-report describing the LOFTRAN Code has been epproved by the NRC. Group: 3 l_ FSAR Change Request Number: 89-672.34 l Related SER Section: 15.1.2 SER/SSER Impact: Yes Section 15.1.2 should be revised to reflect the fact that the LOFTRAN code has been approved. Table 15.6-1 See Sheet No(s):01
Description:
(Correction) Modifies the sequence of events results for the-Steam > Generator Tube Rupture event. Justification: This change is made to incorporate the results of the , i
~
1
'i ~ Attach:Snt to TXX-90011 January- 15, 1990 1 Page'255'of 304 1 1
FSAR Page ] (as amended) Descrintion j reanalysis of this event. Group: 3 . FSAR Change Request Number: 89 672.45 Related SER Section: 15.4.4 i SER/SSER Impact: No j Table 15.6-5. 6
Description:
(Correction) ; Modifies the LOCA analysis input data concerning the steam generator tube plugging levels as used in-these analyses. .3 Justification: These. changes are made to reflect the assumption used ' in the original.LOCA analysis and, in so doing, avoid ; misinterpretations; subsequent safety evaluations were performed to_ account for steam generator. tube plugging. Group: 3 FSAR Change Request Number:-89-680.3 ' Related SER Section: 15.3.8 SER/SSER 1mpact: No Table 15.6-5 See Sheet No(s): Figures 15.6 47A-& 478
Description:
(Correction) Modifies the value of the safety injection pumped flow used as input data in LOCA analysis.- Justification:- l' This change is made to reflect the' fact that different safety injection flow rates were used for the large and small break analyses; the flow rate for the former did not change whereas a separate and different flow rate :1 curve was used for the latter case; In~both instances, the curves represent the values that were used in the calculations. , Group: 3' FSAR Change Request Number: 89-680.4 , Related SER Section: 15.3.8-SER/SSER Impact: No i Table 15.6-12
Description:
(Addition) Modifies the table by including certain wind speed and direction information as well as control room occupancy l- factors used in the reanalysis of the control room dose I component from ESF equipment leakage occuring outsideL the containment. Justification: This change reflects the data used in the reanalysis of the post-LOCA contribution to the control room dose from ESF equipment leakage. - Group: 3 , FSAR Change Request Number: 89-638.06 Related SER Section: 6.4 SER/SSER Impact: No l ! I
Attach 2ent to TXX-90011 > January 15, 1990 i Page 256 of 304 : i FSAR Page > (as. amended) Descrintion Table 15.6-12 Description (Correction) : Changes the list of affected sectors for the X/0 values used in reanalysis of the containment leakage component of the control room dose from the loss-of-coolant > accident. Justification: This change is made-in order to achieve consistency with the listed v ' values. Group: 3 l FSAR Change Request Aber: 89-638.07 Related SER Section: 6.4 SER/SSER Impact: No. Figure 15.6-3
~
See Sheet No(s):and Figures 15.6-3A, -3B and -3C_ Description (Correction) Revises Figure 15.6 3: deletes the information dis-played on Figures 15.6 3A & B revises the-transient-shown on Figure 15.6-3C .(for the ruptured steam gener-- ator liquid volume) and relocates that information to Figure 15.6-3A: deletes Figure 15.6-3C.. Justification: See the entry for the change to pg 15.6 14. Group: 2 FSAR Change Request Number: 89 672.42 Related SER Section: 15.4.4 SER/SSER Impact: No-generator overfill. Figure 15.5 47A. 47B
Description:
(Addition) Replaces Figure 15.6-47 with Figures 15.6 47A and 15.6-47B. Justification: This replacement reflects the fact that different safety injection flow rates were used for,the analyses ' of.the large break and small break LOCA's; the curves _ do not present any changes from the values that had-been used in the analysis. _The curve for the small break case had not previously been providerd in the sly FSAR. Group: 3 FSAR Change Request Number: 89-680.9 ' Related SER Section: 15.3.8 SER/SSER Impact: No 1 15.7-3 See Page No(s):15.7-11
Description:
(Clarification) Accident Analysis - Radioactive Release From a Subsystem or Component - Environmental Consequences - Adds the phrase "...using the whole body dose' con-version factor from reference [3]" to the text. Justification: Cites the -reference document from which the whole body
k ittach2ent 'to TXX-90011 January 15,'1990 Page 257 of 304 i l ? i FSAR Page (as amended) Description f [ l dose conversion factors were obtained to calculate the whole body gamma dose. Group: 4 FSAR Change Request Number: 89 637.2 ; Related SER Section: 15.4.6 SER/SSER Impact: No 15.7 3 See Page.No(w): Table 15.7-1, sh 2 .
Description:
(Revision) Accident Analysis - Radioactive Release From a l l Subsystem or Component - Environmental Consequences - l Revises the whole body dose at the nearest point on the EAB to 7.6x10 2 rem (from 7.3x10-2 rem). Justification: The whole body dose at the nearest point on the exclusion area boundary is conservatively: recalculated , resulting in a slightly increased value which origi-nates from the use of a revised dose conversion factor that is taken from Revision 3 to the~ Westinghouse. Radiation Analysis Nanual. 'This-change has.been l evaluated under the TU Electric 10 CFR 50.59 process as discussed in TXX-89718 dated 9/28/89. Group: 2 FSAR Change Request Number: 89-637.1 Related SER Section: 15.4.6 SER/SSER Impact: No 15.7 11 See Page No(s):15.7-3. T15.7-1 Sh 2 i
Description:
(Clarification) Accident Analysis - Radioactive Release From a Subsystem or Component Environmental Consequences - Adds References 2 and 3 to reference section. Justification: ' Provides the reference document from which the whole body dose conversion factors were obtained to calculate the whole body gamma dose.
- Group
- 4
- FSAR Change Request Number: 89-637.2 Related SER Section: 15.4.6 SER/SSER Impact: No Table 15.7-1 See Sheet-No(s):02, 15.7-3
Description:
(Revision) Accident Analysis - Radioactive Release From a Subsystem or Component - Environmental Consequences - See the description provided for the: change to pg. 15.7-3, as identified-in FSAR Change Request Number 09-637.1. Justification: See the justification provided for the change to pg. 35.7-3, as identified in the description above. Group: 2
_ Attach ent to TXX 90011 January 15.-1990 , j' Page 258 of 304 I l l i FSAR Page 1 J (es.. amended) Descrintion_ I FSAR Change Request Number: 89-637.1 Related SER Section: 15.4.6 SER/SSER Impact: No
~'
Table 15.7-1 See Sheet No(s):02, T15.7 4 (sh 2)-
Description:
(Clarification). }' Accident Analysis - Radioactive Release From a ^ Subsystem or Component - Parameters for Postulated
~
Waste Gas Decay Tank Rupture - adds footnote "a". > Justification: Clarifies that the method of dose calculation utilized average gamme energies obtained from the Hestinghouse Radiation Analysis Manual Revision 3. Group: 4 i FSAR Change Request Number: 89 637.3 l Related SER Section: 15.4.6 SER/SSER Impact: No l Table 15.7-4 See Sheet No(s):02, T15.7-1 Sh 2 i L
Description:
(Clarification)
-Accident Analysis - Radioactive Release From a Subsystem or Component - Parameters for Postulated Waste Gas Decay Tank Rupture - adds footnote "a".
Justification: ; See Justification for Table 15.'7-1, sh 2. Group: 4 FSAR Change Request Number: 89-637.3 l Related SER Section: 15.4.6 3ER/SSER Impact: No 15B-2 See Page No(s): Table 15B-1 (sh 1)-
Description:
(Clarification) Accident Analysis - Dose Models Used to Evaluate the Environmental Consequences of Accidents - Physical Data for Dose Conversions _ Adds the phrase "...and from. reference [7]" to assumption #5. . Justification: I Clarifies that isotopic beta and gamma decay energies were also taken from reference [7]. Group: 4 FSAR Change Request Number: 89-637.4 Related SER Section: 15.4.6 SER/SSER Impact: No. 15B-5, 6 See Page No(s):08
Description:
(Clarification) Deletes references to specific computer codes or routines identified in the descriptions of the analytic models used for dose calculations. Justification: This change is made since it is not necessary to use specific proprietary computer programs to implement the 1 1
i Attach:snt- to TXX-90011 January 15, 1990
,Page 259 of 304- ,
FSAR Page (as amended) Descrintion accident analysis methodology.. Manual ' calculations,. industry codes, and utility analytic routines that are > l described within the calculation documentation package and use the same methodology are adequate ~for this: - purpose. Group: 4. _ .. FSAR Change Request Number:.89-473.1 i Related SER Section: 6.4 SER/SSER Impact: No 15B-7 Description (Clarification)? Modifies the. wording in the introductory paragraph of Section 15B.6 to avoid the implication that sole'reli- t ance will be placed on the listed proprietary' computer
' codes.
Justification: This change is made to reflect the fact that other. methods are employed (e.g., manual calculations, indus-try codes and utility analytic routines described with-in the calculation documentation package) which'use the. same methodology. Group: 4 FSAR Change Request Number: 89-473.2 Related SER Section: 15.4 SER/SSER Impact: No Table 158 1 See Sheet No(s):01, 158-2
Description:
(Clarification) Accident Analysis - Dose Models Used to-Evaluate the Environmental Consequences of Accidents-- Physical Data for Dose Conversions - Adds reference [7] to the "Averege Beta-Energy" and " Average Gamma Energy" columns. Justification: Clarifies that isotopic beta and gamma decay energies , were also taken from reference'[7). Group: 4 FSAR Change Request Number: 89-637.4 Related SER Section: 15.4.6 SER/SSER Impact: No 17.1-6, 12 See Page No(s):31
Description:
(Update) I l Change Vice President. Engineering and. Construction to j Senior Vice President: Change Director of Engineering to Chief Engineer: Change Manager, Plant Operation to Plant Manager. Justification: Update the titles to reflect the current NE0 organizational structure and reporting responsibilities Group: 4 FSAR Change Request Number: 89-725.1
?
Attach ent to TXX 90011 January 15, 1990 -; Page 260 of 304 FSAR Page (as amended) Description Related SER Section: 17.2: SSER6 17.2 . SER/SSER Impact: Yes . Section 17.2 in SER and SSER #6 are affected by the proposed change. Figure 17.1-5
Description:
(Update) Update the figure to reflect the current B&R. organization structure and reporting responsibilities. . Justification: The change is consistent with Sections 13.0 and 17.2. and is in accordance with the CPSES Quality Assurance Manual, Group: 4 FSAR Change Request Number: 89-725.3 SER/SSER Impact: No Figure 17.1-6
Description:
(Update) Update Figure 17.1-6 to reflect'the current NEO organizational structure and reporting responsibilities Justification: , The change is consistent with FSAR 13.0 and 17.2 and is-in accordance with the current CPSES Quality Assurance Manual. Group: 4 FSAR Change Request Number: 89-725.2 Related SER Section: 17.2: 'SSER6 17.2. SER/SSER Impact: Yes Section 17.2 and Figure 17-1 in SER and/or~SSER #6-are affected by the proposed change. 17.2-14
Description:
(Clarification) State design control process responsibility for Vice President, Nuclear Engineering. ' Justification: To reflect current title and design control process L responsibilities. Reference NEO 1.01 , Group: 4 i , FSAR Change Request Number: 89-631: L SER/SSER Impact: ilo L 17.2-14
Description:
(Editorial) Delete " Appendix 1A(N)" in the first paragraph on Page'17.2-14. Justification: Appendix 1A(N) was inadvertently added in Amendment 77. Appendix 1A(N) is referenced in Appendix 1A(B) on . L ' Page.1A(B)-33, which is consistent with the. format of Section 17.2. Group: 4 FSAR Change Request Number: 89-603.3 SER/SSER Impact: No
~-. - ~___.- __ . _ . . _ . . _ . _ _ . - _ - - _ _ _ .
. Attach:ent -to,TXX-90011 )
January.15, 1990 n
;Page 261 of.304-1 FSAR Page !
(as amended) Description -
]
17-.2 14
Description:
- (Revision) . .
Change Reg Guide 1.28 to 1.33 in the first sentence off 1 Section 17.2.3._ l Justification:- . The appropriate Reg Guide for the operation phase OA
-Program is 1.33 (1.28 is applicable to the designLand construction).. ;
Group: 3 FSAR Change Request Number: 89 727.2 SER/SSER Impact: No - Table 17.2-2 See Sheet No(s):01
Description:
'(Revision) .
Delete Reg.JGuide l.28. Justification: The appropriate Reg Guide for the operation phase OA program is 1.33 (1.28 is applicable to the design and construction). Group: 3 FSAR Change Request Number: 89-727 Related SER Section: 17.3 SER/SSER Impact: Yes
- The proposed change is'not consistent with SER Table 17.1.
Table 17A-1 See Sheet No(s):04
Description:
(Revision) Add information for the PD pump suction stablizer tank. Justification: To correct an inadvertent omission in~the FSAR. .; Group: 3 FSAR Change Request Number: 89 715 g SER/SSER Impact: No Table 17A-1 See Sheet No(s):27
Description:
(Correction) Adds description for the flow orifice plate under the Containment pressure relief. system. Justification: - See description provided for Figure 9.4 6 and page 22-51. Group: 3 FSAR Change Request Number: 89-523.2 Related SER Section: 6.2.3 SER/SSER Impact: No Table 17A-1 See Sheet No(s):29
Description:
(Correction) Changes the seismic category of the electrical area supply units / fans from 'None' to Seismic Category
'II/None'. Also, changes the listing under the Quality ,
Assurance notes from 'None' to ' Note 26,B/None'. i
AttachIent to TXX 90011' JJanuary 15, 1990- j Page 262 of 304 q j FSAR Page ids amended) Description l Justification. . The seismic category of the electrical area supply l l units / fans is changed from 'None' to Seismic Category ; t
'II/None' to reflect-the. referenced Design Basis -d Document. The Design Basis Document classifies.the fans as non-safety.non-seismic;-the same Design Basis. J Document classifies the supply units as Seismic l-Category II. The appropriate references to the table's notes have been determined and added to the Quality-Assurav.ce column for this listing. The applicable l
, notes to the Seismic Category II supply units are the l same as they were prior to FSAR Amendment 77. i Group: 3 FSAR Change Request Number: 89-418 Related SER Section: 17.5 SER/SSER Impact: No i Table 17A-1 See Sheet No(s):34 and'46
Description:
(Update) . Update 17A-1 to indicate the pertinent requirements of the operations quality assurance program. Change the QA note from~"28" to "C" for Spent Fuel Handling Tool, Rod Control Equipment, Rod Position-Indication Containment Cabinets,-and Control Board Demultiplexer. Justification: These items are not Nuclear Safety- Related and had procuerment GA applied during original. procurement by Westinghouse. However, a specifically structured non Appendix B Quality Assurance program will be-instituted during operations. Therefore, in response ' to NRC Ouestion 260,1~.a the' operations OA Nute "C" has been added where the pertinent requirements of the FSAR operational QA program are applicable. These changes were made for consistency in response to NRC's RAI'concerning Amendment 76. Group:14 FSAR Change. Request Number: 89-668 Related SER Section: 17.5 SER/SSER Impact: No Table 17A 1 See Sheet No(s):46.
Description:
-(Correction) List of Quality Assured Structures, Systems and ' Components Justification: The seismic quality requirement for the NSSS process instrumentation and control racks were originally incorporated in the FSAR with a Seismic Category I classification. The racks were' purchased to be installed in an area where during or following a seismic event, the rack could possibly damage equipment required to be functional, although the racks had no _ . 2 _ . _
Attach 2:nt -to TXX-90011 , January 15, 1990 i Page 263 of 304' ! FSAR Page (as _seended)~ Arscription
}
functional requirements themselves.- Based on the intended-installation, the racks were purchased Seismic Category I, for at.the time of purchase.. Seismic
~ Category II designation, as we know it today, was non-existence. However, since this time,'the racks were' -
determined to be not required for the. intended-location, and instead installed in an area where they , would-not affect equipment required to be functional, during or following a seismic event. Thus, scismic mounting or the~ structural integrity of the racks'is not required. Group: 3 FSAR Change Request Number: 89-723.1 Related SER Section: 17.5 SER/SSER Impact: No Table 17A-1 See Sheet No(s):46
Description:
(Addition) List of Quality Assured Structures Systems.and Components < Justification: In-FSAR 0260.1(d), the Staff indicated:that the pressurizer PORV proportional integral derivative (PID) controller should be included in FSAR Table 17A-1. As a result. TU Electric committed to add ~this component to the FSAR. Therefore, the addition:of the PID controller and applicable quality related information to FSAR , Table 17A-1, satisfies 1this commitment. Gruup: 3 FSAR Change Request Number: 89-723.2-Related SER Section:.17.5 SER/SSER Impact: No Table 17A-1 See Sheet No(s):47 <
Description:
(Addition)- l List of Quality Assured Structures Systems and '
- Components - Instrumentation Justification:
- Adds the quality requirements.for the CPSES Core Cooling Monitors and Reactor Vessel Level Indicating System (RVLIS) instrumentation to the table to be consistent with related portionr, of the FSAR.
l-Group: 3 FSAR Change Request Number: 89-671.4 Related SER Section: 17.5 l SER/SSER Impact: No, j Table 17A-1 See Sheet Ho(s):50 i
Description:
(Revision) Add a new QA Note for the Positive Displacement Pump l Suction Stabilizer Tank. l Justification:
, e - ----
4 Attach ent~ to TXX-90011
-January 15', 1990 Page 264 of 304 i
FSAR Page ) j (as amended) Descrintion This OA Note has been added to reflect the correct [ quality assurance requirements for the Positive , Displacement Pump Suction Stabilizer Tank..- The quality-
- requirements meet AMSE Boiler and. Pressure. Vessel. Code l Section III.
Group: 3 : FSAR Change Request Number: 89-715 ; I SER/SSER Impact: No 3B-34, 35 See Page No(s):36.thru 43
Description:
(Update) -! Updated listing of computer _ codes utilized in the analysis of ASME Class 2&3 piping systems, including supports for ASME Class 1, 2 & 3 piping.
~
Justification: Provided updated 2 computer code's brief description, the assumptions, the refrerences used in the program, the extent of its application and method of qualification. Group: 3 FSAR Change. Request Number: 89-600.2 < l Related SER Section: 3.9.1: SSER14 App. A .t' l SER/SSER Impact: No t ( TMI !.A-7 Descripti on:- (Update)' ' Licensed operator training. Justification: The text refers to-training materials which have long i since been updated to reflect changes in the industry: although the basic subject-matter and course topics have not changed, the program has been modernized. Group: 4 FSAR Change Request Number: 89-665-Related SER Section: 22 SER/SSER Impact: No= THI I.C-7, 8
Description:
(Update) Organization updates, a l / Justification: Update the discussion to be consistent with org titles in Chapter 13, Section 1. Group: 4 FSAR Change Request Number: 89 693 Related SER Section: 22 SER/SSER Impact: No - TMI II.B-15 See Page No(s):18 and 25
Description:
(Revision) Deletion of in-line conductivity instrumentation. Justification: > This monitoring system was purchased as a package ! system which was not specifically designed for the post accident conditions-anticipated at CPSES. -This
Attach ent' J to'TXX-90011 January 15. 1990 J Page 265 of 304 ,
]
l
]
l FSAR Page. (as_ amended) Descrintion 1 package system included an in-line conductivity monitor although there is no regulatory requirement to have -' such a monitor.. It has been determined during-testing. 1 that the monitor does not operate under tne conditions. ' anticipated post accident. .Furthermore, experience has shown'that the conductivity cell traps air during . calibration and negatively impacts the. ability'of the i pH monitor to perform-its function. The'in line pH is , a regulatory requirement.and necessary'for adequate post accident sample information. TXX-3612 dated . I 1/18/83, the CPSES Person-Motion Study.._ indicated that ! the use for the conductivity cell was as wne of several s indications to confirm an adequate flush _for the ' sample. _However, the only parameter that is actually'- . used to verify an :tffective flush is the radiation' level at the panel. Conductivity analysis was: included
~in the original .FSAR-description only because it was an available option of the selected system. Since it does not operate at the expected conditions (and thus? '
adversely impacts the preoperational test to demonstrate correct operation) and since it can adversely impact the operation. of the required Lin line ph monitor. the conductivit.y cell is being: deleted. This change has been evaluated under the TV Electric 10CFR50.59 process as described in TXX 89718 dated September 28. 1989. l Group: 2 FSAR Change Request Number: 90 005. l l Related SER Section: 22: -SSER6 22 SER/SSER Impact: Yes SSER 6 Section II.B.3 page 22-9, and CPSES Person-Motion Study transmitted in TXX-3612 dated 1/18/83, ' indicate the system contains an in line conductivity ' monitor. THI II.B-25
Description:
(Correction) Post Accident Sampling Instrumentation - pH i Justification: ' Corrects FSAR text to reflect the correct. display range for pH as specified in the vendor manual. Group: 3-FSAR Change Request Number: 89-671.1-Related SER Section: 22.2 SER/SSER Impact: No THI Table II.B.3-1
Description:
(Revision) Deletion of in-line conductivity instrumentatien. Justification: See justification under TMI II.B 15. l Group: 3 FSAR Change Request Number: 00-005 Related SER Section: 22 s
-- - - - - . - - - - - - - e u , -v
l Attach 2 tnt to TXX-90011 a January 15, 1990 j Page 266 of 304 2 i FSAR Page ! (as amended). Description j I SER/SSER Impact: No -] TMI !!.D-3 Descriptions (Clarification) Clarifies that the loop seal is only insulated on the pressurizer safety valve, not the PORV.- ; Justification:' l Based on the EPRI test reports-and Westinghouse l
- analysis, it is desirable to provide a loop seal L temperature profile similar to that produced in EPRI Test 917. For this reason the safety valve ,
loop seal.is insulated. The PORV loop seal was " cold" in the EPRI test, and to prevent-flashing of the liquid .i in the seal, it is left uninsulated,~ per Westinghouse recommendations. - Group: 4 FSAR Change Request Number: 89-550.1; Related SER Section: II.D.1; -SSER21 , SER/SSER Impact: No I THI II.D-3
Description:
(Clarification) Clarify which loop seals will be insulated to ensure
.that the EPRI Test fluid conditions are enveloped.
Justification: ' The loop. seals upstream of the safety valve inlets.are required to be insulated such that the loop seal: tem-perature is'approximately 300 degrees'F at the valve-inlet, however the PORV loop seals are not required to bg insulated since a cold loop seal with approximately 150 degree F water envelops the EPRI test fluid con-ditions. Group: 4 . FSAR Change-Request Number: 89-550 . . Related SER Section: II.D.1; SSER21 App. AA SER/SSER Impact: No TMI II.E-7, 8 See Page No(s):13
Description:
(Clarification):. , Hodifies the response to Questions la and 2, deal'ing ' with the recommendations contained in Appendix III'to NUREG 0611, by indicating that the loss of main feed-water transients did include consideration of theLloss of non-emergency AC power. Justification: These changes are made to reflect the fact taat, at the-time these responses were written, the term " blackout" 1-was used synonymously with " loss of-offsite power". In fact, as indicated in the original text, it was the loss of offsite power event that was~ analyzed to' help ; i establish the design requirements for coping with loss of main feedwater transients. Group: 4 j FSAR Change Request Number: 89-672.22
Attach:ent to TXX 90011 . January 15,.1990 . Page 267 of 304 l FSAR Page (as amerwied) Descriptiqn Related SER Section: 15.2.2 : SER/SSER Impact: No TMI II.E 8 Description (Correction) :i
, Further modifies the response to Question la, dealing with the recommendations contained in Appendix III to NUREG 0611, by indicating the manner by which'the minimum AFW system flow was established. ;
Justification: These changes are made to provide a description of the current basis for establishing the minimum AFW system } flow requirement. Groups 3 .. FSAR Change Request Number: 89-672.23 Related SER Section: 15.2.2 .. SER/SSER Impact: No THI II.E-13, 14
Description:
-(Editorial)
- Modifies the FSAR section references-provided in the response-to Question 2 dealing with establishing flow requirements for the.AFW system considering just the Loss of Main Feedwater events.
Justification: These changes are made to be consistent with the ad-l ditional scope of the analyses performed-to establish the minimum AFW flow requirements.. Group: 4 FSAR Change Request Number: 89-672.24~
- Related SER Section: 15.2.2 SER/SSER Impact: No a THI II.E-13
Description:
(Revision) Modifies the statement of the purpose.for analyzing the l Loss of Main Feedwater events.by deleting the require-L ment for assuring that no fuel failures occur (since that is inherent in the Condition II event criteria) and adds a requirement regarding water relief. Justification: This change is made to be consistent with Westinghouse acceptance criteria relating to the adequacy of the system design. ' Group: 3. FSAR Change Request Number: 69-672.25 Related SER Section: 15.2.2 SER/SSER Impact: No THI II.E-13, 14 See Page No(s):15
Description:
(Correction)- Further modifies the discussion of the Loss of Main i l Feedwater event and provides-changes to the text ' i describing the analysis of the Main Feedwater Pipe Rupture event.
Attach;ent' to-TXX 90011' j January 15, 1990 Page 268 of 304 > r' : FSAR Page . f (as amended) .Descrintion Justification: . These changes are made to reflect both the current design bases for the AFW system and the current.analy- , sis results for the Main Feedwater-Pipe Rupture event. [ Group: 3 I
^
l FSAR Change Request Number: 89-672.26 Related SER Section: 15.3.6 : SER/SSER Impact: .No , TMI II.E 17
Description:
(Update) . Hodifies the response to Question 3 which deals with
. verifying that the AFW pumps' will supply the necessary flow to the steam generators considering a single; ,
failure, t Justification- . This change is made in order.to delete duplicative text and to update the supply capability for.the turbine- , driven AFW pump so as to agree with the value provided'
'in Amendment 68, as incorporated in'Section 10.4.9.-
Group 3 FSAR Change Request Number: 89-672.27 Related SER Section: 10'4.9 r SER/SSER Impact: No , THI II.E-18 Description (Correction).
-Further modifies the response to Question 3 (see pg.' ,
II.E-17, above) by referring to the sections in Chapter 15 that indicate the AFW flow rates considering single j active failures. I Justification: This change is made.in order to refer--to the appropri-ate sections of Chapter 15 that present the current; analysis assumptions regarding AFW flow rates and ' single active failures. Group: 3 FSAR Change Request Number:.89-672.28 Related SER Section: 15.2.2. SER/SSER Impact: No THI Table II.E.1.1-2
Description:
(Correction) Modifies this table to add an entry for the Main Steam Line Break event and changes-the Station Blackout entry to read " Loss of Non-Emergency AC Power". Justification: These changes are made to incorporate-information supplied elsewhere in the Amendment 78 changes to Section II.E.1. In particular, the justification for replacing the term " Station Blackout" is the same as I described for the changes to'pages IIE-7 and 12. 'l Group: 3 4 FSAR Cher.ge Request Number: 89-672.29 Related SER Section: 10.4.9 i
Attach ent ' to TXX-90011' January 15, 1990 Page 269 of 304' l I FSAR Page (as amended) Description i I SER/SSER Impact:-No TMI Table II.E.1.1-3 See Sheet No(s):01 and 02 l
Description:
(Editorial) l Deletes the entries for the Loss of Feedwater and Main Feedline Break events and refers, instead. to the appropriate FSAR sections which contain.the current information on the assumptions used in the AFW system design verification analyses. Jastification: This change is made to avoid unnecessary duplication of information and to refer to the appropriate FSAR sections that contain the information. Group: 4 FSAR Change Request' Number: 89-672.30 Related SER Section: 15.2.2 SER/SSER Impact: No i TMI Table II.E.1.1-5
Description:
(Editorial) ' Deletes this table in its entirety. Justification: This deletion is made since the.information in the table has already been provided in the appropriate FSAR sections referred to earlier (see Table II.E.1.1-3, sh I and 2, above). Group: 4 FSAR Change Request Number: 89-672.31 Related SER Section: 15.2.2 SER/SSER Impact: No l l TMI III.A-5, 10 See Page No(s):21, 22, 28 ,
Description:
(Update) Response to NRC Action Plan Developed as a Result of the THI-2 Accident - Emergency Preparedness and L Radiation Effects - NRC and Licensee Preparedness l Justification: I Updated THI section to reflect the implementation j of the Safety Parameter Display System (SPDS).
- Group 3 FSAR Change Request Number
- 89-554.1 Related SSER Section: SSER12 22.2 SER/SSER Impact: No THI III.A-10, 15 See Page No(s):19
Description:
(Clarification) Justification: Minor clarifications to description of communication system provide consistent terminology. Group: 4 l FSAR Change Request Number: 88-735.6 I Related SER Section: 9.5.2 SER/SSER Impact: No
]
Attach =nt' to TXX 90011 January 15. 1990 Page 270'of 304 FSAR Page (as amended) Description-TMI III.A-23
Description:
(Update)- . Response to NRC Action Plan Developed as as tesult of
'the THI-2 Accident - Emergency Preparedness and l Radiation Effects HRC and Licensee Preparedness - -i Display Considerations Justification:
TV Electric has-integrated the generic SAS design into i ERFCS. The SAS committee is not intact, thus the ! discussion about the old presentation was deleted. This ' change reflects the current SPDS design and is ' consistent with the-previously submitted CPSES SPDS SAR, Revision 3 (TXX-89531, dated 7/31/89).- . Group: 3. FSAR Change Request Number: 89 554.2 Related SSER Section:~SSER12 22.2 SER/SSER Impact: Yes SSER# 12 Section 22.2. Item I.D.2 should be updated to reflect the CPSES plant specific design. TMI III.A-23 Descriptions (Update) Response to NRC Action Plan Developed as a Result of the TMI-2 Accident - Emergency Preparedness-and-Radiation Effects-- NRC and Licensee Preparedness - General Considerations Justification: Since TV has integrated its generic' SAS-design into its ERFCS. the ERFCS is referenced as meeting the-SPDS ' requirements..Therefore, the references to SAS meeting , the SPDS requirements was deleted. This change is-consistent with the previously submitted CPSES SPDS SAR, Revision 3 (TXX-89531, dated 7/31/89). Group: 3-FSAR Change' Request Number: 89-554.3 Related SSER Section: SSER12 22.2 SER/SSER Impact: Yes SSER# 12 Section 22.2 Item.I.D.2 should be updated to t reflect the CPSES plant specific design. TMI III.A-24, 25 See Page No(s):26, 27
Description:
(Update) l Response to NRC Action Plan Developed as a Result of- l the THI 2 Accident - Emergency Preparedness and Radiation Effects - NRC and Licensee Preparedness - 1 General Considerations j Justification: Since "SAS" refers to a generic design, and has been incorporated into the CPSES ERFCS, references to "SAS" I has been replaced by SPDS to reflect the plant specific , design. This change is consistent with the previously 'l submitted CPSES SPDS SAR. Revision 3 (TXX-89531, l dated 7/31/89). I
3 Attach::nt . to TXX-90011. January 15, 1990 ; Page 271'of 304. [ ' l , ! FSAR Page its amended) Descriptir.n Group 3
- FSAR Chan9e-Request Number:'89 554.4' Related SSER Section: SSER12 22.2 SER/SSER Impact: Yes . . .
SSER# 12 Section 22.2L! tem I.D.2 should be updated to reflect-the CPSES plant specific design.. . THI III.A-25
Description:
-(Correction) l Response to NRC Action Plan Developed as a Result'of the TMI 2 Accident Emergency Preparedness and 7 i I
. Radiation Effects - NRC.and Licensee Preparedness -
Display Contents Justification: Corrects text to reflect that the display for Reactor , Vessel Water Level is provided by status indicators. Group: 3 . FSAR Change Request Number: 89 554.5 - Related SSER'Section: SSER12 22.2 SER/SSER Impact::No THI III.A-25
Description:
(Update) l Response to NRC' Action Plan Developed es.a Result of , the TMI-2 Accident.- Emergency Preparedness.and. L ' Radiation' Effects - NRC and Licensee Preparedness - Display Contents Justification:
.Since the SPDS displays are installed, the two-sentences addressing future developments were deleted.
Group: 3 FSAR Change Request Number:- 89-554.6 , Related:SSER Section: SSER12 22.2 , SER/SSER Impact: No~ l l TMI III.A 25
Description:
(Correction) Response to NRC. Action Plan Developed as a Result of the THI-2 Accident - Emergency Preparedness and l- Radiation Effects - NRC and Licensee- Preparedness - i j Display Contents Justification: Corrects the text to reflect the color sequence 'for the SPDS bar graphs. The correction notes that the bar color will turn " yellow" before it turns red when a parameter is outside_its normal range. This. change is consistent with the previously submitted.CPSES-SPDS SAR, Revision 3 (TXX-89531, dated 7/31/89). Group: 3 FSAR Change Request Number: 89-554.7 Related SSER Section: SSER12 22.2 l
(: L ' Attachment to TXX-50011-
- January 15, 1990 Page 272 of.304 l
FSAR Page (as amended) Descrintion SER/SSER Impact: Yes ' SSER# 12 Section 22.2 Item I.D.2 should be. updated to reflect the CPSES plant specific design. TMI III.A-27
Description:
(Update) ' Response to NRC Action' Plan Developed as a Result of' the TMI-2 Accident _ Emergency Preparedness and-Radiation Effects. NRC and Licensee Preparedness - Validation and Verification , i Justification: Validation'and verification activities have been , performed'on the CPSES SPDS'per the guidance provided-in IEEE-730, NSAC-39, and ANSI /ANS 10.4, 1987. Thus, discussions of historical SAS development future-design specifications, and parameter selection were appropriately deleted. l Group 3 FSAR Change Request Number: 89-554.8 Related SSER Section: SSER12 22.2 SER/SSER Impact: No ' l TMI III.A 29
Description:
(Additton) Response to NRC Action Plan Developed as a Result of the THI-2 Accident'- Emergency Preparedness and Radiation Effects - NRC and Licensee' Preparedness - Integrated ERF Computer System - General Description Justification: Revised text to include an additional CRT which is l available on the main control board. This CRT is- . equipped with a manual' switch, such that.SPDS or Plant
- Process Computer parameters can be displayed. -
Group: 3 FSAR Change Request Number: 89-554.9 Related SSER Section: SSER12 22.2 SER/SSER Impact: No THI 111.0 4
Description:
(Revision) _ l / In the response to NRC Action Plan item III.D 1.1, mod- ' ) ifies the subsection.," Limiting Leakage Value", to spe - _ l- cify that the limiting.value for those portions-of the-l RHR. CS, SI, CVCS and PASS systems outside containment-will be established at a maximum of 1 gpm/ Unit. l Justification: , ! :This change is made to be consistent with the leak rate assumed for Engineered Safety Features equipment in calculating the LOCA dose received by control room occupants, as described in TU Electric letter TXX-89692 dated.10/20/89 and described elsewhere in Amendment 78. Group: 3 FSAR Change Request Number: 89-718 Related SER Section: 22.2 )
-_ - _ _ ~ _ - . _ . , _ . - _. ..__ - .. , .
P Attachm:nt to TXX-90011 i January 15, 1990 s Page 273 of 304 l t i FSAR Pope , f.as amended) Descrintion f i SER/SSER Impact: Yes ! As mentioned in connection with Amendment 76 (see Change Request No. 89 210.05). NRC Action Plan Item l
!!!.D.1.1 of SER 22.2 (see $$ER 4. pg 22 3) should be !
revised. in this case, to indicate that the limiting l 1eakage value is established at a maximum of 19pa/ Unit. i TH! !!!.D 9 See Page No(s):10 l Descriptions (Update) ! Revisions to Section !!!.D.3.4.2 i Justifications i This revision corrects various references in Section .
!!!.D.3.4.2. t Group 4 FSAR Change Request Number: 89-434.2 j Related SER Sections !!!.D i SER/SSER Impact: No l TMI !!!.D 9 See Page No(s):and 10 '
Descriptions (Update) , Correction of text references in Section !!!.D.3.4.2 * (a). (k), and (1) t Justifications ! An FSAR reference and 2 references to the Emergency ; Plan are corrected. Group: 4 I FSAR Ch6nge Request Number: 89 434.2
^
Related SER Section: !!!.D.3 SER/SSER Impact: No TM! !!!.D-10 Descriptions (Update) . Use of K! During a Plant Emergency ; Justification:
- FSAR is updated to reflect completion of review of the use of K! during a plant emergency. The revision refers to Section 8.5.3 of the Emergency Plan for details of K! use and quantity stocked.
Group: 4 . FSAR Change Request Number: 89 434.1 Related SER Sections !!!.D 3 SER/SSER 1mpact: No O&R 010-1b Descriptions (Clarification) $ Clarified response to question concerning " Break Exclu-sion" region identification. Justification: Response was clarified to provide consistency and com-pleteness of the response. , Group: 4 i FSAR Change Request Number: 89-139.1 Related SER Section: 3.6.2: SSER6 3.6.2 SER/SSER Impact: No i
Attachment to TXX 90011 $ Jan:ary 15, 1990 Page 274 of 304 FSAR Page i (as amended) Descrintion '{ O&R 010 14
Description:
(Clarification) , Clarified response to question concerning "8reak Exclu- l sion" region identification. , Justification: Response was c)arified to provide consistency and com-pleteness of the response. l Group: 4 i FSAR Change Request Number: 89 139.2 Related SER Section: 3.6.2 $$ER6 3.6.2 ! ! SER/SSER Impact: No ; i 0&R 010 28
Description:
(Correction) Environmental impact of an MSLB with superheat releases i Justification: ;
- In FSAR Amendment 76, part of the licensing basis for the MSLB superpipe issue was omitted. The omission !
s contained key assumptions for the analysis of superpipe
- cracks which is necessary to avoid future misinterpretation regarding single failure and loss of offsite power as they relate to superpipe. This i change was evaluated under the TU Electric 50.59 {
process as described in TXX 89718 dated 9/28/89. } Group: 2 i FSAR Change Request Number: 89 773.1 l Related SSER Section: SSER12 3.11.6 4 SER/SSER Impact: No f 4 0&R 010 28a, 28b See Pa9e No(s):28c Descriptions (Correction) Environmental impact of an MSLB with superheat releases , Justification: Corrects room numbers associated with the MSLB stiperpipe compartments to be consistent with design drawings and documents. This change was evaluated under the TU Electric 50.59 process as described in TXX 89718, dated 9/28/89. : j Group 3 FSAR Change Request Number: 89 773.2 i Related SSER Section: SSER12 3.11.6 l SER/SSER Impact: No ! I l O&R 010 28g Description (Correction) i Environmental impact of an MSLB with superheat releases l Justification l Revised the description of the PORV pressure transducers to clarify their functional requirements and to reflect their correct location. This change was evaluated under the TU Electric 50.59 process as described in XX-89718, cated 9/28/89. Group 3 FSAR Change Request Number: 89-773.3
'+' y- pwa- w w. ,-y, . , , , _ ..,,-m,.,.y +,,w,yq,., w,g, , , _ g,g.., ,y s --,& ,e, ,.p.-,-y *.
Attachment to TXX 90011 . January 150 1990 i Page 276 of 304 l l F3AR Page : 3 (as amended) Descristien l Related SSER Section: $$ER12 3.11.6 ! SER/SSER 1mpact: No ! O&R 010 28g Description (Correction) f Environmental impact of an MSL8 with superheat releases Justifications : Revised the description of the Auxiliary Feedwater ! Containment isolation valves to clarify their ! functional requirement. Amendment 77 previously noted } that these valves were postulated as required to close i which was incorrect. This change was evaluated under the TU Electric 50.59 process as described in TXX 89718. dated 9/28/89. Group: 2 FSAR Change Request Number: 89 773.4 i , Related $$ER Section: $$ER12 3.11.6 I SER/SSER Impact: No , 0&R 010 28h Descriptions (Correction) Environmental impact of an MSL8 with superheat releases ; 1 Justification: '
- Revised the description for the auxiliary feedwater ,
flow indication to reflect that.although not required. l these indicators must not fail in a manner detrimental ! to plant safety. This change was eyeluated under the i TU Electric 50.59 process as described in TXX 89718 dated 9/28/89. ! Groups 3 i FSAR Change Request Number: 89 773.5 , , Related $$ER Section: SSER12 3.11.6 l SER/SSER Impact: No r i O&R Figure 010.20 2 See Sheet No(s):01, 02, 03, 04 Descriptions (Correction) Environmental impact of an MSL8 with superheat releases Justification: Corrects room numbers associated with the MSLB
< superpipe compartments to be consistent with design . I drawings and documents. This change was evaluated under the TV Electric 50.59 process as described in ;
TXX 89718. dated 9/28/89. ; Group: 3 FSAR Change Request Number: 89 773.6 ' Related SSER Section: SSER12 3.11.6 - SER/SSER Impact: No ; i Q&R 022 25 Descriptions (Correction) Justification: 1 Revised the reponse to reference the applicable FSAR section. Group: 4 j FSAR Change Request Number: 89-443.1 !
i i Attache;nt . to TXX 90011 l January 15, 1990 j Page 276 of 304 i FSAR Page (as amended) Descrintion l Melated SER Section: 7.3 1 SER/SSER Impact: No i O&R 022 51 Description (Correction) : Deletes the time restriction on the Containment ' pressure relief valves and adds a description on the l' 3" restrictive flow orifice plate. Justification:
- The allowed accumulative opening time for the 18 inch !
- containment pressure relief discharge isolation valves' f is changed to be unlimited. This is based on redesign i of the system which limits the amount the valve will i I open and adds an orifice plate which. changes the ,
effective diameter of the valves to 3-inches:from the I combination of these modifications. Therefore, with , the valves essentially being equivalent to a 3 inch : valve and being capable of closure to meet the accident ! analysis assumptions any time, restrictions do not apply. Also, this change was identified and accepted
- by the staff as part of Technical Specifications ,
changes in TXX 88780 dated 11 16-88 Attachment 9 pages , 4A and 13 of 42. ! Groups 3 ! i FSAR Change Request Number: 89 523.3 i Related SER Section: 6.2.3 SER/SSER Impact: Yes l SER Section 6.2.3 page 6 11, 3rd paragraph and Section 22.2(!!.E.4.2), page 22-54, 7th paragraph are not consistent as a result of this change.
- Q&R 022 51
Description:
(Clarification) f Clarifies that the debris screen is designed to . Seismic Category !! Criteria in consistent with FSAR > Table 17A 1, Sheet 27. Justification , The debris screen is installed on a Class 5 piping for which the highest seismic categroy class the screen 4 could be rated is Seismic Category !!. . Group: 3 ' FSAR Change Request Number: 89 523.4 , SER/SSER Impact: No 0&R 022 55
Description:
(Clarification) i Clarifies response to 022.22 to state that the NRC-accepted " mass plot method" of ANSI /ANS 56.8 1987 is ! currently being used at CPSES. . Justification: - This change is being made for consistency with FSAR section 3.8.1.7.2 and Table 14.2 2 sheet 59. This LDCR
- resolves a concern identified during the NRC structural audit at CPSES during Sept. 6-7, 1989.
Group: 4
. _ __ _ _ _ . . _ ~ _ _.
Attachment . to TXX 90011 January 150 1990 ; Page 277 of 304 FSAR Page (as amended) Descrintion i FSAR Change Request Number: 89 651.6 Related SER Section: 3.8.1: SSER12 6.2.5 , SER/SSER 1mpact: Yes ; CPSES calculates the leakage rates for the ILRT using ! the mass / plot method of ANSI /ANS 56.8 1987.
- The 1987 version (for mass plot method) has been accepted by the NRC in the Federal Register. Volume 53. '
No. 220. page 43890. ; 0&R 032 in Description (Correction) Replaces the response to the RESAR 3 request to provide ! pressurizer relief and safety valve capacities when discharging water liquid by referring to the response i to Question 0212.75 (see pg. 212-139 below). Justification: . l This change is made to provide a reference to more , recent information. Group: 3 i FSAR Change Request. Number: 89 672.17 i Related SER Sections 5.3 ' SER/SSER Impact: No O&R 032 2
Description:
(Correction) Environmental Qualification 4 Justification: In a previous amendment, several tables in Appendix.3A were consolidated into Table 4 1. Change makes correct reference to this table. Groups 3 FSAR Change Request Number: 88 843.2 t Related SSER Section: SSER6 3.11.3 i SER/SSER Impact: No l O&R 032 2 Description (Clarification) ' Environmental Qualification Justification: i Clarifies that Table 4.1 is limited to safety related
, equipment located in a potentially harsh environment l (i.e. does not include mild environment) i Group: 3 I FSAR Change Request Number: 88 843.3 Related SSER Section: SSER6 3.11.3 SER/SSER 1mpact: No Q&R 032-2 See Page No(s):35 and 35a
Description:
(Update) ; l Environmental Qualification l Justification: Update responses to reflect the current environitental qualification program and the pertinent environmental qualification FSAR sections. Group: 3
i Attachment to TXX-90011 January 15, 1990 Page 278 of 304 l FSAR Page l Cas_amehdad) Descrintion ! FSAR Change Request Number: 88 843.1 t Related SSCR Section: SSER6 3.11.3 l SER/SSER Impact: No !
- Q&R 032 41 Descriptions.(Correction) ;
Justifications ! Revised the question and reponse to reference the ' l applicable FSAR section. l Group: 4 . FSAR Change Request Number: 89-443.2
?
Related SER Section: 7.2 SER/SSER Impact: No Q&R 032 42 Descriptions (Correction)- Justification: + Corrects the total number of RCS wide range pressure ' transmitters to reflect that there are four instead of two. Also reflects the correct model numbers for the Rosemount and Veritrak transmitters. Group: 4 FSAR Change Request Number: 89 443.3 Related SSER Section: SSER6 3.11.4 SER/SSER Impact: No 0&R 032 45
Description:
(Correction) Justification: l Revised response to reference the correct sub para. l which describes reactor trip on turbine trip circuit isolation criteria. 1 Group: 4 FSAR Change Request Number: 89 443.4 Related SER Section: 7.2 SER/SSER 1mpact: No O&R 032 47
Description:
(Correction) Justification: Revised the response to reflect the applicable FSAR
, section for containment isolation valve position indicators.
Group: 4 FSAR Change Request Number: 89 443.5 Related SER Section: 7.3 SER/SSER Impact: No Q&R 032-49 Descriptions (Correction) Hydrogen Purge System Justification: Correction of references that were changed in a prior amendment, but never reflected in this section. Group: 3 FSAR Change Request Number: 89 298 Related SER Section: 7.3.1 2
i Attachment to TXX-90011 January 15. 1990 1 Page 279 of 304 I FSAR Page ; (as amended) Descrintion - SER/SSER impact: No ; 0&R 032 126, 127 Description (Correction) I Level Measurement Errors Due to Environmental Temperature Effects on Level Instrument Reference Legs Justification: l Added the term " nominal" to reflect that the dimensions i of the Unit 1 and Unit 2 steam generators is an ! approximate length. The as built dimensions vary from }' steam generator to steam generator. Therefore. references to steam generator taps, height, etc. ( represent nominal values. ; Group: 3 i , FSAR Change Request Number: 89 697.1 t l Related SER Section: 7.3.2.2 SER/SSER lapact: No l O&R 032 127, 129
Description:
(Update) [ Level Measurement Errors Due to Environmental , Temperature Effects on Level Instrument Reference legs , Justifications : The containment temperature and pressure values used in ! calibrating the level indication system has been ! revised based on revised calculations in the CPSES i Scaling Manual and Power Capability profiles. At SOE pressure point for the steam generator, the i corresponding system pressure is approximately , 1053 psia, which corresponds to approximately 70% 1 power, which is noted by this change. I Group 3 FSAR Change Request Number: 89 697.2 l Related SER Section: 7.3.2.2
- SER/SSER 1mpact
- No i O&R 032-129
Description:
(Correction) Level Measurement Errors Due to Environmental Temperature Effects on Level Instrument Reference Legs- >
< Justification:
Corrected the ecuation which calculates the level error due to the changes in coolant density with respect to changes in pressurizer and steam generator pressure, , The term that is being deleted is associated with calculating the magnitude of the bias for reference f leg heatup error instead of the density changes. The reference leg heatup error is calculated separately. Thus, the term was deleted from the equation. ; Group: 3 FSAR Change Request Number: 89-697.3 Related SER Section: 7.3.2.2 SER/SSER Impact: No l l
Attachment to TXX 90011 l January 15. 1990 i Page 280 of 304 l I FSAR Page l (as _ amended ) Descrintion l 0&R 032 131
Description:
(Correction) Level Measurement Errot's Due to Environmental , Temperature Effects on Level Instrument Reference Legs Justification: l Deleted the reference to post accident radiation effects on the steam generator low low setpoint , transmitter. Originally for a feedline break, i transmitter errors were attributed to post accident temperature and radiation effects. However, analysis ! does not support the radiological releases for a feedline break. Thus, the reference to radiation , effects on transmitter error was deleted. ! Group 3 l
- FSAR Change Request Number
- 89 697.4 Related SER Section: 7.3.2.2 i SER/SSER 1mpact: No 1 O&R 032 132 Description (Revision)
Level Measurement Errors Due to Environmental ; Temperature. Effects on Level Instrument Reference Legs j l Justification: Revised the text to reflect that the bounding containment temperature used to calculate the error attributed to reference leg heatup error is 345 degrees F. This value is conservative and represents ! the peak containment temperature for a steamline break. l In addition, the 345 degrees F bound the anticipated ; conditions of a feedline break. The resulting , I calculated reference leg heatup error based on the - I 345 degrees F is +13.75
- Groups 3 <
FSAR Change Request-Number: 89 697.5 Related SER Section: 7.3.2.2 SER/SSER Impact: Yes SSERf6 reflects the feedline break as the bounding conditions for calculating the reference leg heatup error. As a result, the peak containment temperature
< (227 degrees F) and the reference leg heatup error for '
this break are no longer valid. O&R Figure 032 103 See Sheet.No(s):01 and 02 ;
Description:
(Update) ' Level Measurement Errors Due to Environmental Temperature Effects on Level Instrument Reference legs- l Justification: - l Updated Figures 1 and 2 to reflect the reference leg height and the revised. containment temperature and pressure values used in calibrating the steam generator level indication system. Group: 3 FSAR Change Request Number: 89-697.7 .i Related SER Section: 7.3.2.2 i
.. ., , - - , - . . - , ~ -- .- . - - -
k Attachment to TXX*90011 January 15. 1990 l Page 281 of 304 l 1 FSAR Page (as_ amended) Descrintion f SER/SSER Impact: N3 i 06R Table 032.110 1 See Sheet No(s):02 Descriptions (Update) l Accident Nonitoring Instrumentation RVLIS l Justification: Update to the Table to reflect that the RVLl$ ; instrumentation is installed and operable. Groups 3 . FSAR Change Request Number: 89 551 Related SSER Section: SSER6 22.2 SER/SSER Impact: Yes ; SSER #6 Section 22.2, item !!.F.f. still shows the ^ CPSES implementation of RVLIS outstanding. This section 1 should be revised to reflect that the work is complete. i 0&R Table 032.110 1 See Sheet No(s):02 , Descriptions (Update) Conformance to Reg Guide 1.91, Rev. 2 Justification: A fourth wide range pressure transmitter (PT-3616) has a been added to the CPSES reactor coolant system. The additional transmitter is utilized as one of the three required accident monitoring channels for RCS because of the improved instrument accuracy. This transmitter replaces the existing transmitter (PT 405) as an accident monitoring channel. However PT 405 is still being utilized for a non accident monitoring function. Thus, Table 032-110 1 is being updated to reflect the change in tag numbers, 1 Groups 3 FSAR Change Request Number: 89 695.5 Related SSER Section: SSER12 APP T SER/SSER Impact: No O&R Table 032.110 1 See Sheet No(s):04 Descriptions (Correction)
< Conformance to Regulatory Guide 1.97, Revision 2 Justification i
i Corrects the upper range for the containment radiation high range accident monitoring instrumentation. The t upper range of 10E7 R/hr meets the range requirements of the Reg Guide for this variable. Group: 3 FSAR Change Request Number: 89 608.9 Related SSER Section: SSER12 APP T i SER/SSER Impact: No
. _ _ _ _ . . ._ , _ _ _ _ _ _ _ _ ~ , _ _ _ _ ,
Attachment to TXX 90011 f January 15, 1990 l Page 282 of 304 ; f i FSAR Page . (as amended) Descrintion 0&R Table 032.110 1 See Sheet No(s):04 and 18 Descriptions (Correction) Post Accident Sampling Instrumentation pH Reg Guide 1.97 , Justification t Corrects FSAR text to reflect the correct display range for pH as specified in the vendor manual. Groups 3 FSAR Change Request Number: 89 671.3 Related SER Section: 22.2 l SER/SSER Impact: No 06R Table 032.110 1 See Sheet No(s):06 Descriptions (Revision) l I Accident Monitoring l Justification: The accident monitoring variable "CCW Header Temperature" instrument range has been revised. The new range is 30 150 degrees F. This is a deviation : [ from Reg Guide 1.97, Rev. 2, as noted in'this Table. l l For additional details see FSAR change description Table 7.5 7, sheet 11, for CCW Header Temperature. This change was evaluated under the TU Electric 50.59 process as described in TXX 89718, dated 9/28/89. Group: 2 FSAR Change Request Number: 89 862.3 Related SSER Section: SSER12 App T SER/SSER Impact: Yes The SER/SSER does not reflect CCW Header Temperature as ! a deviation. O&R Table 032.110 1 See Sheet No(s):06
Description:
(Correction) Conformance to Reg Guide 1.97 Rev. 2 , Justifications SI Accumulator Tank Level instruments are seismically l qualified for pressure boundary integrity and are I e seismically mounted as delineated by Notes'7 and 8. Group 3 i FSAR Change Request Number: 89 553.3 Related SER Section: 7.5 ; SER/SSER Impact: No Q&R Table 032.110 1 See Sheet No(s):08 Descriptions (Correction) Conformance to Regulatory Guide 1.97 Revision 2 Justification: Corrects Table to reflect that the power supply for i reactor coolant pump status is non 1E. This instrument is designated as a Category 3 instrument which per Reg ! Guide 1.97 is acceptable. Group: 3
Attachment to TXX 90011 ! January 15, 1990 ! Page 283 of 304 l l FSAR Pepe (as amended) Descrintion l FSAR Change Request Number: 89 608.10 Related SSER Section: SSER12 APP T ( t SER/SSER Impact: No I i Q&R Table 032.110 1 See Sheet No(s):09 i Descriptient (Update) ! Conformance to Regulatory Guide 1.97, Revision 2 i Justification ; Based on NRC request, in TXX 89253, dated 5/19/89, TU Electric committed to expand the utilization of the j , steam generator wide range level instrumentation to a i l Type B Category 1 accident monitoring variable, and ; update the FSAR in a future amendment to reflect this designation. This change satisfies the requirements of Reg Guide 1.97 Revision 2. ; Groups 3 FSAR Change Request Number: 89 608.11 : l Related $$ER Section $$ER12 APP T I SER/SSER Impact: No i Q&R Table 032.110 1 See Sheet No(s):13 Description (Revision) i Accident Monitoring Justification:
- The accident monitoring variable "CCW Header i Temperature" instrument range has been revised. The new range is 30 150 degrees F. This is a deviation from Reg Guide 1.97, Rev. 2 even though the new range envelopes the maximum anticipated ranges. For !
additional details, see the description for Table 7.5 7 ! sheet 11 for "CCW Header Temperature." This change i was evaluated under the TU Electric 50.59 process as described in TXX 89718, dated 9/28/89. Group: 2 FSAR Change Request Number: 89 862.2 Related SSER Section: SSER12 App T SER/SSER 1mpact: Yes t The SER/SSER does not reflect CCW Header Temperature as a deviation. . t Q&R Table 032.110 1 See Sheet No(s):15
Description:
(Update) ' Conformance to Regulatory Guide 1.97, Revision 2 l Justification: l Revised the variable function and category for the j control room area radiation monitors from " Key-E2" to
" Backup E3." TU Electric indicated in TXX 89253, dated 5/19/89, that fixed area monitors in the CPSES accident monitoring design are utilized as backup monitors to portable monitors. Portable monitors are considered to be more reliable for detecting localized areas of '
higher contamination.
l l Attachment to TXX 90011 January 15. 1990 ; Page 284 of 304 1 i FSAR Page ! (as amanded) Descrintion i Group: 3 ! FSAR Change Request Number: 89 600.12 i Related SSER Section: SSER12 APP T l l SER/SSER 1mpact: Yes l SSER #12 does not reflect the control room area j monitors as a deviation from Reg Guide 1.97. Rev. 2. - i ! 0&R Table 032.110 1 See Sheet No(s):17 _ ! , Description (Clarification) . l Revises temperature range for atmospheric stability. ! ! Justifications Clarifies the temperature range from " 5 to +5" to
" 5 to +15" degree F to provide consistency with a revision to T2.3 34 submitted in a previous amendment.
These changes to the Delta Temperature calibration range will eliminate rollover problems in recording i instruments and ensure valid meteorological data collection. Group: 4 , FSAR Change Request Number: 89 566.2 Related SER Section: 2.3 SER/SSER 1mpact: No O&R Table 032.110 2 See Sheet No(s):01 '
Description:
(Addition) Conformance to Reg Guide 1.97, Rev. 2 Justification: Added RHR heat exchanger inlet temperature as an ; accident monitoring 03 Backup variable. In lieu of the required containment sump water temperature variable, this variable in conjunction with containment atmospheric temperature and RHR heat exchanger outlet temperature variables, are considered adequate to monitor containment cooling. RHR heat exchanger inlet temperature is reflected in SSER# 12 Appendix T as part of the CPSES design. In a telephone conference call between the NRC and TU Electric (9/27/89), the
< difference between SSER# 12 and the CPSES design was noted. TU Electric has since added this variable to the CPSES design.
l Group: 3 FSAR Change Request Number: 89-695.6 l Related SSER Section: SSER12 APP T SER/SSER Impact: No O&R Table 032.110 2 See Sheet No(s):01, 11 and 12 Descriptions (Correction) - Conformance to Regulatory Guide 1.97, Revision 2 Justification: Corrects the upper range for steam generator blowdown, liquid waste effluent and turbine building drains i radiation accident monitoring instrumentation. These >
Attachment to TXX 90011 l January 15. 1990 l Page 285 of 304 ; FSAR Page , (as amended) Descrintion i monitors are not required by the Reg Guide, but are I designated as accident monitoring instrumentation based ; on the CPSES plant specific design. Although the ; change to the upper range is conservative, it has no direct correlation to the Reg Guide. ; Group: 3 t FSAR Change Request Number: 89 608.13 i Related SSER Section: SSER12 APP T SER/SSER Impact: No Q&R Table 032.110 2 See Sheet No(s):11 Description (Correction) Conformance to Regulatory Guide 1.97 Revision 2 ! Justification: Delete the E0 and 50 requirements for the safety ! chilled water flow instrumentation and added Note 7 for clarity. This instrumentation is a designated CPSES nonsafety accident monitoring variable'that is not
- required per the Reg Guide. However, the CPSES design requires that this instrument be designed to maintain ;
pressure boundary integrity. l Group 3 , FSAR Change Request Number: 89 608.14 Related $$ER Section: SSER12 APP T SER/SSER 1mpact: No O&R Table 032.110 3 See Sheet No(s):01 Descriptions (Correction) Conformance to Regulatory Guide 1.97. Rev. 2 Justification: ; Notes 7 and 8 were incorrectly deleted in a previous ' FSAR amendment. These Notes are added to reflect those accident monitoring instruments that are seismically mounted and seismically qualified for pressure boundary integrity. Group: 3 FSAR Change Request Number: 89-553.4 Related SER Section: 7.5 SER/SSER Impact: No 0&R Table 032.110 4 See Sheet No(s):02. 03. 04 and 05 Description (Correction) Conformance to Reg Guide 1.97. Rev. 2 l Justification: Based on a telephone conference call between the NRC and TV Electric (9/27/89), two of the line items in T032.110 4 (deviations) were identified as not a deviation from the requirements of Reg Guide 1.97 Rev. 2. The variables include. SI accumulator isolation valve status (instrument range) and CR vent damper position (instrument range) In addition, several of the monitors used to assess the magnitude of 1
Attachment to TXX 90011 i January 15, 1990 j Page 286 of 304 i FSAR Pope 1 (as amended) Descrintion l l l radioactive material releases, per the Reg Guide. ; require portable instrumentation or grab samples to i make the analysis. For these variables, it seems l unlikely that the intent of the Reg Guide is to require ! a direct display of the results in the control room. 1
- For this reason, the display deviations for accident sampling and environs radiation, in addition to the ;
variables listed above, have been deleted from ! l Table 032.110 4. Groups 3 6 FSAR Change Request Number: 89 695.7 Related SSER Section: SSER12 APP T SER/SSER Impact: No Q&R Table 032.110 4 See Sheet No(s):03 , Description (Correction) Conformance to Regulatory Guide 1.97, Revision 2 , Justification: In TXX 89253, dated 5/19/89, the NRC identified a discrepancy between FSAR Tables for pressurizer level instrument range. This change updates the FSAR to reflect the correct instrument range and resolves the Table discrepancy. , ! Group: 3 FSAR Change Request Number: 89 608.15 , Related SSER Section: SSER12 APP T SER/SSER Impact: No O&R Table 032.110-4 See Sheet No(s):03 , Description (Update) ' Conformance to Regulatory Guide 1.97, Revision 2 Justification: Deleted steam generator water level (WR) as a deviation ' since it no longer applies. TU Electric committed to expand the utilization of.this instrumentation to a Type B Category 1 accident monitoring variable. Group: 3
, FSAR Change Request Number: 89 608.16 Related SSER Section: SSER12 APP T SER/SSER Impact: No Q&R Table 032.110 4 See Sheet No(s):05 Description (Clarification)
Revises temperature range for atmospheric stability. ' i Justification: Clarifies the temperature range from " 5 to +5" to
"-5 to +15" degree F to provide consistency with a revision to T2.3 34 submitted in a previous amendment.
These changes to the Delta Temperature calibration range will eliminate rollover problems in recording instruments and ensure valid meteorological date : collection.
1 Attachment to TXX 90011 ! January 15. 1990 i Page 287 of 304 ' FSAR Page (as amended) Descrintion l l Group: 4 ; FSAR Change Request Number: 09-566.2 : l Related SER Section: 2.3 SER/SSER Impact: No j O&R Table 032.110 4 See Sheet No(s):06 ' i Descriptions ( Addition) [' Conformance to Reg Guide 1.97. Rev. 2 Justification: Added high level radioactive liquid tank level as a t , deviation to the Reg Guide. For instrument range, the ; i Reg Guide specifies top to bottom and the CPSES design i specifies 0 - 100% whereby the 0 and 100% taps are not exactly at the top and bottom of the tank. Although a 4 deviation, the range specified in the CPSES design is < considered acceptable since alarms, indication, etc.. setpoints are within the 0 100% band. This deviation I was noted by the NRC in the telephone conference call (9/27/89) regarding the CPSES accident monitoring design. j Groups 3 l FSAR Change Request Number: 89 695.9 Related $$ER Section: SSER12 APP Y SER/SSER Impact: Yes SSERf 12 Appendix T does not reflect this variable as a deviation for Instrument Range. Q&R Table 032.110-4 See Sheet No(s):06
Description:
(Addition) Conformance to Reg Guide 1.97, Rev. 2 Justification: Added plant environs radioactivity as a deviation to the Reg Guide for instrument range. CPSES does not have a portable multichannel vamma-ray spectrometer whereby release assessments or an analysis can be done locally. Instead, field teams are dispatched to collect samples, which are transported to an onsite lab facility 4 where gamma spectroscophy equipment is used to l analyze the sample. This deviation was noted by the NRC in the telephone conference call (9/27/89) regarding the CPSES accident monitoring design. Group: 3 FSAR Change Request Number: 89 695.10 Related SSER Section: SSER12 APP T SER/SSER Impact: Yes SSERf 12 Appendix T does not list plant and environs radioactivity 3s a deviation for Instrument Range. I
I
- Attachment to TXX 90011 January 15, 1990 l Page 288 of 304 FSAR Page (as amended) Descrintion O&R Table 032.110 4 See Sheet No(s) 06 Descriptions ( Addition)
Conformance to Reg Guide 1.97, Rev. 2 Justification: Revised the variable function and category for CR area radiation from " Key-E2* to " Backup E3." TV Electric indicated in TXX 89253, dated 5/19/89, that area fixed monitors in the CPSES accident monitoring design, are utilized as backup monitors to portable monitors. Portable monitors are considered to be more reliable for detecting localized areas of higher contamination. However, using these monitors as "E3's" is a deviation i from the Reg Guide. Thus, a line entry for this ! variable was added to the Table. I Group 3 FSAR Change Request Number: 89-695.8 Related SSER Section: SSER12 APP T l SER/SSER Impact: Yes SSER# 12 Appendix T does not reflect the CR area radiation monitors as a deviation for Category. 0&R Table 032.110-5 See Sheet No(s):01 Description (Revision) Accident Monitoring Justification: The accident monitoring variable "CCW Header Temperature" instrument range has been revised. The new range is 30 150 degrees F. The justification for this deviation from Reg Guide 1.97, Rev. 2, is noted in this Table. For additional details, see FSAR description, Table 7.5-7, sheet 11. This change was evaluated under the TU Electric 50.59 process as described.in TXX-89718, dated 9/28/89. Group: 2 FSAR Change Request Number: 89 862.4 Related SSER Section: SSER12 App T SER/SSER lapact: Yes The SER/S$ER does not reflect CCW Header Temperature as a deviation. O&R Table 032.110-5 See Sheet No(s):03
Description:
(Addition) Conformance to Reg Guide 1.97, Rev. 2 Justification: Added RHR heat exchanger inlet temperature to Note 13. This is an accident monitoring 03 Backup variable. In lieu of the required containment sump water temperature variable, this variable in conjunction with containment atmospheric temperature and RHR heat exchanger outlet temperature variables are considered adequate to measure containment cooling. SSER# 12 reflects this variable as part of the CPSES accident monitoring 1
i Attachment to TXX 90011 ! January 15. 1990 [ Page 289 of 304 ; FSAR Page [ (as amended) Description ; design. Group: 3 > FSAR Change Request Num0er: 89 695.11 : Related SSER Section: $$ER12 APP T : j SER/SSER Impact: No j 0&R Table 032.110 5 See Sheet No(s):03 and 06
Description:
(Update)' Cenformance to Regulatory Guide 1.97. Revision 2 , Justification:
- Deleted Notes ~8 and 28 which described TU Electric's .
utilization of the steam generator water level (WR) , instrumentation prior to the instrumentation being considered as a Type B1 variable. These notes no longer ! apply. ' Group 3 FSAR Change Request Number: 89 608.17 Related SSER Section: SSER12 APP T , SER/SSER Impact: No 0&R Table 032.110 5 See Sheet No(s):04
Description:
(Update) Conformance to Reg Guide 1.97. Rev.-2 ; Justification: Updated Note 17 to reflect that the requirement for radiation exposure meters. which was postponed l indefinitely in Rev. 2 of the Reg Guide. has since been t i superseded and deleted from Rev. 3 of the Reg Guide. Group 3 FSAR Change Request Number: 89 695.12 Related SSER Section: SSER12 APP T SER/SSER Impact: No l 0&R Table 032.110 5 See Sheet No(s):06
Description:
(Addition) Conformance to Reg Guide 1.97. Rev. 2 . Justification: 4 Added Note 29 to explain the CPSES process'for assessing plant and environs radioactivity using multichannel gamma-ray spectrometer. The assessment and/or analysis is not performed locally. but samples are collected and analyzed in a lab.- , Group: 3 , FSAR Change Request Number: 89-695.13 Related SSER Section: SSER12 APP T SER/SSER Impact: No-0&R Table 032.110-6 See Sheet No(s):03
Description:
(Correction) Conformance to Reg Guide 1.97. Rev. 2 Justification: ; Revised the description for Type A. B and C. Category i
. - _ . _ _ - s. . - _ __ ._
t
! Attachment to TXXo90011 January 150 1990 ,
Page 290 of 304 l FSAR Page (as amended) Descrintion l 1 and 2 accident monitoring instrument identification. ! As denoted in TXX 89253, dated 5/19/89, these ' instruments are uniquely identified with the exception i of steam generator blowdown, condenser offgas and plant vent stack radiation monitors, and containment - isolation valve (CIV) status indication. The radiation monitors are part of a computer based system in which ; information is displayed on demand on a CRT and the i CIV status indication is provided by control switches i and monitored light boxes located on the main control board. Group: 3 . FSAR Change Request Number: 89 695.14 : Related SSER Section: SSER12 APP T i SER/SSER Impact: No j O&R 040 2, 5
Description:
(Correction) Safety Equipment Located Below the Flood Level Justification: i Deleted references to temperature element, TE-5404, This component has been removed from the plant design. ' Also, this component was incorrectly referenced as an 4 accident monitoring component. TE-5400 through TE-5403 l are the correct components for accident monitoring, and
- are installed above the flood level. This change is ,
consistent with the identified tag numbers for the accident monitoring containment ! atmospheric temperature elements in FSAR Table 7.5 7. Group: 3 ' FSAR Change Request Number: 89 787 Related SSER Section: SSER12 App T ' SER/SSER Impact: No , 0&R 040 43 Description (Update) Environmental Qualification Justification: Delete reference to vendor qualification program documents since the detailed qualification program information has been incorporated into the CPSES , Equipment Qualification program. The correct reference to the section of the FSAR where - compliance to IEEE 334-1975 is discussed is also . provided. Group: 3 . FSAR Change Request Number: 88 843.7 Related SSER Section: SSER6 3.11.3 , SER/SSER Impact: No
l Attachment to TXX 90011 l January 15, 1990 : Page 291 of 304 ! l FSAR Page ! (as amended) Descrintion ; i 0&R 040 49
Description:
(Update) l Environmental Qualification ! Justifications ; Updated responses to reflect the current Environmental ' Oualification program and the pertinent Environmental ! qualification FSAR sections Group: 3 , FSAR Change Request Number: 88 843.4 i Related SSER Section: SSER6 3.11.3. : SER/SSER Impact: No ! i O&R 040 65
Description:
(Correction) ! Environmental Qualification Justification: Corrects references to Table 4 1 that was previously consolidated from several App. 3A tables.
- Group
- 3 FSAR Change Request Number: 88 843.5 Related SSER Section: SSER6 3.11 SER/SSER Impact: No Q&R 040 121 Descriptions.(Clarification)
Justification: Clarifies response to Question & Response 040.86 by identifying that the previous response had contained a typographical error. Group: 4 FSAR Change Request Number: 89-430.10 Related SER Section: 9.5.7 SER/SSER Impact: No i 1 0&R 040 163 Descriptions (Correction) Justification: ! Corrects version of IEEE Standard from 1972 to 1980. consistent with FSAR Amendment 66 revision to Sections 1A(B) and 8.3. Group 4
< FSAR Change Request Number: 89 667 Related SER Section: 8.3.2 SER/SSER Impact: No Q&R Table 040.109 1 See Sheet No(s):02
Description:
(Revision) Revises the time delay for relay (27-32)/(IEA1) from 2 tp 1.9 second. Justification: Revises the time delay for relay (27-32)/(1EA1) from 2 to 1.9 second. This accounts for calibration tolerance, so that the relay will trip at the desired 2 second time delay in the event of relay drift. Group: 3 FSAR Change Request Number: 89 524.1 i 1
I Attache:nt to EtX 90011 : January 15, 1990 j Papa 292 of 304 I FSAR Page (as amended) Descriction j Related SER Section: 8.2.4 SER/SSER impact: No j O&R Figure 040.109 1 Descriptions (Editorial) j i Justification: Corrects MCC No. 1EB03 to 1EB3. Group: 4 FSAR Change Request Number: 69 524.3 SER/SSER Impact: No i ! O&R Figure 040.109 1 Descriptions (Revision) l Revises the time delay for relay (27 3Z)/(1EA1) from 2 l to 1.9 second. l l Justification: l Revises the time delay for relay (27 3Z)/(1EA1) from 2 l to 1.9 second. This accounts for calibration tolerance, so that the relay will trip at the desired 2 second time delay in the event of relay drift. Groups 3 FSAR Change Request Number: 89 524.2 Related SER Section: 8.2.4 SER/SSER Impact: No Q&R 130 50
Description:
(Correction) Revises the number of masonry walls that require mod. ification due to adverse seismic interactions. Justification: Access blockout at elevation 830' in the Safeguard Building was reworked and is now seismically designed. Text is being modified to reflect as built conditions. Group: 3 FSAR Change Request Number: 89-030 Related SER Section: 3.8.3 SER/SSER Impact: No
- O&R 140 3 Descriptions (Correction)
Environmental impact of an MSLB with superheat releases-Justification: Revised the description of the worst break technical justification to match the plant specific calculation, and to provide clarification regarding the evaluated power levels. This change was-evaluated under the TV Electric 50.59 process as described in TXX 89718 dated 9/28/89. Group: 3 FSAR Change Request Number: 89-773.7 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No
Attachment to TXXop0011 January 15, 1990 , Page 293 of 304 : FSAR Page (as. amended) Descrintion O&R 140 4 Descriptions (Correction) Environmental impact of un MSLB with superheat releases l l' Justification: , Corrects the time sequence for steamline isolation to 311 seconds. This is consistent with the value-specified in Table 140.1-2. This change was evaluated l under the TV Electric 50.59 process as described in l TXX 89718. dated 9/28/89. ; Group: 3 > FSAR Change Request Number: 89 773.8 ' Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No , 0&R 140-5
Description:
(Addition) Environmental impact of an MSLB with superheat releases Justification: Clarifies a steam generator tube uncovery event by I adding conditions which may delay the event due to power levels and break sizes. This change was evaluated under the TU Electric 50.59 process as described in TXX 89718. dated 9/28/89. Groups.2 FSAR Change Request Number: 89 773.9 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No l O&R 140 7
Description:
(Correction) Environmental impact of an MSLB with superheat releases Justification: Revised blow down analysis and mass energy release data description to. reflect that the plant specific analysis resulted in a change in the time sequence of the event even though the analysis is virtually the same. This ! change was evaluated under the TU Electric 50.59 process as described in TXX 89718. dated 9/28/89. Group: 3 FSAR Change Request Number: 89 773.10 Related SSER Section: SSER12 3.11.6 SER/SSER Impacts.No 0&R Table 140.1 1 See Sheet No(s):01 Descriptions (Correction) Environmental impact of an MSLB with superheat releases Justification: Corrects the required operability time to 72 hours for the MSIV's to include the time during which the adverse failure mode is possible. Also revised the demonstrated peak operability time and corresponding time margin to , be consistent with the environner.tal test data. This 1 change was evaluated under the TU Electric 50.59 process as described in TXX 89718. dated 9/28/89. Group: 2
Attachment to TXX 90011 l January 15. 1990 ' Page 294 of 304 l i FSAR Page ; l (as amended) Descrintion ; FSAR Change Request Number: 89 773.11 Related SSER Section: SSER12 3.11.6 l SER/SSER Impact: No ! l* l 0&R Table 140.1 1 See Sheet No(s):01
Description:
(Correction)
- Environmental impact of an MSLB with superheat releases Justification:
The MSIV bypass valves are manual valves and do not have any qualified parts. Thus. "N/A" is-appropriate since a demonstrated peak temperature is not required. This change was evaluated under the TV Electric 50.59 : process as described in TXX-89718 dated 9/28/89. l Group: 3 i FSAR Change Request Number: 89-773.12 ' Related SSER Section: SSER12 3.11.6 , SER/SSER Impact: No ; 0&R Table 140.1-1 See Sheet No(s):01, 02, 03, 04, 05
Description:
(Correction) Environmental impact of an MSLB with superheat releases , Justification: Added Note 5 to the applicable equipment to reflect the - basis for the 72 hour operability time. This change was evaluated under the TV Electric 50.59 process as described in TXX 89718 dated 9/28/89. Groups 3 FSAR Change Request Number: 89-773.16 I Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No QLR Table 140.1 1 See Sheet No(s):01, 02, 06 Description (Correction) , Environmental impact of an MSLB with superheat releases Justification: Corrects the required operability times for the main j i steam drain pot isolation valves, feedwater bypass' '
< valves and the feedwater sample isolation valves to 30 minutes. The 30 minutes is based on operator action. No adverse failure mode after valve closure is expected to occur. This change was evaluated under the TV i
Electric 50.59 process as described in TXX-89718. dated 9/28/89. Group: 3 . FSAR Change Request Number: 89 773.13 Related SSER Section: SSER12 3.11.6 SER/SSER 1mpact: No ' L
. ~ . - - .- , , _ . --_ ._
. ~ . - . - - - . - -- - - . . -. -
1 Attachment to TXX 90011 January 15, 1990 Page 295 of 304 FSAR Page ! (as amended) Descrintion 0&R Table 140.1 1 See Sheet No(s):02 Description (Correction) 1 Environmental impact of an MSLB with superheat releases 1 Justification: l Corrects the required operability time to 72 hours for the FIV's to include the time during which the adverse j failure mode is possible. Also revised the demonstrated i peak operability time and corresponding time margin to be consistent with the environmental test data. Also ,
- added corresponding notes associated with operability l of these valves. This change was evaluated under the i TU Electric 50.59 process as described in TXX 89718, i dated 9/28/89.
Group: 2 ; FSAR Change Request Number: 89-773.14 Related SSER Section: SSER12 3.11.6 4 SER/SSER Impact: No , 0&R Table 140.1 1 See Sheet No(s):03 i Description (Correction) Environmental impact of an MSLB with superheat releases Justification: Corrects the required operability time for the Barton steamline pressure transmitters. Failure of these ' transmitter could result in operator error. Also, the transmitters are required for controlling cooldown rates, and are not located in the break room. Thus, the transmitters are required to be qualified for a , minimum of 72 hours. This change was evaluated under the TU Electric 50.59 process as described in TXX 89718. dated 9/28/89. . Group: 2
- FSAR Change Request Number: 89-773.15 Related $$ER Section: SSER12 3.11.6 SER/SSER Impact: No O&R Table 140.1-1 See Sheet No(s):04
< Descriptions (Correction)
Environmental impact of an MSLB with superheat releases Justification: Corrects the required operability time to 72 hours and a corresponding time margin for the HVAC dampers. ! The operability time includes the potential adverse failure mode of the non metallic parts. This change was evaluated under the TU Electric 50.59 process as described in TXX-89718 dated 9/28/89. i Group: 2 FSAR Change Request Number: 89-773.17 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No
i Attachment to TXX 90011 't
'l January 15, 1990 e Page 296 of 304
- I FSAR Page l (as am W ) Descrintion ,
I O&R Table 140.1 1 See Sheet No(s):05 i l
Description:
(Correction) ! Environmental impact of an MSLB with superheat releases Justification: + Clarifies the accessory limit switches auxiliary feed-water flow transmitters and MSSV position indicator line items by adding " intact steam generators" to : reflect that the equipment required is not associated with the faulted steam generator. This change was j evaluated under the TV Electric 50.59 process as i described in TXX 89718. dated 9/28/89. Group: 3 l FSAR Change Request Number: 89 773.18 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1 1 See Sheet No(s):05
Description:
(Correction) . Environmental impact of an MSLB with superheat releases Justification: Reflects that the auxiliary feedwater containpent isolation M0V's do not have a required operability time i since alternate equipment is available to perform the
- safety function. However, the qualification data is shown to reflect that this equipment must not fail in ,
a manner detrimental to plant safety. This change was j evaluated under the TV Electric 50.59 process as described in TXX 89718, dated 9/28/89. Group: 2 FSAR Change Request Number: 89-773.19 Related SSER Section: $$ER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1 1 See Sheet No(s):06
Description:
(Correction) Environmental impact of an MSLB with superheat releases Justification:
, Revised Note 2 to reflect the 30 minute operability- l time and expounds on the functionality of the MSIV's.
This change was evaluated under the TV Electric 50.59 process as described in TXX 89718, dated 9/28/89. i Group: 2 FSAR Change Request Number: 89 773.20 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No O&R Table 140.1-1 See Sheet No(s):06
- Description (Clarification)
Environmental impact of an MSLB with superheat releases Justification: Clarifies Note 4 to reflect the 30 minute operability : time for the feedwater bypass valves, feedwater sample
)
Attachment to TXX 90011 January 15, 1990 Page 297 of 304 i FSAR Page , i (as.amende() Descrintion ! I isolation valves and main steam drain pot isolation l valves. This change was evaluated under the TU ' Electric 50.59 process as described in TXX 89718. j dated 9/28/89. j Group: 4 I FSAR Change Request Number: 89-773.21 -J r Related SSER Section: SSER12 3.11.6 . SER/SSER Impact: No 3 l 04R Table 140.1 1 See Sheet No(s):06 'J Descriptions (Correction) i Environmental impact of an MSLB with superheat releases ' Justification: Revised Note 6 to reflect the 30 minute operability time and expounds on the functionality of the Barton : steam line pressure transmitters. This change was ; evaluated under the TU Electric 50.59 process as ' described in TXX 89718, dated 9/28/89. Group: 2 FSAR Change Request Number: 89-773.22 l Related SSER Section: SSER12 3.11.6 l SER/SSER Impact: No 0&R Table 140.1 1 See Sheet No(s):07 Description (Correction)- Environmental impact of an MSLB with superheat releases Justification: i Deleted the parenthetical statement which indicates that the operability of the HVAC dampers is less than l 12 minutes. As previously indicated in this Table, the ! operability time for the dampers is 72 hours. This change was evaluated under the TU Electric 50.59 4 process as described in TXX 89718, dated 9/28/89. , Group: 2 ' FSAR Change Request Numbers' 89-773.23 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No 4 > O&R Table 140.1-1 See Sheet No(s):07 Description (Correction) Environmental impact of an MSLB with superheat releases Justification: ' Revised Note 10 to reflect that the auxiliary feedwater containment isolation M0V's is not required to isolate auxiliary feedwater flow since alternate equipment is i available to perform the safety function. This change was evaluated under the TU Electric 50.59 process as described in TXX 89718, dated 9/28/89. Group: 2 FSAR Change Request Number: 89-773.24 i Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No
i Attachment to TXX 90011 ) January 15. 1990 l Page 298 of 304 i
- FSAR Pope l (as amended) Descrintion ;
! Q&R Table 140.1-1 See Sheet No(s):08 Descriptions (Correction) I Environmental impact of an MSLB with superheat releases- i . Justification: 1 Deleted the description of Note 14 regarding Barton i steam line pressure transmitters and replaced it with i the feedwater isolation valve operability and ; functional description. This change was evaluated under ; the TU Electric 50.59 process as described in TXX 89718 i dated 9/28/89. : ! Group: 2 ! FSAR Change Request Number: 89 773.25 Related SSER Section: SSER12 3.11.6 SER/SSER 1mpact: No , T O&R Table 140.1 1 See Sheet No(s):08 i Descriptions (Correction) i Environmental impact of an MSLB with superheat releases Justifications r Revised Note 15 to clarify that the Rosemount steam line pressure transmitters although not required to i function, must not fail in a manner detrimental to l Plant safety. This change was evaluated under the TV l Electric 50.59 process as described in TXX-89718. dated ! 9/28/89. Group: 3 FSAR Change Request Number: 89 773.26 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No ' Descriptions (Correction) O&R Table 140.1 2 , Environmental impact of an MSLB with superheat releases i Justification: Corrects the time sequence for steamline isolation to 311 seconds. This change was evaluated under the TV Electric 50.59 process as described in TXX 89718
, dated 9/28/89.
Group: 3 ' FSAR Change Request Number: 89 773.27 Related $$ER Section: SSER12 3.11.6 SER/SSER Impact: No 0&R 150 3
Description:
(Update) Updates the response to 0150.2 to refer directly to Table 17A-1. Justification During the Pump & Valve Operability Program NRC inspec- _; tion of Aug. 22 25, 1989, the NRC stated that the res-ponse to 0150.2 was-out of date. TV Electric agreed to t update the response. Group 3 t
?
. .~ _ -
Attachment to TXX 90011 January 15. 1990 Page 299 of 304 FSAR Page (as acepded) Descrintion FSAR Change Request Number: 89-621.1 Related SER Section: 3.10: SSER19 r SER/SSER impact: No i 0&R 150 5. 6 Descriptions (Update) . Updates the response to 0150.3 to refer to the.MEL { instead of TXX 3295. remove the statement concerning BOP piping and supports qualification method, and add a > commitment to identify to the NRC any safety related equipment items not installed prior to fuel load. Justifications-During the Pump & Valve Operability Program NRC inspec- . tion of Aug. 22 25. 1989, the NRC stated that the res-pense to 0150.3 was out of date. TV Electric agreed to ' update the response. The statement regarding the BOP piping and supports qualification method is irrelevant to the question and is being deleted. Group: 3 FSAR Change Request Number: 89 621.2 ' Related SER Section: 3.10: SSER19 SER/SSER Impact: No ' Q&R 150 8 Descriptions (Correction) Environmental Qualification Justification: Correction of Table 14.2 2 references that were changed in a prior cuendment. but never reflected in this section. Group: 4 ' FSAR Change Request Number: 89 115 Related SSER Section: SSER6 3.11.3 SER/SSER Impact: No Q&R 212-11 Descriptions (Correction). ' Revises safeguards sump level setpoints. Justification: Revisions were made to the safeguards sump level j
< setpoints to provide consistent terminology in
, regards to the discussion of sump pump initiation / alare levels. 1 , Group 3 i FSAR Change Request Number: 89 514.2 ; Related SER Section: 9.3.3 SER/SSER Impact: No O&R 212 70 Description (Clarification)
- Justifit:ation
, Since the FSAR description addresses flow instead of l electrical circuitry, the term " path" is more appropriate than the term " circuit". Group: 4 FSAR Change Request Number: 89-443.6 , i , i
Attachment to TXX 90011 i
- January 15, 1990 !
Page 300 of 304 l 3 FSAR Page (as amended) Descrintion j I l Related SER Section: 6.2 j SER/SSER 1mpact: No , OkR 212-70 Descriptions (Correction)
- Justification: ;
The response to this section describes the RHR system l I performance. References to the closure and opening of. ; l "RCS" is out of context. The correct wording describes l j the closure and opening of "RHR valves". , l Groups 3 - ! FSAR Change Request Namber: 89 443.7 , i Related SER Sections 6.2 ! SER/SSER Impact: No OtR 212 138 Descriptions (Clarification) ! Modifies the reponse to Question 0212.74, dealing with , the Feedwater Pipe Break event, to indicate that the l assumed time required for initiation of operator action ! is 1800 seconds after reactor trip occurs. ! Justification: This change is made to clarify the time frame assumed ! in the analysis for the initiation of operator action. i Group: 4 ! FSAR Change Request Number: 89 672.18 l i Related SER Section: 15.3.6 SER/SSER Impact: No 0&R 212-139
Description:
(Correction) l Modifies the response to Question 0212.75 to provide ; the maximum water relief rate through the three ' l pressurizer safety valves. Justification: 4 This change is made to confrom this value with that used in the analysis of the Feedwater System Pipe Break l event in Section 15.2.8. Group 3 4 FSAR Change Request Number: 89 672.19
< Related SER Section: 15.3.6
- SER/SSER Impact: No ,
- Q&R 212 189a Descriptions (Update) l
- Modifies the response to Question 0212.112 to indicate that an error of +5% is assumed in the full power programmed pressurizer level for the analysis of the Feedline Rupture event. -
Justification: ' Tin, change is made to conform this value to that.used in tie analysis of the Feedwater System Pipe Break - event in Section 15.2.8.2 as revised in Amendment 57. Group: 3 i FSAR Change Request Number: 89 672.20 Related SER Section: 15.3.6 ,
, - . , . . . , < - , . . , , . - . , , . , . . ~ - , , , - . ,- ~ ~
- s. . ........m . - , . , - + - . 4 m Attach:Ont- to TXX 90011
' January 15, 1990 Page 301 of 304 FSAR Page (as amended) Descrintion
'SER/SSER Impact: No 0&R.212-201
Description:
(Correction) Modifies the_ sets of conditions that must be procedur-ally satisfied following the occurrence of a steam line rupture in order for the operators to stop the reactor coolant pumps, 4 Justification: This change is made to be consistent with the in . structions provided to the operators in the E0P_and the supporting calculations. ; Group: 3 l FSAR Change Request Number: 89i472 ;
- Related SER Section
- 15.3.5 l SER/SSER Impact: No 0&R Table 212.65 1 See Sheet No(s):01 and 03 1 Descriptions (Correction) l Corrects the description of the basis for selection of-the worst single failure assumed for the analysis of the'Feedwater System Pipe Break event.
Justification:
- This change is made to_ indicate that although one pro- l
! tection train is assumed to fail, the associated motor- _; driven AFW pump is not assumed to fail (for.AFW flow j purposes): rather, the turbine-driven pump is assumed .!
- to fail, thus providing a conservative bounding-failure.
Group: 3 ! FSAR Change Request. Number: 89 471 Related SER Section: 15.3.6 j
- j. SER/SSER Impact: No i
( Q&R Table 212.65-1 See Sheet No(s):02
Description:
(Correction) Modifies the entry for the worst failure assumed in 1 l analyzing the Steam Generator-Tube Rupture event by r , deleting the listing for the overfill aspect of that
~
l l event. i l- Justification: ! This change is made to reflect the fact that the Steam: i Generator Tube Rupture event is' analyzed to demonstrate .] that the resulting radiological doses are within 'the j guideline values of 10CFR100. Group: 3 j l FSAR Change Request Number: _ 89-672.21 l
- Related SER Section: 15.4.4 i SER/SSER Impact: No
\
Attachment to-TXX-90011 ' January 15, 1990 ' Page 302 of 304 TSAR Page (as amended) Descrintion . O&R 423 2. 3
Description:
(Clarification) l Corrects R423.2(2)(a) reference to test summary. , tables. Justifications R423.2(2)(a) incorrectly references Table 14.2-2 L (Sheet 41 of 60). Table 14.2-3 (Sheet 33 Of 35) is the ' I proper reference for the Automatic Reactor Control
, System functional demonstration. i Group: 4 >
FSAR Change Request Number: 89 607 Related SER Section: 14.2
- SER/SSER Impact: No Q&R 423-2. 3 See Page No(s):04 f
Description:
(Clarification) ' Deletes discussion of Incore Nuclear Instrumentation Testing from R423.2(1)(b). (2)(b). (3)(b) and (4)(b). - Justification: Deletes discussion of Incore Nulcear Instrumentation Testing from R423.2 to provide consistency with changes to Table 14.2-2 and 14.2-3 as provided in a previous amendment. Incore Nuclear Instrumentation Testing was deleted from the Preoperational Testing Program (Table 14.2-2. Sheet 45) and will only be tested in the Initial Startup Testing Program-(Table 14.2-3 Sheet.34). Added clarification note to : to R423.2(1)(a). Group: 4 FSAR Change Request Number: 89-580 Related SER Section: 14.2~ SER/SSER Impacts No
- O&R 423-16
Description:
(Clarification) Deletes R423.8 D.I.o to be consistent with the deletion of the Pseudo Rod Testing' requirements (Table 14.2-3.. Sheet 27) as provided in a previous amendment.
- Justification The Pseudo Rod Testing was deleted from the Intial Startup Test Program in a previous amendment based.on the performance of Pseudo Rod Testing at other similar' Westinghouse NSSS Nuclear Power Plants.
Group: 4 FSAR Change Request Number: 89-582 Related SER Section: 14.2 SER/SSER Impact: No 0&R 423-19
Description:
(Clarification) Deletes reference in R423.10(b) that the Rod Control test will be performed prior to fuel load. Justification: Deletes reference in R423.10(b) that the Rod Control. test will be performed prior to fuel load to provide a . _. L
Attachment to TXX-90011
. January 15, 1990 Page 303 of~304 FSAR Page (as amended) Descrintion consistency with T14.2-3 Sheets 31 and 32, and i14.2 4 Rod Control testing will be performed in Initial Startup testing.
Group: 4 FSAR Change Request Number: 89 592 Related SER-Section: 14 SER/SSER Impact: No O&R 423 29, 30 Descriptio;.. ( Addition) Revises R423.12' Item 16 to summarize the "Special Test" for the DCLSystem Minimum Voltage Calculation Validatione Justification: R423.12 Item 16 has been revised per NRC request tof to provide consistency with previously provided information. Groups 3. FSAR Change Request Numbers. 89 662.3 Related SER Section:'14 SER/SSER Impact: No O&R 423-30a
Description:
(Correction) Deletes reference to Sheet 66 of FSAR Table 14.2-2. Justification: Reference to, Sheet 66 of FSAR Table 14.2-2 is deleted.. since Sheet No. 66 does not exist.for this table. 1 In response to NRC inquiries related to Instrument Air i System testing during the preoperational and startup; testing audit conducted June 20-22, 1989, TU' Electric
- provided an advance FSAR change submittal
- for' Sections
- 1A(B), 9.3, 14.2, 0&R 423.12-and 423.26 (TXX-89461),
which wes later incorporated into the FSAR in Amendment 77 (TXX 89657). During the FSAR change' request process prior to the advance submittal, three (3) tests were a considered for inclusion in Chapter 14: Individual Accumulator Tests, Branch Header Testing, and . l Individual Component. Tests. The latter was to have j
, been included on Sheet 66, but was subsequently deter-- 1 l mined to be a prerequisite test, not preoperational: , and, therefore, was-not included in Chapter 14 Refer-encefto Sheet 66, though, was not removed frce FSAR' page 423-30 (submitted as revised in Amendment 77), and .
the detailed description for Amendment 77 (TXX-89659) referred to "three" preoperational tests being added, i instead of two,'tn-meet the intent of the requirements of R.G. 1.68.3. Also, reference to " Air Operated. i Component Failure Positions" should not have been in-i cluded in the detailed description, as it' relates.to l the prerequisite test discussed above. An appropriate ! plant procedure incorporates this prerequisite test. Group: 3 FSAR Change Request Number: 89-706 i.
( i Attachment to TXX-90011 January 15 1990 i Page 304 of 304 J FSAR Page (as amended) Describtion . Related'SER Section: 14 - - SER/SSER Impact: No O&R 423 39
Description:
(Uposte) : Changes to response 2b of 0423.16- regarding ARMS , calibrations and source checks i Justification: The current FSAR wording (Ammendment 76) in.the I response to this question includes-incorrect assignments of responsibilities for area monitor calibrations and source ~ checks. , Group: 4. FSAR Change Request Number:'89 477 , Related SER Section: 12.3.4 1 SER/SSER Impact: No s 4 L i
'I l
i. b n -- - e n ,
2 - Bases submittals should be in hard copy and on magnetic media (3 and 1/2-inch ! normal density diskettes) in Word Perfect 5.1. , Sincerely, i t M l Jose A. Calvo, Chief- '3 Technical Specifications Branch -! Division of Operational Events Assessments,'NRR 4
Enclosures:
As stated cc: C. DeDeaux, CE0G Chairman
- J. Hinds, WOG Chairwoman ,
J. Jones, BWROG Chairman 4 C. Smyth, B&WOG Chairman E. Lozito, VEPC0 ; B. Woods, SCE , K. Wilson, FPC , ! J. Fowler, SERI- ' M. Bryan, TVA , i I r l l l l l l 1 1 l l -l \ \
}}}