ML20199K133
| ML20199K133 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/02/1998 |
| From: | Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-98015, NUDOCS 9802060110 | |
| Download: ML20199K133 (211) | |
Text
Log # TXX 98015 M' File # 10010 llllllllll' 1llllllll Ref. # 10CFR50.71(e) 3 3 nlELECTRIC' O. lance lerry February 2, 1998 3, ., w , r,,,a, a r, w w m,,
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 DESCRIPTION OF AMENDHENT 95 REVISION TO THE UPDATED FINAL SAFETY ANALYSIS REPORT Gentlemen:
Amendment 95 to the CPSES updated Final Safety Analysis Report (FSAR) was transmitted to you under a se)arate cover letter, TXX 98014, dated February 2, 1998. The attachment to t11s letter provides line by line descriptions of the changes in Amendment 95. FSAR pages which do not have technical changes but are included in the amendment (because they cre the opposite side of the sheet from a 3 age that was changed, because the change shifted existing material to anotler page, because only editorial changes were made on these pages or because of restructuring FSAR figures into process flow diagrams for each unit) are not discussed in the attachment.
Amendment 95 includes revisions to plant process flow diagrams which replaced certain FSAR figures as described in the description of Amendment 94 (TXX 96423, dated August 1, 1996). These flow diagrams include design details over and above the previous simplified FSAR figures. The justifications for the trivial changes on flow diagrams are not provided in this attachment; however, justification for non trivial technical changes for each flow diagram is provided in the attachment. The replacement of the FSAR figures with plant process flow diagrams meets the intent and requirements of NRC Regulatory Guide 1.70, Revision 2.
A discussion of some of the codes used in the description letter is provided in the enclosed letter (TXX 88467 dated June 1, 1988, without attachment).
This letter (TXX 98015) and its attachment contain no commitments.
_. Since y, 9902060110 900202 / l PDR ADOCK 05000445 Q K
BSD/bsd PY d, G v U .j C. L. erry - bJ j Enclosure Attachment c- Mr. E. W. Herschoff, Region IV ,
Mr. J. I. Tapia, Region IV 'l il ihh33 5
Resident Inspector. CPSES Hr. T. J. Polich, NRR r O. Don 1(U2 Glen Rose, Texan 7 tot 3
,_. - .. - - - = .- - - - - - . -
Attachment to TXX.98015 CPSES - \ sATIID FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT- 95 DI TAILI:D DI:SCRipTION Prefix Page Page 1 (as amEndnfj Group Danictig!] Sectiert 1.1- l 4 Revise " Production Division oflU I:lectric" to *0cneration llusiness Unit of ,
1U 1:lectric". 1 Revision !
Organisational update to reflect 1997 reorganiration of'IU 1:lectric's functional divisions into business units.
Change Request Number SA 129 , i Related SI:R : SSl:R : Section:
$1-R/SSI:R
- 1mpact N 1.1 - 2 4 Clarification As described in Section 6.2 and Chapter 15, while the containment and engineered safety features were designed for operation at the maximum calculated power output, the current evaluations do not support operation at that power level.
Change Request Number SA 142 . O Related SI:R - SSI:R Section:
SI:R/SSI R impact N 1.1 - 2 2 Corrected for consistency with Section 6.2 and Chapter 15.
Correction Containment and engineered safety features were designed and originally evaluated for operation at the maximum caiculated power output; however, as described in I'SAR Section 6.2 and Chapter 15 many of these evaluations have been superseded with evaluations performed at the RATI:D TIIERMAL POWliR level of 3411 MWt plus the net reactor coolant pump heat of at least 14 M Wt.
Change Request Number SA - 96 100 I Related SI R : SSI:R : Section:
SI:IUSSIIR impact N
T Attxhment to 1XX.980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAll.ED DESCRIPTION Prefix Page Page 2 f as amended) Grupp Descrintion Section.
1.2- 6 2 Pages 7 and 17 Corrected for consistency with Chaptera 4 and 5.
Upt. ate More than one-third of the core is discharged during the typical refuelmg cycle as described in Appendices 4A and 411. Text descriptions are corrected so as not to conflict with other details in Appendices 4 A and 4D and Chapter 9.
Also, there is not a definition for NSSS rated thermal pow ct:" thus, that phrase is changed.
Change Request Number SA 100 . 2 Itelated SER . SSER : Section:
SEluSSER impact N 1.2- 7 4 Clarification The descriptions of the reload cose composition (discharge 1/3 of the core each refueling) and the exact loading pattern are incoraistent with the loading patterns shown in Appendixes 4 A and 411.
Change Request Number SA 142 . O Related SER : SSER . Section:
SI:lUSSER Impact N 1.4- 2 4 Page 3 Revise discussion of TU Electric's organization.
Revision Organizational update to reflect 1997 reorgantiation of TU Electric's functional divisions into business units.
Change Request Number SA 129 . 2 Related SI:R
- SSER : Section:
SI:R/SSER impact N I A(N)- 58 4 Remove duplicate information.
Editori.nl This information is deleted as it is a duplication ofinformation summarized in Chapter 7 and in the Technical Specifications Section 2 and 3.3 II ASES.
Change Request Number SA 100 . 4 Related SER - SSER : Section:
SI:R/SSER Impact N
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Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 Dirl' AILED DESCRIPTION l
PetrisPage Page 3 l j (EtninEDdsf; Group ikseriotion Section.
i (
I A(N)- 69 3 i_ Update method for densification model of the fuel.
Update j The methods currently used by 1U Electric are referenced in the TU Electric 3 topical eport RXE-90 007 A. referenced in the TSAR Appendices 4A and 40, i and the Technical Specification 6.9.l.6b, item 1$.
! Char.ge Request Number S A 100 . $
i Related 5ER : SSER : Section:
SER/SSER impact N i A(Ni- 73 4
)
cenmvc referer:ce to NRC Question 2.2.32.
tuitorial 1 he responsa to NRC Questiaa was previousi incorporated into TSAR Chapter $.
SEk/SSER 1mpact N
! I A(ll)" f l 2 Ados paragraph to Section 1 A(ll)(Regulatory Guide 1.75. Physical independence of Electric Systems") stating that isolation between Class lE pressure indicating switch contact and Non-Class IE time delay relay in the 1 cmergency diesel Fercrator control panels is not required based on the analysh
! provided in l'SAR Section 8.3 i Correction i DO Starting Air system modification shown on the revised flow diagrams (See Change Request Numbers S A 96-34.6 thm 9) meets the requirements of ANSI NIN9.2 specified in l'SAR Section 3.2 for safety class 3 and NNS class 1 interface.
The Non-Class lE time delay relay contact that is in series with the Class lE pressure switch contact and has no impact on the safety function of the Class lE Solenoid Operated Valva. An open circuit or grounding of the time delay relay contact will deenergire the SOV and default to the safe position (closed).
A shortened time delay is no ditTerent than a closed circuit and it does not affect the Class l E pressure indicating switch contact.
- SER/SSER impact N
. - _ _ . - . _ _ ...,.,.m._._,,___ _.
Attachment to TXX 98015 CPSliS - UPDATED FINAL SAFETY ANALYSIS RIIPORT AMI:NDMI'NT. 95 DETAILED Dl:SCRIPTION Prefix Page Page 4 (asunendod) OnW IkhniPilRD Section.
I A(II)- 52 2 in section 1 A(II) under Regulatory Guide 1.75 discussion, adds description of galvanited steel sheathed cable for consider:ng as Metal Clad (MC) cable.
Deletes the details describing the various MC caoles.
Addition Galvanlied steel sheathed cable which carries low level signald at CPSES like other metal clad cables meets ll:I:E 383 and RO 1.75 requirements and is installed to seismic category 11 requirements. The details of various metal clad cables are described in section 8.3.
Change Request Nurnber S A 66 1 Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N l A(ll)- 53 3 Adds new Spent l'uel Pool (SI'P) level devices (X LY 4849A 1, X LY-4849A 2, X LY-4849111 and X LY-4849112) to provide 2-out-of 2 logic for Spent l'uci Pool cooling pump protection on low-low pool level and continuous level indication in the control room.
Revision 1hc existing level instrumentation for the SI'P provide a high and low pool level alann along with a low-low SI'P cooling pump trip.1hese instrumwents are replaced with level instruments that will retain the function of high and low level alanns and add the function of pump protection. 'Ihe 2 out-of 2 logic ensures that a single instrument malfunction will not cause the pump to trip. In addition SI'P indication is added to the plant computer to allow the control niom personnel to monitor SI'P level.
Isolation devices have been tested . As a result of the testing Class IE fuses were added to the output to protect the isolator. Class 1E and non 1 E cables tenninate on the same terminal block inside the electronic boxes. Non lE cables are rated at 600 volt AC and are lhe retardant and the associated tenninal bhick is heavy duty type with adequate rating. The devices inside the electronic boxes are seismically installed.
1he cables in the vicin:ty of annunciator cable terminations are trained to tenninate on particul.r terminals. These cables are not expected to get loose and cause hot short at the annunciator cable tenninals.
1herefore these changes will not degrade the operation of the class IE cicetronic boxes.
Change Request Number SA 110 . 1 Related SER : 8.3 SSER , 22 Section: 8.3 SER/SSER 1mpact N
Attachment to TXX 9kol5 l l
CPSIIS - UPDATIID FINAL SAFliTY ANALYSIS RIIPORT l AMENDMI:NT 95 Dl! TAILED DESCRIPTION l Prefix Page Page 5 (as amended) Ongtp pcKrlption $ntion; 1 A(II)- 53 2 Changes the i SAR section I A(ll) pertaining to Regulatory Guide 1.75 to identify that separation is not required between the output cables and conduits of spare Class i!! Inverters.
Addition Procedural controls and interkicks ensure that the spare inverter can only feed the loads of one inverter at a time. Only one of the four output cables from the spare inverter is energlied at a time while the other cables remain disconnected. See alsojustification for changes to page 7.6-1.
Change Request Number SA 60 . 20 Related SER : 8.3 SSI:R : 22 Section: 8.3 SER/SSIIR 1mpact N l A(II)- 54 2
- Changes FSAR section i A(II) pertaining to Regulatory Guide 1.75 to identify that the separation hetween non-Class III Train C cables and Class 11! Train 11 cables powering breaker shimt trip coil for breaker CP2 IISDSEll 01 is adequate.
Rtvision 1he ables used h the non-Class 1 E application are 600V rated Class 11!
cables meeting the IEEE 383 requirements and the cables are terminuted to meet the Class 111 termination requirements. The non-Class 11: cables are fire retardant adequately designed and are protected by atleast two breakers in series. liased on these, internal spatist separation and scismic panel mounting.
there is assurance that any fault in the non-Class 11! cabling does not degrade the Class lE system.
Change Request Number SA 134 . 5 Related S!!R : 8.3 SSER , 22 Section: 8.3 SER/SSER impact N I A(II)- 54 2 Add CP2-EIPRLV-4R for electrical equipment not requiring internal cable separation an exemption from intemal train separation requirements to NRC R,G.1.75, Also revises applicable section 8.3.1.2.1 (Page 8.3 71) and table 8.3 10 (Sheet 2).
Revision CP2-EIPRIN-48 is the Unit 2 Turbine Driven Auxiliary Feedwater Pump control panel which is multi-train equipment and is exempt from internal train separation requirements. The panel does not serve a safety fimetion and contains one non safety related cable along with several Train A associated
l Attachment to 11 T 980l$ ,
f i
i CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT !
AMENDMENT 95 f i DETAILI:D DESCRIPTION !
$ l Prells Page Page 6 .
- ias amended) Group Deveintion Section
l cables.1he non bafety related cable is part of a circuit that provides an armunciation interkick between the lobe oil trouble alarm and the ,achometer. .
Power to the associated cables is tripped upon receipt of an SI signal.1hc i
' maximum credible fault current in the non safety related cable is less than the !
current carrying capacity of the cable and will not affect any of the associated l 1 cables in its vicinity. Therefore, the separation between non safety and >
associated Train A cables in the panel is not required. f Change Request Number SA 97 36 .1 Related SI:R : 8.3 SSER : 22 Section: 8.3
) SI:R/SSER impact N f i
I A(II) 54 2- l Changes l'SAR scetion l A(II) pertaining to Regulatory Guide 1.7$ to identify I i-that separatiort/ isolution hetween associated control cables and non-Class IE control cables at the Instrument Alt Compressor Termination Cabinet CPI CICACO-01 A is not required.
! Addition ;
1hc power for these control circuits is tripped on Safety injection Signal (SIS) 4 and the entire circuit is de-energized where SIS is present. Additionally . the circuit characterica including double fuses at the control power transformer.
ensure occurrence of no cable damage from worst case faults and propogatioa to nearby Class 11! circuits is not credible. ,
< Change Request Number SA 44 .I l Related SliR
- 8.3 $$ER t 22 Section: 8.3 ,
4 SER/SSUR impact N j
, 1 A(II). 54 2
Changes l'SAR scetion I A(ll) pertaining to Regulatory Guide 1.75 to identify .!
that the separation hetween non-Class IE Train C cables and Class 11! Train 11 cables powering breaker shunt trip coil for breaker Cpl.IISDSEll-01, is adequate.
Revision 4 1he cables used in the om-Class IE application are 600 V rated Class IE cables meeting the IEEE 383 requirements and the cables are terminated to i meet the Class 1E termination requirements. The non-Class 11! cables are fire ,
retardant, adequately designed and are protected by atleast two breakers in ,
series, liased on these, internal r,paEal separation and seismic panel mounting. .
there is assurance that any fault in the non-Class IE cabling does not degrade the Class IE system.
Change Request Number SA 83 .I ;
Related SER t 8.3 SSER : 22 Section: 8.3 i SER/SSER Impact N -!
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l Attachment to 1XX 98015 1
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT ,
AMENDhti:NT 95 DETAILED DESCR;Pi1ON Prefis Page Page 7 f as amendedj LitnW; Descriotion fitytion:
1 A(II)- 67 3 Revise discussion of CPSES compliance to Regulatory Guide 1.101.
Revision 1his change revises the I'SAR to reflect the current licensing basis for CPSES regarding emergency preparedness, Regulatory Guide (RO) 1.101 and the Emergency Action Levels (EALs) which have been incorporated into the CPSES Emergency Plan and Emergency Plan Procedures after review and approval by the NRC.1he l'SAR discussion of RO 1.101 is changed from compliant - 31.10l( Rev. 2) to compliance to RO 1.101 (key. 3) with the following ..on statement:
TU Electric takes esception to that part of RO 1.101 (Rev. 3) Section C
Regulatory Position" which states " licensees may use either NUREO 0654/I'EMA REP-1 or NUMARC/N!:SP-007 in developing their EAL scheme but may not use portions of both methodologies". CPSES EAL's reflect criteria from both documents and have been specifically reviewed and approved by the NRC (NRC letter of 10/06/1994).
Change Request Number SA 12 . O Related SER : 13.0 SSER- 22 Section: 13.0 SER/SSER Impact N 1 A(ll)- 94 2 CPSES Tech Spec amendment endorsed 10CITc 0 Appendix J. Option 11.
1hese changes reflect the new requirementr> o' 1 JCI'R$0 Appendix J, Optien i 11 and Reg. Guide 1.163.
Revision include discussion of CPSES compliance to Reg. O: <
3.
Change Request Number SA - 96 wa .O Related SER : SSiiR . Section:
SI:R/SSER impact N 2.1- l 4 Page 2 Update the section to show that 111 Electric has the responsibility for maintaining and controlling access to Squaw Creek Park.1his change also updates the state road designator and adds an attemative name for a county road.
Update lhis change updates county and state road designators to reflect changes made by the state and county and makes this description consistent wi) the CPSES Emergency Plan.
l Attachment to TXX 980l$
CPSES - UPDATI!D FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT 95 DETAILED DESCRil'IlON Page 8 l Prefix Page f as amcadtd) Group I)escription firsikn; Change Request Number SA 109 . O !
Related SER : SSER . Section:
SI'.R/SSER impact N 2.1 4 4 Revise Section 2.1.2.1.2 " Mineral Righto to suuove discussion about site perimeter fencing.
Revision This section discusses the responsibilities oflU Electric within the Exclusion area. The info mation removed does not change these responsiblities not the description of the Exclusion Area. This change does clarify the bounds oflU Electric's responsibilities by removing confusing description about the site vs the Exclusion Area.1U Electric control ofingress into the Ex!usion Area is continued to be maintained by use of a mobile patrol at random intervals.
Change Request Number SA 13 .I Related SER . SSER - Section:
SEIUSSER impact N 2.5 200 2 Revi.scs the monitoring frequency of the surface monuments on the crest of the SSI Dam from
- periodically, during impoundment and operation " to
" annually".
Revision This change is consistent with a previous I'SAR Amendment regarding the monitoring frequency of the pierometers on the SSI Dam.1he monitoring frequency of the pierometers on the SSI Dam was revised from " periodically during reservoir impoundment and operation" to " annually" in l'SAR Amendment 21, dated May 21,1981.1his is also consi.itent with the requirements of R.G.1.127, " Inspection of Water Controlled Structures Associated with Nuclear Power Plants."
Change Request Number SA 4I .1 Related SER : 2.5.6 SSER 22 Section: 2.5.6.7 SEIUSSER tmpact N 1his change does nu impact statements made in SSER 22 Sc tion 2.$.6.7, llowever, as a part of the consistency review for change request number SA 97-041 therc !s a statement in Section 2.$.6.7 of SSER 22 which appears to conflict with the Eicensing !! asis as described in l'SAR Section 2.$.6.8.1.
SSER 22, Section 2.5.6.7 panuary 1990] st tes in part:
1he stafT un6rstands, on the basis of discussions with the applicant. that periodic dei nninations for both the surface alignment monumems and pierometers will occur at least every six months and the semiannual
Attachment to TXX 98015 CPSES - UI'DATIID FINAL SAFETY ANALYSIS REPORT AMI:NDMENT. 95 DI: Tall.l:D DESCRIPTION Prefis Page Page 9 (nLAmtudtd) Omug Description Sc(tion, inspections of the pierometers and the surface alignment monuments for the SSI dam will be administratively controlled by means of a CPSI:S surveillance procedure.1he staficonsiders that these inspections satisfy the applicant's commitment to perfonn these inspections at least annually as recommended in RG 1.127.
lhe orignial l'SAR stated that "1he piezometers installed in the SSI Dam will be monitored periodically during reserv'or impoundment and operation in order to gain a measure of the pierometric level within the core of the dam."
In I'SAR Amendment 21. dated May 21,1981, this sentence was changed to "The SSI Dam will be inspected and pierometer tendings taken annually."
In a related NRC inspection report the NRC also documented their review of the required annual SSI Dam inspections.
NRC Inspection Report 445/88-54. 446/88 50, dated 9/27/88 states in part:
- e. (Clor.ed) Open item (445/8852-0-07):
Annual inspection of SSI dam in accordance with Regulatory Guide 1.127.
Revision 1. 'the inspectors reviewed applicant's Procedure EOT.758, " Safe Shutdown impoundment Dam inspection," Revision I dated January 22,1988, and dran Revision 2 to this procedure and determined that annual measurements of pierometric levels and annual surveys of the surface elignment monument locators am required.
In addition, the inspectors revie cd several of the annual dam safety inspection reports and determined that they have the applicable information required by Regulatory Guide 1.127, Revision 1. This item is unsidered closed.
2.5-202 2 Deletes the sentence "1he monitoring of the pierometer will be in accordance with MJ QAP-21." from Section 2.5.6.8.1, "limbankments and Dams /
Instrumentation / SSI instrumentation."
Revision 1he requirement to monitor the pic/ometer is not being changed and remains in I'SAR Section 2.5.6.8.1.1he reference to a specific procedure number is below the level of detail required to be included in the I'S AR. This change is consistent with other monitoring activities described in 17SAR Section 2.5.6.8.1 which also do not include a reference to specific procedure numbers.
R.G.1.70 requires the embankment perfomiance history since completion of construction to be included in the I'S AR Change Request Number S A - 9' - 41 ,2 Related SER : 2.5.6 SSER , 22 Section: 2.5.6.7 SER/SSER Impact N
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Attachment to TXX-980l$
CPSES - UPDATED FINAL sal /ETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Prefix Page Page 10 f as amendsdj Group Description $rstkm; 2.5-213 2 Updates the discussion in Sce' ion 2.5.6.10. " Embankments and Dams /
Operational Notes," to address the embankment performance history since completion of construcdon.
Update Section 2.5.6.10 is spdated to note that the Safe Shutdown impoundment (SSI)
Dam and the Squaw Creek Dam have been monitored as discusscJ in Section 2.5.6.8 and the performance has been satisfactory.1he performance of the i Safe Shutdown impoundment Dam and the Squaw Creek Dam will continue to te monitnred and any unsatisfactory conditions will be evaluated and corrected.
Change Request Number SA 4l .3 Releted SLR
- 2.5.6 SSER - Section:
SI:R/SSER Impact N 2.5.4 32 4 Figure Revise minimum depth requiremen' of Category I backfill over safety-related commodities from 4'6" to 2'6" as shown in i SAR figure 2.5.4 32.
Revision Calculation 16345-CS(II)-103, Rev. I provides the engineering basis for Temado Missile protection of underground safety-related commodities. This
- alculation requires a minimum of two (2) feet of Category I backfill material above safety-related commoditics in order to protect from tornado missiles.
Change Request Number SA 82 ,I Related SER
- SSER Swtion:
SER/SSER impact N 3.1- 8 4 Correction The requirement to have a nonpositive moderator temperature coefUclent of reactivity was removed from the unit Technical Specifications. This tat is revised to be consistent with the plant Technical Specifications a,d Appendixes 4 A and 4D.
Change Request Number S A 142 . O Related SER : SSER . Section:
SER/SSER Impact N
Attachment to TXX 98015 CPSliS - UPDATED FINA1. SAFETY ANALYSIS REPORT AMENDMENT. 95 Dl: Tall,ED DESCRIPTION Prefix Page page 11 ias amended) Group Descrintion Strilca; 3.1-41 3 Change to section 3.1.4.14 to clarify that the flydrogen Purge system can be tested
- periodically to demonstrate its ability to function" instead of"in accordance with the requirementr of the technical specifications".
Clarification The containment isolation valves for the hydrogen purge system are tested as per CpSES Technical Specification. The purge system is routinely tested to demonstrate its ability to function.
Change Request Number S A 130 . I Related SER : J1 SSI:R Section:
SER/SSI:R imnact N 3.2- R 4 Add chlorination systems to list of seismic Category 11 systems.
Clarification Chss 5 piping shown on flow diagram applies.1his is a trivial clarification for the user of Section 3.2 and 17A to find the applicable systems and drawings for progrramatic s esmic Category 11 requirements discussed in the l'S A R.
Change Request Number S A 113 . O Rc;ated SER : SSER : Section:
SEIUSSER 1mpact N 3.2- 3 4 Sheets I thru 7 Table Updated the revision numbers for plant flow diagrams to make them current.
Also added additional sheets to existing flow diagrams (MI 202 3, M10216-C, Ml 0227 01, M10236-11, Ml 0306 A, M2-202 3, Mi-0207 II, M2-0236-11, M2-0306-A M2-0313).
Update lhe revision numbers for the flow diagrams in this table arc revised each FSAR update.
Change Request Number SA 166, o Related EER : SSER : Section:
SEIUSSER 1mpact N
Attachment to TXX-9801f CPSilS - UPDATIID FINAL SAFIITY ANALYSIS RIIPORT AMENDMENT 95 DETAll,ED DESCRIPIIGN Prens Page Page 12 (ALA!ntadsdl GIDMD Donindnu firtlicIn 3.2-4 4 Sheets I thru 7 Table Deleted the revision numbers and amendment numbers for the plant flow diagrarrs. Also added additional sheets to existing flow diagrams (M1202-1, Mi-0216-C, Mi-0227-01, tvi8-0236-il, Mi-0306 A, M2-202-3, i
Ml-0207 II, M2-0236-ll, M2-0.'06-A M2-0313).
tIpdate Table 3.2-4 is the same as Te'.,se 3.2-3 except that the contents are sorted diiTerently. The flow diagram revision numbers and amendment numbers are maintained in Table 3.21 and it is unnecessary to repeat that information in Table 3.3-4. The list of eilective flow diagrams and the cross-referenced l'SAit figure numtwrs are updated for each I'SAR amendment.
Change Request Number SA 166 . O Related SER SSER Section:
SER/SSER 1mpact N 3.6I1- 67 2 Updates l'SAR Section 3.616.2.5.213 A) to include ASME SA 333, Grade 6 as a material used in the auxiliary feedwater lines.
Correetion The piping drawings show both ASME SA 106, Grade 11 and SA-333, Grade 6 material in the Auxiliary I'cedwater System (llRP-A17-1 Sil-009, C1'-3, and ilRP-t-Sil-Ol2, CP-3). ASME SA-333, Grade 6 is equivalent to or better than ASME S A-106, Grade D.
~1his change makes the 1'SAR description consistent with the as-built plant.
Change Request Nu uber SA 118 . 1 Related SER 3.6.2 SSER. 26 Section: 3.6.2 SEIUSSER impact N 3.8 4 2 CPSES Tech Spec amendment endorsed 10CFR50 Appendix J, Option 11.
These changes tellect the new requirements of 10CI'R50 Appendix J. Option 11 and Rc g. Guide 1.163.
Revision Revise discussion of testing requirements for Containment Airlock to reference Option 11 of Appendix J.
Change Request Number S A 68 . I Related SER SSER Section:
SEIUSSER 1mpact N
Attachment to TXX 98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 Dirl'All.ED DI SCRIPTION Prefis Page Page 13 (BLams:ndnt) Onmp Dsscriptioll Sectiom 3.8 30 4 Change the word " saturation" to " design" in items 1,2 and 3 under subsection 4.S.
Editorial The statement in the i SAR is not a correct statement. 280 degrees F corresponds to a saturation pressure of 50 psia and not psig. The containment liner is designed to the numerical va!uu of statements 1,2 and 3 in subsection 4.h Change Request Number S A 81 ,O Related SER SSER Section:
SER/SSER 1mpact N 3.8-69 2 Adds a description of the " Outage Equipment llatch" to l'S AR Section 3.R.I.6.6. The temporary outage equipment hatch is equivalent to the permanent inner containment equipment hatch in MODES 5,6 defueled or during fuel movement.
Revision An outage equipment hatch with pipe penetrations is to bc installed to allow sicam generator activities concurrent with fuel movemat. The outage equipment hatch is in two sections. One section is fbr the penetrations and is instr.lled when containment closure is not required. When containment closure is required, the second piece of the outage equipment hatch is installed and the entire equipment hatch opening is covered by the two pieces. All penetrations and joints associated with the outage equipment hatch shall be sealed. The equipment which passes through the outage equipment hatch penetrations will not provide a path between the containment atmosphere and the outside atmosphere. With the exception ofloss of shmdown cooling where containment pressures and radiation levels are potentially much more severe than a fuel handling accident, the outage equipment hatch provides a fission product barrier which is equivulcnt to the permanent equipment hatch. Since the outage equipment hatch can not be relied upon for loss of shutdown cooling, all penetrations are equipped with quick disconnets to allow timely closure of the equipment hatch.
There are no credible failures introduced by this temporary modification to the e luipment hatch penetration as described in the FSAR. Technical Specincution 3.9.4 is to be satis 0cd while this modification is in place. There is no reduction in the margin of safety because the containment closure function is to be maintaned durnig core alterations and movement of irradiated Ibel during Mode 6.
Change Request Number SA RR 1 Related SER 3.R.1 SSER Section:
Atta:hment to TXX 98019 r
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 14 f as amenddl Group Descrintion Section.
SER/SSER 1mpact N 3.8- 72 2 CPSES Tech Spec amendment endorsed 10CI R50 Appendix J, Option II.
These changes reflect the new requirements of 10CFR50 Appendix J, Option il and Reg. Guide 1.163.
Revision Revise discussion to reflect past tense for initial testing since future testing will be in accordance with Option II.
Change Request Number SA 68 .2 Related SER SSER Section:
SER/SSER Impact N 3.8- 73 2 Page 137 CPSES Tech Spec amendment endorsed 10CFR50 Appendix J, Option 11.
These changes reflect the new requirements of 10CFR50 Appendix J, Option 11 and Reg. Guide 1.163.
Revision Revise ISI program to reflect Option It Change Request Number SA 68 4 Related SER SSER Section:
SER/SSER Impact N 3.9N- 10 2 Sheet 3 Table Correct Table 3.9N-10," Unit 1 & 2 Active Valves," to clarify the basis for active classification of valves LCV-0459 and LCV-0460, and to match FSAR Sections 7 and 15.
Correction The current *llasis" column for these valves indicate, " Class 1 - prevent letdown with low pressure level".
The " Class I" indicates RCS pressure boundary and is correct. The " prevent letdown with low pressure level" is not correct. The pressuriier level interlock is control grade and not a safety function. Iloth valves and the interlock are of the same electrical train and not failure proof. No credit for this mterlock is taken in FSAR Section 7 (Figure 7.2-1l) or Section 15.
This change makes the supporting Section (Table 3.9N-10) consistent with the primary Sections 7 and 15.
Change Request Number S A 14 . I Related SER 3.9.3.2 SSER 22 Section: 3.9.3.2 I
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAll1D DESCRIPTION Prefix Page Page 15 hts amended) Qtgity Dgggription Section:
SEIUSSER Impact N 3.911- 40 2 Deletes the reference to Table 3.9H.7 " Relief and Safety Valves in Seismic Category i Piping Systems," in the FS AR text (Section 3.911.3.3). 'the sentence referring to Table 3.98 7 is revised to state that the safety and relief vulves in seismic Category I piping systems are rihown on the piping and instrumentation diagrams in appropriate sections of the FSAR.
Revision There is no need to maintain a separate listing of duplicate information which is identified on the FSAR figures / llow diagrams. 'Ihe safety and relief valves can be identified using FS AR Section 3.2.1.1 (Scismic Category I), applicable piping & instrumentation diagrams, and FSAR Table 17A 1 (List of Quality Assurred Structures, Systems, and Components). Deleting this table eliminates inconsistencies.1he Standard Review Plan and Reg Guide 1.70 do not require a listing of valves to maintained in this FSAR Section. (For 4 additional inforroation see the detailed description for change request number SA-97 8.2 on Table 3.9117)
Change Request Number SA S , I Related SER . 3.9.3.3 SSER Section:
SER/SSER Impact N 3,911- 47 2 Page 48 Corrects references to IWP and IWV of Section XI of the ASME Code which have been superseded by use of ASME Iloiler and Pressure Vessel Code,Section XI,1989 Edition (no addenda).
Correction Remove incorrect references to IWP and IWV which have been superseded by the use of ASME Code OM Parts I,6, and 10. The discussion is being simplified to refer to the Inservice Testing Plan. As the Inservice Testing Plan receives NRC approval, it is acceptalde to remove this level of detail. *lhis will avoid future FSAR updates to be consistent with the Inservice Testing Plan changes.
Change Request Number SA 115 . I Related SER 3.9.6 SSER- Section:
SEIUSSliR impact N
. - _. - -. =-
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORY AMENDMENT 95 DETAILED DESCRIPTION Prefis Page Page 16 (Blumended) fungr Dnstiption Ssetion:
3.911- 48 2 Corrects Section 3.911.6.2.2, " Valve Test List," by deleting the discussion regarding (1) the types of valves included the Inservice Testin3 Plan and (2) the format for categorizing the valves.
Correction
'Ihe scope of the inservice valve testing plan and the format for the valve tables is provided in the Inservice Testing Plan (I.icensing Ilasis Document).
Deleting duplicate information will eliminate the possibility of future inconsistencies between the Ircervice Testing Plan and PSe l'S AR.
Change Request Number SA 115 . 2 Related SER 3.9.6 SSER ' Section:
SER/SSER Impact N 3.9I1-48 2 Clarify the discussion of valve test provisions in the Technical Specifications (FSAR Section 3.9fl.6.2.3, " Inservice Testing of Valves / Test Procedures").
Valves tested in accordance with the Technical Specifications shall meet "any additional" conditions of the Inservice Testing Plan.
Clarification This change will prevent the misinterpretation that the Inservice Testi Plan requirements supersede Technical SpeciGcation requirements. Tl.: more restrictive requirements of the Technical Specifications take precedence over the ASME Code.
Change Request Number SA 115 . 3 Related SER SSER , Section:
SER/SSER Impact N 3.9 11- 7 2 Table Deletes Table 3.911-7," Relief and Safety Valves in Seismic Category 1 Piping Systems," and adds sentence, "This table is intentionally not used."
Revision There is no need to maintain a separate listing of duplicate infonnation which is identified on the FSAR ligures / Ilow diagrams. The safety und relief valves can be identified using FS AR Section 3.2.1.1 (Scismic Category I), applicable piping & instrumentation diagrams, and FSAR Table 17A 1 (l.ist of Quality Assurred Structures, Systems, and Components). Deleting this table eliminates inconsistencies. The Standard Review Plan nnd Reg Guide 1.70 do not require a listing of valves to maintained in this FSAR Section. (For additional information see the detailed description for change request number SA-97-8.1 on Table 3.911-7)
Change Request Number SA 8 .2 Related SER 3.9.3.3 SSER Section:
l Attachment to TXX-98015 1
I CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 17 (as amended) Group Descrintion Section.
SEIUSSER Impact N 3.911- 10 2 Sheets 22 and 23 Table The Unit I and Common Reactor Makeup Water Pump minillow lines are being modified from I-inch to 2-inch pipe. Valves "lDD-016" and "XDD-044" of Table 3.9H-10, " Active Valves," are revised from 1 inch to 2-inch.
Revision Pump minillow lines and recirculation lines back to the Reactor Makeup Water Storage Tanks are being upsized to increase the recirculation flow capacity.
Increasing the slic of the Unit I and common Reactor Water Makeup pump miniflow lines will reduce the overall system pressure, enhance pump availability, and reduce pump maintenance. For additilonal information see Change Request Number SA-96-55.2 (page 9.2 38).
Change Request Number SA 55 . 1 Related SER 9.2.3 SSER : Section:
SEIUSSER 1mpact N 3.911- 10 2 Sheet 22 Table The Unit 2 Reactor Makeup Water Pump miniflow line is being modiGed from 1 inch to 2-inch pipe. Valve "2DD-016" of Table 3.913 10, " Active Valves," is revised from 1-inch to 2-inch.
Revision Pump miniflow lines and recirculation lines back to the Reactor Makeup Water Storage Tank are being upsized to increase the recirculation flow capacity, increasing the size of the Unit 2 Reactor Water Makeup pump miniflow line will reduce the overall system pressure, enhance pump availability, and reduce pump maintenance. For additional information see Change Request Number S A-96-56.2 (page 9.2-3 8).
Change Request Number S A 56 , I Related SER 9.2.3 SSER Section:
SER/SSER Impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Page 18 (as amendedi Group Description SgsitQn; 3.911- 10 2 Sheet i Table Adds main steam bkick valves (MS-0101 and MS-0128) to Table 3.911-10
" Active Valves".
Addition The Main Steam valves llV 2452-1 and ilV-2452-2, supply steam from Steam Generators 1 and 4 to the Auxillery feedwater Pump Turbine. Dese valves utilire safety related air accumulators to maintain the valves closed during oft normal plant conJitions. After exhausting the air accumulators, a secondary method of ensuring Containment isolation is required. De upstream block valves (MS-0101 and MS-0128) fulfill this requirement.
The air accumulators supply safety related air to the air-operated valves upon loss of the non-safety related plant instrument air system. Ilowever, by design, the air accumulators only provide suflicient air to close the valves and keep them closed for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> with an additional half hour allocated for manual operator action. The block valves upstream ofIIV 24521,-2 are ASME Safety Class 2 gate valves with manual gear operators and have been qualified to function as secondary outside Containment Isolation for penetrations M1-0001 and M1-0004.
As a result these valves are now considered " active" and function as Containment Isolation Valves requiring manual operator action.
This change is also consistent with (1) FS AR Section 9.3.1.2 which discusses local manual isolation for the main steam lines supplying the auxiliary feedwater turbine and (2) FSAR Section 11.11.2 which discusses shielding and access to vital areas for postaccident operation ,
ne Technical Requirements Manual (LDCR-TR-97-007) and Inservice Testing Plan (LDCR-IT-97-006) are also being revised to be consistent with this change.
Change Request Number SA 131. I Related SER 3.9.6 SSER - Section:
SER/SSER impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPT10N Prefix Page Page 19 (as amended) Group Descrintion Section.
3.911- 10 2 Sheet 25 Table Adds Valves SV 3421 lE, SV-3421 IF, SV-3422 lE, and SV-3422 IF to Table 3.9B-10. " Active Valves".
Correction The solenoid operated valves (SOVs) establish (1) safety class interface between safety related DO Air Receiver and NNS Dil Air Compressor and (2) the isolation of the Air Receiver from the Air Compressor upon receiving a signal from the respective pressure indicating switch (PIS) on decreasing air receiver pressure below the set point that ensures the air receiver is still operable.
Based on the design basis, an active failure of the SOVs to funtion as intended could alTect the DO emergency start. Therefore, the SOVs are included in the active valve table.
Change Request Number SA 34 .2 Related SER 3.9.6 SSER : 23 Section: 3.9.6 SER/SSER Impact N 3.11 D- 14 3 Correct the lower limit operating relative humidity from "20 percent" to
" Uncontrolled".
Correction The environment qualification requirement for the CPSES EQ program is based on the upper limit of 100% relative humidity requirements in the harsh environment category. Lower hm;t operating relative humidity has never been -
an environment qualification parmeter and was added to be consistent with identification of a numerical lower limit. This lower limit was based on engineeringjudgement but this is not consistent with the CPSES design, This change is consistent with various FSAR sections such as 3.1 I D.1, item 'd' and Table 9.4-2. Only the Control Room equipments are qualified to 50 % realtive humidity which is under mild environment category and humidity controls are employed to monitor and control the relative humidity in the Control Room..
Change Request Number S A 137 . O Related SER . 3.11 SSER . 26 Section: 3 *.1 SEIUSSER Impact N
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 20 f as amendr.5D Group Description ficction.
4.1- 1 4 Clarification The descriptions apply to all core configurations, not just the initial core.
Change Request Number SA 142 . O Related SER : SSER : Section:
SER/SSER 1mpact N 4.2- 4 4 Revise value of strain on clad for Siemen's fuel.
Revision Siemen's fuel allows for a strain on the clad up to 1%.
Change Request Number SA 100 . 19 Related SER : SSER - Section:
SER/SSER Impact N 4.2- 12 4 Additional control rod design detail is add d to the FSAR Add nominal makeup of Ag-In-Cd and length of control rod.
Clarification This design information is not required in the Improved Technical Specifications. Therefore, this information is included as part of tiic FSAR.
Change Request Number SA 61 . 1 Related SER SSER Section:
SEIUSSER Impact N 4.2- 15 3 llelical spring in the fuel rods may be made of .:ainless steel or Inconel.
Update Modification notes that the helical spring in the fuel rods may be made of stainless steel or inconel. depending on the fuel vendor..
Change Request Number SA 100 . 6 Related SER ' SSER- Section:
SEIUSSER impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DirrAILED DESCRIPTION Prefix Page Page 21 f as amended) Group Descrintion Section.
4.2 17 4 Fuel assembly top noule flow penetration.
Clarification The change notes that, depending on the fuel vendor, the flow penetrations in the fuel assembly top nonic are not necessarily round.
Change Request Number SA 100 . 7 Related SER SSER. Section:
SER/SSER impact N 4.2-24 2 Page 25 Correct discussion of secondary source assemblies.
Correction Expands thJ discussion on secondary source assemblics to cover the existing sources in Unit 2 Cycle 4 as well as the new sources in Unit 1 Cycle 6.
Change Request Number SA 100 . 8 Related SER : SSER : Section:
SER/SSER impact N 4.3- 5 2 Clarify 95% probability Clarification Clarify that the design basis is that with at least a 95 percent confidence level, there is at least a 95 percent probability that either the fuel peak power will not cause melting or that the fuel will not operate with a power distribution that results in departure from nucleate boiling. His is consistent with FSAR Section 4.4 and Chapter 15.
Change Request Number SA 100 . 9 Related SER , SSER Section:
SER/SSER 1mpact N 4.3- 6 2 Remove 75 PCM/sec reactivity change.
Update The specific value for maximum reactivity change rate for accidental withdrawal of control banks is determined for each cycle and verification performed that the peak heat generation and DNilR do not exceed the maximum allowable at overpower conditions. This verification is performed using methodologies approved in Technical Specification 6.9.1.6b for preparation of the Core Operating Limits Report.
Change Request Number SA 100 . 10
Attachment to TXX-98015 CPSES - UPDNTED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAII.ED DESCRIPTION Prefix Page Page 22 (as amended) Qgwp 1)ng.ription Section.
Related SER , 6.2 SSER - Section:
SER/SSER impact N 4.3- 7 4 Pages 33 & 34 Clarify the specific location of the shutdown margin requirements.
Clarification 1he Technical Specifications now refers to the Core Operating Limits Report for specific shutdown margin requirements. " Technical Specifications" is replaced with " Core Operating Limits Report" to provide the direct location of the shutdown margin requirements.
Change Request Number S A 124 . I Related SER , SSER Section:
SEIUSSER impact N 4.3-25 4 Editorial Change " measure" to " measured."
Change Request Number SA 142 O Related SER SSER : Section:
SEIUSSER Impact N 4.3-26 4 Editorial Change " methodology is" to " methodologies."
Changs Request Number SA 142 O Related SER . SSER Section:
SER/SSER impact N 4.3-11 4 Figure Clarify figure legend.
Clarification Replace "Unrodded core" with " Group D at 35%" in the legend of Figure 4.3-1I for consistency with the text discussions in Section 4.3.2.2.2.
Change Request Number SA 100 . 13 Related SER . SSER Section:
SEIUSSER impact N
_ ___.. . .__m., .-.~ .__ _ _. _ __ _ . ___ _ _ . . ~ _ _ _ - _ - _ _ ~ . . _
P 4
Attachment to TXX-9 sol 5 I
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT j AMENDMENT. 95 l DETAILED DESCRIPT10N i
Prefix Page Page 23 ,
__(as amended) Onne Description Section. j 4.3 14 4 ,
Figure Editorial 1.abel on figure is incorrect. He label reads "AO = 15.32;" should read "AO =
-15.32."
Change Request Number SA 142. 0 l Related SER : SSER - Section:
SER/SSER impact N 4.3 29 4
- Figure Clarify figure legend.
Clarification The legends of these figures are changed to note that the values in the Figures are " typical" for consistency with the text discussions (e.g., Sections 4.3.2.3.5 and 4.3.2.5).
Change Request Number S A 100 . 14 Related SER : SSER : Section:
SER/SSER impact N
+
4.3-33 4 Figure Clarify figure legend Editorial He legends of these figures are changed to note that the values in the Figures
, are " typical" for consistency with the text discussions (e.g., Sections 4.3.2.3.5
, and 4.3.2.5).
Change Request Number SA 100 . II Related SER : SSER . Section:
SER/SSER Impact N 4.3-37 4
-Figure . Clarify figure legend.
Editorial ne legends of these figures are changed to note that the values in the Figures
- are " typical" for consistency with the text discussions (e.g., Sections 4.3.2.3.5 g and 4.3.2.5).
Change Request Number SA 100 . 2 Related SER .. SSER - Section:
SER/SSER Impact N 4
,>~ - -
e . , . . - - - , r n., -- . . . - - - - - - -
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Prefix Page Page 24 (as amendedi Omup Descrirition Section.
4.3-40 4 Figure Restore figures 4.3-40. His figure is still referenced in the text.
Editorial Figures 4.3-40 is still referenced in the FSAR text. The discussion regarding this figure still remains valid:hence the figure still should be included in the FSAR.
Change Request Number SA 2 .I Related SER : SSER Section:
SER/SSER Impact N 4.3-41 4 Figure Restore figures 4.3-41. His figure is still referenced in the text.
Editorial Figures 4.3 41 is still referenced in the FSAR text. The discussion regarding this figure still remains valid:hence the figure still should be included in the FSAR.
Change Request Number SA 2 .O Related SER - SSER. Section:
SER/SSER Impact N 4.4- 13 4 Page 14 Remove specific section of Technical Specification Revision identifying the specific section of the Technical Specifications for handling Quadrant Power Tilt Ratio is unecessary.
Change Request Number EA 100 . 15 Related SER SSER , Section:
SER/SSER Impact N 4.4-17 2 Provide typical RCS Temperature and power curves for Units I and 2.
Revision Figures 4.4-21 A and 4.4-21B previously provided the relations between various RCS temperatures and power, based on the RCS flow rate assumed in the accident analyses. This value (although reletively constant) is subject to changes from cy le to cycle, as described in Appendices 4A and 48. Only
- Tavg relationship to power is cycle-independent. Therefore Figure 4.4-21B was deleted, Figure 4.4-21 A was renumbered to 4.4-21, and both the text in Section 4.4.3.4 and the legend in Figure 4.4-21 are annotated to indicate that the curves represent typical values.
- _ _ . _ _ _ . . . . _ . ~ _ _ _ . - . . . _ . _ _ . . _ . _ _ . - _ _._..___._ _ _ _ . . _ . _ . _ - . . . _ .
Attachment to TXX 98015 l
c CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT-AMENDMENT. 95 DETAILED DESCRIPTION 2
2 Prefix Page Page 25 ,
- (as amended) ' Group Dsseription Section: ;
Change Request Number S A 100 . 16 Related SER : SSER : Section:
SER/SSER Impact N ,-
4.4-21 2 Figure Provide typical RCS Temperature and power curves for Units I and 2.-
Revision See description for Page 4.4 17.
Change Request Number SA 100 . 17
- Related SER . SSER : Section:
! SER/SSER impact N 4A-1 2 Pages 2 thru 27 Update for Unit 1 Cycle 6.
, Revision
, 'this appendix is replaced in its entirety to reflect the changes required for Unit -
I Cycle 6 operation.
Change Request Number S A 100 . I8 Related SER - : SSER : Section:
SER/SSER Impact N i .
, 4 A.2.1- 1 2
. Table Update for Unit 1 Cycle 6.
' Revision This Table is replaced in its entirety to reflect the changes required for Unit 1 -
Cycle 6 operation.
Change Request Number SA 100 . 0
=
Related SER : SSER : Section:
SER/SSER Impact N 4
4All-1 2 Table . Update for Unit i Cycle 6.
. Revision i This Table is replaced in its entirety to reflect the changes required for Unit I Cycle 6 operation.
Change Request Number SA 100 . 0 Related SER : SSER : Section:
SER/SSER Impact N-
1 Attachment to TXX-980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Prefix Page Page 26 (as amended) Group Descrintion Ssetion:
4 A.2.2- 2 2 Table Update ihr Unit i Cycle 6.
Revision This Table is replaced in its entirety to reflect the changes required for Unit I Cycle 6 operation.
Change Request Number SA 100 . O Related SER : SSER : Section:
SER/SSER impact N 4 A.2.2- 1 2 Figure Update for Unit I Cycle 6.
Revision "Ihis Figure is replaced in its entirety to reflect the changes required for Unit I Cycle 6 operation.
Change Request Number SA 100 . O Related SER SSER. Section:
SER/SSER Impact N 4 A.2.2- 2 2 Figure Update for Unit I Cycle 6.
Revision This Figure is replaced in its entirety to reflect the changes required for Unit 1 Cycle 6 operation.
Change Request Number S A 100 . O Related SER : SSER- Section:
SER/SSER impact N 4 A.2.2- 3 2 Figure Update for Unit 1 Cycle 6.
Revision This Figure is replaced in its entirety to reflect the changes required for Unit i Cyc!c 6 operation.
Change Request Number SA 100 . O Related SER , SSER : Section:
SER/SSER Impect N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI'NDMENT. 95 DETAILED DESCRIPflON Prefix Page Page 27 (as amended) Qump Description Section:
411- l 2 Pages 2 thru 29 Update for Unit 2 Cycle 4.
Revision Appendix 41) is replaced in its entirety with a new appendix applicable to Unit 2 Cycle 4.
Change Request Number SA 142 . O Related SER : SSER. Section:
SER/SSER impact N 411.2.2- l 2 Table Update for Unit 2 Cycle 4.
Revision Appendix 411 is replaced in its entirety with a new appendix applicable to Unit 2 Cycle 4.
Change Request Number SA 142 . O Related SER : SSER , Section:
SER/SSER Impact N 4 11.2 .2 - 2 2 Table Update for Unit 2 Cycle 4.
Revision Appendix 41) is replaced in its entirety with a new appendix applicable tc Unit 2 Cycle 4.
Change Request Number SA 142 O Related SER : SSER. Section:
SER/SSER 1mpact N 4 11.2 .2 - 1 2 l'igure Update for U.iit 2 Cycle 4.
Revision Appendix 41) is replaced in its entirety with a new appendix applicable to Unit 2 Cycle 4.
Change Request Number SA 142 . O Related SER SSER* Section:
SER/SSER Impact N
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 28 (ns amendtd) Croup Descrintian Section.
4 11.2.2 - 2 2 l'igure Update for Unit 2 Cycle 4.
Revision Appendix 4tl is replaced in its entirety with a new appendix applicable to Unit 2 Cycle 4.
Ch.aige Request Number SA 142 . O Related SER . SSER . Section:
SI:R/SSI.R impact N 4 11.2.2 - 3 2 l'igure Update for Unit 2 Cycle 4.
Revision Appendix 411 is replaced in its entirety with a new appendix applirste to Unit 2 Cycle 4 Change Request Number SA 142 , O Related SI:R : SSER Section:
SER/SSER Impact N 5.1 - 9 4 Change Veritrak model number from 67 to 76.
Editorial Numbers were transposed, correcting error.
Change Request Number S A 64 .I Related SER SSER Section:
SER/SSER Impact N i 5.1- 1 4 Sheet i Table Add information on RCS design pre .ure, system water and steam volume, and system design temperature which is currently contained in section 5.4 of the Te .mical Specifications.
Addition This information is intended to be relocated from the Technical Specifications in accordance with 1.AR 97-001. The information will be added to the FSAR per this change.
Change Request Number SA 62 ,I Related SER : SSER - Section:
SER/SSER Impact N l
l
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAll.ED DESCRIPTION Prefix Page Pege 29
{ar amended) Dimm Iloniction Section.
5.2- 8 4 Page 12 Clarification of the operation of the RilR suction relief valves as low temperature overpressure protection.
Clarification CPSES' response to G1,90-06, clarified the use of the RIIR suction relief valves for 1. TOP. This change is clarifying the SAR infonnation in a similar manner.
Change Request Number SA 140. 1 Related SER . SSER : Section:
SER/SSER 1mpact N 5.2- 10a 3 Pagei1 Revise wording to allow operation with only one RilR relief valve aligned to the RCS for low temperature overpressure protection during water solid operations. In accordance with Technical Specifications the Pressurlier PORV may be used as the alternative device.
Revision Minor editorial changes are made on page 5.2 10a. On page 5.2-11, a change in wording in paragraph *a' is made to allow only one RllR inlet line from the RCS to be aligned during water solid operation if desired.
Change Request Number SA 85 .I Related SER : SSER- Section:
SER/SSER 1mpact N 5.2- 31 2 Clarify Section 5.2.4, " Inservice Inspection and Testing of the Reactor Coolant Pressure floundary". Clarify that during the Unit 2 preservice inspection, Class I systems were inspected using ASME Code Case N-408 and the reactor vessel was m accordance with the 1980 Edition.
Clarification These changes are consistent with the as-built plant. This clarification is also consistent with the NRC Supplemental Safety Evaluation 26, Section 5.2.4.2, Change Request Number SA l 15 , 4 Related SER
- SSER
- Section:
SER/SSER impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDA.ENT - 95 DETAILED DESCRIPTION Prefix Page Page 30 (Atamended) Onn!D Descrintiou SfdicD; 5.2 31 2 Clarify the discussion regarding the design of the reactor pressure boundary, components, equipment layout, and support structures with respect to accessibility. The words "to the extent practical" are added.
Clarification This changes represents the as-built plant is consistent with the statements from NRC SSER 4, Section 5.2.4.
Change Request Number SA 115 . 5 Related SER : 5.2.4 SSER : Section:
SER/S'iER impact N 5.2-42 4 This change revises the reference to Chapter 16 to directly refer to the Technical Specifications.
Clarification Chapter 16 no longer contains the current Technical Specifications. Therefore, references made to FSAR Chapter 16 are removed and revised to refer directly to the Technical Specifications.
Change Request Nur: her SA 125 . 1 Related SER . SSER - Section:
SER/SSER 1mpact N 5.2- 4 R 4 DM 95-013 and DM 95-014 have provided plant computer inputs for the monitoring of containment dewpoint temperatures, as well as nuxiliary and main condenser temperatures. These computer points are replacing existing recorders. Reference to the plant computer inputs is included and reference to the recorders is deleted.
Correction include reference to the plant computer inputs for monitoring comainment dewpcint temperature and delete reference to the previous recorders.
Change Request Number S A 100 . I Related SER . SSER - Section:
SER/SSER 1mpact N
Attachment to TXX-98019 1
i CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDME:NT 95 DETAILED DESCRIPTION Prefix Page Page 31 LauunsDdsd) Groen Description Section. ,
5.2- 5 4 Table Remove referenew to electrical conductivity, solution pil and total susupended solids and any limits associated with each parameter, Modify the pil control
~*
agent section to reficct the desired pil operathip. range. Modify the toric acid section to reficct current core operatinF "7 meters.
Updaie
'the parametert have been modified for CPSES current core designs and k chemirary operating parameters in accordance with EPRI guidlines for PWR Primary Water Chemistry.
Change llequest Number S A 99 .O Related SER . SSER Section:
SER/SSER Impact N 5.3-23 4 The change removes the administrative limits on RCS heatup and cooldown rates. Removal of the administrative limits allows plant operation within the NRC approved Technical Specification heatup and cooldown rates.
Revision Revise wording of paragraph 5.3.3.1 to point to the Technical Specifications for RCS heatup and cooldown rates. This clumge is acceptable based on the NRC approvea Technical Specification heatup and cooldown rates.
Change Request Number S A R6 .1 Related SER SSER Section:
SER/SSER impact N 5.4-26 4 Correct editorial reference to Technical Specification section.
Editorial Reference was incorrect based on CPSES Technical Specification numbers being difTerent from standard technical specifications.
Change Request Number S A 122 . 1 Related SER , SSER
- Section:
SER/SSER Impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Page 32 f as amended) Group Descrintion Section.
SA.59 4 The word 'rettore' is added for clarification of the ECCS capability.
Clarification Clarification only, no change in meaning.
Change Request Number SA 68 .I Related SER - SSER , Section:
SER/SSER 1mpact N 5.4- 75 4 Remove specific reference to pressurizer heatup/coodown administrative limit. Limit is controlled by Technical Specification limit.
Update lhe Technical Specifications impose limits on the heatup and cooldown rates of the pressurizer. These limits are acceptabe to the NSSS supplier and have received approval by the NRC. Stricter administrative limits are not required in the Safety Analysis Report.
Change Request Number SA 124 . 1 Related SER
- SSER Section:
SER/SSER Impact N 5A-1 1 Page 6 This change revises information with respect to the 13TP RSB 5 1 basis for sizing of the air reservoirs associated with operation of the SO power operated atmospheric relief valves. The change is to identify for IITP conformance that once the air supply is exhausted, manual control is available.
Correction The change is to delineate the actual CPSES as designed plant. The PORV air reservoirs are sized for 15 operations which should provide a nominal 4 bours of operation. Local manual control was previously dtscribed in Section 9.3.1.2.
Change Request Number SA 38 .I Related SER
- SSER Section:
SER/SSER impact N l
I 1
Attachment to TXL98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT I AMENDMENT 95 DETAILED DESCRIPTION Pre 0x Page Page 33 (as amended) Drsp Descrintion Senten; 6.25 4 Pages 45 and 46 Clarification The discussion on the inital steam generator water and steam inventories is generalired. A common mialysis for steam line break mass and energy releases is used for both units. The steam generator inventories were determined to be bounding for both units. Related references (Nos. 17,18,19, 20 and 22) are also deleted.
Change Request Number SA 142 . O Related SER . SSER Section:
SER/SSER impact N 6.2- 9 4 Also pages 10,30,31 Editorial Changes provided to improve grammar and readability.
Change Request Number SA 142 O Related SER SSER- Section:
SER/SSER impact N 6.2- 10 4 ClariGcation Changes made to properly characterire the containment as a " dry containment" vs. a "drywell" as used in the containment ar alysis computer code.
Change Request Number SA 142 . O Related SER SSER Section:
SER/SSER Impact N 6.2-29 4 Editorial Change " exits" to " exists."
Change Request Number SA 142 . O Related SER
- SSER : Section:
SER/SSER Impa.:t N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALY3IS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 34 (BlamtDsicsD Oroup Description Section.
6.2-30 4 Page 31 Clarification Clarify the two distinct meanings of" blowdown" as used in these paragraphs. Also, clarify that the feedwater line isolation signal is not direct, but is derived from the Safety Irdection Actuation Signal. as described in Chapter 7 and Technical Specification 3.3.
Change Request Number SA 142 . O Related SER SSER : Section:
SER/SSER Impact N 6.2- 32 4 Clarify description of feedwater control salves.
Clarification 1he subject feedwater control valves are classified as NNS and are located outside the ASME boundary. They are installed and maintained as NNS valves lhe original statement related to procurement.
Change Request Number S A 61 .1 Itclated SER - SSER - Section:
a ER/SSER Impact N 6.2-32 4 f ditorial Correct inconsistency with the Westinghouse safety analysis standard included in the references.
Change Request Number SA 142 . O Related SER SSER Section:
SER/SSER Impact N j 6.2-33 4 Editorial Clarify that the analysis is terminated at 600 seconds.
Change Request Number S A 142 . O Related SER . SSER . Section:
SER/SSER Impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Page 35 (as arnendedl Group Description Section.
6.2-38 2 Revision Changes required because the mathematical models used for the mass and energy release calculations are no longer the same models used for Appendix K LOCA analysis as described in FSAR Section 15.6.5. Instead, the models are referenced to an existing reference, WCAP 8204, which includes the required discussion. The change is considered trivial because the information was previously contained in Chapter 15 and the essential elements of the change are being retained in the referenced document.
Change Request Number SA 142 O Related SER . SSER : Section:
SER/SSER Impact N G.2- 49 4 Clari0 cation Section 16.2 of the FS AR is more commonly known as the plant Technical Specifications.
Change Request Number SA 142 . O Related SER - SSER . Section:
SER/SSER 1mpact N 6.2- 64 3 Revises discussion of performance curves and NPSil requirements for the Containment Spray pumps to reficct type ofinformation provided by vendor when the impellers for the pumps were replaced.
Clarification The vendor provided performance curves and NPSil requirements for the original Containment Spray pumps, however, when the impellers were later replaced, the vend,r did not provide shop test curves but did provide " field verified" or " guaranteed" pump curves. This change allows for the use of other vendor supplied curves that demonstrate / predict appropriate pump performance.
Change Request Number SA 143 . O Related SER . SSER- Section:
SER/SSER 1mpact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION
> Prefix Page Page 36 (as amendc<D gmm Dnpfjpling Ssq11ca.
6.2- 77 2 Page 78 Changes the FSAR section 6.2.4.1.3.10 pertaining to Airlock Equalization Valves and Unit I, to indicate that the power supply is tripped via an 51 signal from both trains in order to preclude post accident environmental conditions inside containment from causing spurious opening of the airlock doors / equalization valves.
Revision Tripping power to the hydraulic pump following an accident resulting in a safety injection signal meets the redundancy requirements oflEEE 279 Change Request Number SA 83 . 2 Rc! ted SER : 6.2 SSER : 22 Section: 6.2 SER/SSER impact N 6.2- 77 2 Page 78 Changes the FSAR section 6.2.4.1.3.10 pertaining to Airlock Equalization Valves and Unit 2, to indicate that the power supply is tripped via an Si signal from both trains in order to preclude post nccident environmental conditions inside containment from causing spurious opening of the airlock doors / equalization valves.
Revision Tripping power to the hydraulic pump following an accident resulting in a safety irpection signal meets the redundancy requirements ofIEEE 279.
Change Request Number SA 134 . I Related SER . 6.2 SSER . 22 Section: 6.2 SER/SSER impact N 6.2- 81 2 Add reference to FSAR Table 17A 1.
Clarification ne ASME code applicability is documented in Table 17.\ 1 as noted in Table 3.2- 1. A.
Change Request Number SA 84 .I Related SER . SSER : Section:
SER/SSER 1mpact N 3
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DFTAILED DESCRIPTION Prefix Page Page 37 (as amended) Group Descrintion Section.
6.2- 81 4 Change " Process and Sampling System" to " Process Sampling System."
(Delete the word "and")
Editorial Editorial correction to match the correct name of the Process Sampling System.
Change Request Number S A 96 .I Related SER SSER* Section:
SER/SSER Impact N 6.2 84 4 Correct the sentance from " ..is seismic Category I to.. " to " ..is qualified to seismic Category I by analysis .
Clarification Clarification that the pipe is qualified to seismic Category I by analysis. This clarification does not change the technical intent.
Change Request Number SA 135 . I Related SER 6.2 SSER
- Section:
SER/SSER 1mpact N 6.2- 86 2 Pages 87 and 124 thru 135 CPSES Tech Spec amendment endorsed 10CFR50 Appendix J, Option 11.
1hese enanges reflect the new requirements of 10CFR50 Appendix J, Option 11, Reg. Guide 1.163, and industry guidance NEl 94-01.
Revision Revise leakage rate testing to reficct the incorporatio.t of 10CFR50 Appendix J Option 11 as allowed by Technical Specification 6.8.3g. See also 6.2-125 thru 6.2-134 Change Request Number SA 68 .O Related SER : SSER Section:
SER/SSER impact N l
i
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 38 f as ame.ndg_d] Group DEKIintiq0 Section; 6.2 91 4
- Ihh change removes the reference made to Chapter 16 as containing the Techr.ical Specifications.
Clarifica ion Chapter 16 no longer contains the current Technical Specifications. Therefore, references made to FSAR Chapter 16 are removed and revised to refer directly to the Technical Specifications.
Change Request Number SA 125 . 2 Related SER , SSER : Section:
PER/SSER Impact N 6.2- 099 3 Updates the weight of tirconium cladding.
Update The increased amount of cladding is a function of the fuel type and the 18 month fuel cycle.
Change Request Number SA 108 . I Related SER SSER Section:
SER/SSER Impact N 6.2- 102 2 Revises the hydrogen generation rate from core and sump radiolysis.
Revisica A revised hydroFen generation analysis was performed due to:
- 1) increased weight of zircaloy cladding
- 2) new assumption of a 5% zirc-water reaction instead of 1.5%
- 3) use of current Post-LOCA containment temperature profile
- 4) updated core and sump water energy deposition reflecting the extended fuel cycle
The revised analysis was performed by westinghouse in WCAP 15848 as a bounding analy-is consistent with the requirements of RO 1.7. The analysis concluded that ' <hile the Post-LOCA hydrogen generation rate increased, the hydrogen concectration is maintained well below the 4 v/o lower explosive.
limit.
Change Request Number S A 108 . 2 Related SER . SSER , 22 Section: 6.2 SER/SSER Impact N
. _ _ ... . . - . . . _ . _ - . _ _ _ _ .. . _ . . _ _ . . _ . . _ _ . _ ~ . . . _ . _ _ ...___ _ _ . _ _ - . . _ .
_ _m Attachment to TXX 98015 - ,
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION -
l Prefix Page ' Page 39
- (as vnended! OmE lhEIip.1120 Section:
- 6.2- 106 2_
Revises the required Post LOCA start time >f:he hydrogen purge system and the maximum hydrogen concentration reached.
Update The increased hydrogen generation rate resulting from the new Post-LOCA hydrogen analysis requires an earlier start of the purge system to maintain the ,
hydrogen concentration belovc EL. Also see discussion for page 6.2-102.-
Change Request Number SA 108 . 3 Related SER : SSER : 22 Section: 6.2 SER/SSER impact Y SSER 22 contained results of the previous Post-LOCA hydrogen analysis.
6.2-108 4 Reword sentence regarding testing of system components for clariGcation.
Clarification Component level tests are performed to assure readines .
Change Request Number SA 134 . I Related SER : SSER : Section:
SER/SSER Impact N 6.2- 110 2 Differential pressure swithches only exist across the exhaust nitration units.
Clar1 cation 1 i Clarifies the location of the dolfierential pressure switches.
Change Request Number SA 134 , 2 Related SER SSER : Section:
l SER/SSER impact -N 4
6.2- 112 2
> Deletes reference to zirc-water reaction, being less than 0.3%.
Revision -
l The revised assumptions for the Post LOCA hydrogen analysis conservatively use a 1% zirc-water reaction. Also see discussion for page 6.2102.
Change Request Number S A 108 ' 4 Related SER : SSER : 22 Section: 6.2 SER/SSER Impact Y SSER 22 was based or the previous Post-LOCA hydrogen analysis.
._ i i
Attachment to 'l XX 980l$
I i
CI'SliS - UPDATIID 1 lNA1. SAltliTY ANAL,YSIS Rill' ORT AMI:14Dhti r4T
. 95 Dirl'All.1-:D DI:SCRIPilON Pret x Page Page 40 littettDntdtd) OmuD Dottipin'D StriipE 6.2- 1 i 3 3 Adds new reference l10).
Addition Reference [10] is the new Westinghouse Post-1.OCA hydrogen analysis. Also see discussion ibt page 6 2102.
Change Request Number S A 108 . 6 Related SI:R : SSI;R : Section:
Sl:lUSSI R Impact N 6.e.I13 2 Page 114 llevises the calculated rirc. water reaction.
Revision llased on the assumed 1% rite water reaction and the RG l.7 margin of a factor of 5, the new Post 1.OCA hydrogen analysis uses a 5% rirc. water teaction. Also see discussion on page 6.2102.
Change Request Number SA 96 - 108 . 5 Related SI:R . SSI:R . 22 Section: 6.2 SI:R/SSI:lt impact Y SSI:R uncha 1.5% reaction based on previous Post 1.OCA hydrogen analysis.
6.2- 1 I R 2 Deletes assumption that noble gas remain in the core.
Revision The new Post lA >CA hydrogen analysis uses the assumptions of the
' LID-14844 model which assumes the noble gases escane hno the containment.
Also see discussion for page 6.2-102.
Change Request Numter S A 96 - 1011 R Related SI:R SSI'.R : Section:
SI:lUSSI:R impact N 6.2- I I R 4 Page 120 Revises full core irradiation history assumption for total decay ci ergy from 650 days to
- operation with an extended fuel cycle" Revision This change removes an unnecessarily conservative assumption since the current fuel cycle is 1R months. Aho see discussion for page 6.2102.
Change Request Number SA 108 . 7 Related Sl:R : SSI:R : Section:
SER/SSI R 1mpact N
Attachtnent to TXX 980l$
l CPSlis - UPDATED FINAL SAFETY ANALYSIS REl' ORT AMI;NDMI:NI' 95 DI:TAILI D DI;SCRIPilON Prefiz Page Page 41 (m.mutaduD Ceue Dunhuien sction:
6.2 124 2 Revises teforence 10.
Revision References the new Westinghouse topical report for the revised Post l.OCA hydrogen analysis. Also see discussion for page 6.2102.
Change Regt. cst Number S A 108 . 10 Related SI:R : SSI:R , Section:
SI:lVSSI:R impact N 6.2.4 1 2 Sheet 7 lable Revisc 10 inch containment penetration from " Spare"to " Containment leak Rate test Depressurization" penetration.
Revision 1he containment penetration is being changed for use during II.RT and for cable feed thru during nonnat plant outage activitics.
Change Request Number SA 97 - 31 . 1 Related SI;R SSI:R : Section:
SI:R/SSI:R 1mpact N 6.2.4- 1 4 Sheet $
I nble Clarify main penetration 1. A 2 Mil-0009 with tagged labels for sub-components.
Clarificution
'the Reactor fluildmg Maintenance penetration Mil-0009 consists of a 12 inch capped pipe sleev with two 2 inch and 1 1/2 inch pipes penetrating the cap. ,
1:ach pipe has a valved test connection and is blind flanged on cach end.
1hese maintenance penetrations are used during outages and work orders need to clearly identify pipe penetrations.
Change Request Number SA 129 . I Related SI:R : ESI:R , Section:
SI:R/SSI R Impact N
Attachment to TXX.98015 i
CPS!!S - UPDATliD FINAL SAFIITY ANALYSIS RiiPORT AMI:NDMI:NT. 95 Ol: Tall.1:D DI: SCRIP 110N Prefia Page Page 42 (alluntildtd) fltimp DSiEIJPilnD Strik!E 6.2.4 2 4 Sheet 13 lable Cortcet the direction of test for llV.5536 from *NO" to "Yl:S" and for llV 5537 from "NO" to "YI:S".
IMitorial 1.ditorial . typo enor. This change does not change the technical function of the valves and are 6pnsistent with the flow diagram M10301.
Change Request Number SA -97 135. 2 Itclated SI:R 6.2 SSI:R Section:
SI R/SSI:R linpact N 6.2.4 2 1 Sheets I and 2 1able 2 IIV-24521 and 2 IIV.2452 2 the steam admission valves to the turbine driven auxiliary feedwater pump, are being swapped with tespect to which valve is associated with each steam line for train considerations.1his chanpc resulted in the valves being placed on different steam lines and thus difTerent containment penetntions.
Revision 1his change is part of the corrective action prescribed to the condition reported in 1.1:R 197 001-00. The modification was required to restore the design basis for operation of CPSI'3.1hese changes have tv.sen implemented for Unit 2 only at this time.
Change Request Number SA .97 27 .3 Related Sl;it
- SSI:lt . Section:
SI:R/SSI:R 1mpact N 6.2.4 2 2 Sheet 8 1 able Revisc 10 inch containment penettr. tion from " Spare"to " Containment leak Rate test Depressurliation" penetration, Revision 1he containment penetration is being changed for use during II.RT and for cable feed thru during normal plant outage activities.
Change Request Number SA 31 .1 Related SI:R . SSI:R . Section:
SI:R/SSI'.R Impact N
Attachment to TXX 980l$ l l
CPSliS - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAll.1:D DI SCRIPilON l'refin Page Page 43 latammdnt) iheup DnUjril0D Section.
6.2.4 2 4 Sheets 5 and 6
'I able Clarify main penetration l & 2 Mil 0009 with tagged labels for sub-components.
Clar10 cation See description for Table 6.2.4 1, Sheet $
Change Request Number S A 129 . 2 Related SER : $$l:R . Section:
SI:R/SSI R impact N 6.2.4 2 2 Sheet iR Table Adds note 16 to end of Table.
Addition Valves MS-0101 and MS-0128 have been added to Table 6.2.4 2. Note 16 esplains the backup containment isolation function of these valves and refers to l'5i AR Section 9.3.1.2 for additional discussion.
l'or additional information see the detailed description for Change Request Number SA 96131.1 (Table 3.911 10, Sheet 1), SA 96131.2 (Table 6.2.4 2, Sheet 1), and SA 96131.3 (Table 6.2.4 2. Sheet 2).
Change Request Number SA 131. 4 Related SI:R : 6.2.3 SSER : Section:
SIER/SSI:R impact N 6.2.4 2 2 Sheet 2 Table Adda mam steam block valve (MS-0128) to Table 6.2.4 2, " Containment isolation Valving Application".
Addition l'orjustification see the detailed description for Change Request Number SA 96131.1 on Table 3.911 10, Sheet 1.
Change Request Number SA 131. 3 Related SER 6.2.3 SSER : Section:
SI:R/SSER Impact N
,y , - . -- --
-- - - - - ~___- .. . . - - . - . _ . - .-- -_ _ . _ _
Attachment to TXX.916015 ,
l l
CPSliS - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMI:NT. 95 DETAILED DLSCRIPTION Prenx Page Page 44 i
(.tLi.htatuded) OmuD Dnalpli2D Section.
]
6.2.4 2 2 Sheet I ;
- Table Adds main steam bkick valve (MS-0101) to Table 6.2.4 2, " Containment l Isolation Valving Application".
, Addition )
I'orJustincation see the detailed description for Change Request Number SA 96131.1 on l able 3.911 10, Sheet 1.
Change Request Number SA 131, 2 Related SER : 6.2.3 SSER : Section:
Sl:R/SSER Impact N 6.2.4-3 4 Sheet 7 Table Clarify main penetration 1. A 2-Mil-0009 with tagged labels for kub-comp (ments.
Clarlucation See description for Table 6.2.4 1. Sheet 3 Change Request Number SA 129 , 3 i
Related SER : SSER + Section:
SI:lWSER impact N 6.2.4 3 2 Sheet 9 1 able Revise 10 inch containment penetration from " Spare"to " Containment Leak Rate test Depressuritation" penetration.
Revision The containment penetration is being changed for use during ILRT and for cable feed thru during normal plant outage activities.
Change Request Number SA 31 .0 Related SER : SSER : Section:
SEIUSSER Impact N 6.2,4-3 i Sheets 1 and 3 Table 2.llV.2452 1 and 2-IIV.24$2-2, the steam admission valves to the turbine driven auxiliary feedwater pump, are being swapped with respect to which valve is associated with each steam line for train considerations. This change resuhed in the valves being placed on different steam lines with difTerent train power supplies.
Revision This change is part of the corrective action prescribed to the condition reported in LER 197 00100. The modincation was required to restore the design basis for operation of CPSES These changes have been implemented for Unit 2 only at this time.
Attachment to TXX 980ls CPSliS - UPDATl!D FINAL SAFliTY ANALYSIS Rl! PORT AMI.NDMI:NT. 95 DI:TAII.l~D Dt: SCRIP 110N I
Prefix Page Page 45 (as amendtd) Otnup Descrintion Section.
Change Request Number S A - 97 27 . 4 Related SI:R : S$l:R , Section: l SI:R/SSl31 Impact N l 4
6.2.4 4 2 Table CPSES Tech Spec amendment endorsed 10CI'R50 Appendix J, Option 11.
These changes reflect the new requirements of 10CI'R$0 Appendix J. Option 11 and Reg. Guide 1.163.
Revision See description for 6.2 86.
Change Request Number SA -96 68 .O Related SI:R : SSI:R - Section:
SER/SSliR impact N 6.2.4 6 2 Sheet 9 Table Revisc 10 inch containment penetration from " Spare"to
- Containment Leak Rate test Depressurintion" penetration.
Revision
'the containment penetration is being changed for use during ILRT and for cable feed thru during normal plant outage activities.
Change Request Number SA 31 .O Related SliR : SSI:R - Section:
SER/SSER impact N 6.2.4 6 4 Sheet 7 Table Clarify main penetration l & 2 Mil-0009 with tagged labels for sub-cornponents.
Clarification See description for Table 6.2.41, Sheet $
Change Request Number SA 129. 4 Related SER . SSI'.R : Section:
SER/SSER Impact N
Attachment to TXX.980l$
CPSliS - UPDATliD FINAL SAFliTY ANALYSIS REPORT AMENDMENT - 9$
DETAILLD DESCRIPTION Prefix Page Page 46 inumtndnl] Qinup Descripflen Stellen:
6.2.4.I 2 Sheet $ !
l'igure Adds new valve to Containment isolation Valving arrangment number 17.
Addition l'or justification $ce the detailed description for Change Request Number S A.96 131.1 (Table 3.911 10. Sheet 1).
Change Request Number S A - 96 131. $
Related SER : 6.2.3 $$1:R . Section:
SI:R/SSER Impact N 6.2.4- 1 2 Sheets i1 and 12
- l'igure Add isolation valves to the Personnel Air 1 ock barrel test connections and interior door seal test connections and to the timergency Air 1,ock barrel test connections.
Revision implementation of Appendix J Option 11 provides suggested test connection arrangements thrnugh ANSI /ANS $6.81994. A more conservative design test connection is now employed ibt barrel test connections in the Personnel Air 1 ock and the Emergency Air Lock.
Change Request Number SA 87 . I Related SI:R: SSI:R : Section:
.i SEIUSSER impact N 6.2.5 6 3 Table Change material description to " perforated stainless steel" Clarification Material for non safety system is specified more generically as just perforated stainless steel.
Change Request Number SA 134 . 3 Related SER : SSER : Section:
' SER/SSER Impact N 6.2.5 A- 1 2
'lable Revir.cs Post LOCA time-temperture profile, Revision Revised table is based on performance of new Pos'-LOCA hydrogen analysis with new assumptions. See discussion for page 6.2102.
Change Request Number S A 108 . 11 Related SER
- SSER : Section:
SER/SSER impact N
. _ _ _ . . _ _ _ __ _ __ __ .._ . . _ _ . . _ . . _ ~ _ . _ _ _ _ . _ _ _ ._ _ _ _ _ _ _ _
l j
Attachment to TXX 980l$
i CPSIIS - UPDATIID FINAL SAFIITY ANALYSIS RIIPORT AMI:NDMI:NT. 9$
DI: TAILED DESCRIPilON Preux Page Page 47 Dieur Don]Plinu Section. ,
hulamondt.d) 6.2.$ A. 2 2 Sheet I Table Revise parameters used to determine hydrogen generation.
Revision Revised table is based on performance of new Post.LOCA hydrogen analysis with new assumptions. Also see dircussion for page 6.2102.
Change Request Number S A 96 - 108 . O Related SER : SSI:R : Section:
SI:R/SSI:R impact N 6.2.$A 3 2 1 able Resiscs aluminum and rinc inventory.
Revision Revised table is based on perfonnance of new Post LOCA hydrogen analysis with new assumptions. See discussion for page 6.2102.
Change Request Number SA 108 . 13 Related SI:R . SSI:R : Sectioit:
SI:R/SSI;R impact N 6.2.$ A- $ 2 Table Revises core fissio.t product decay energy table.
~
Revision Revised table is based on performance of new Post LOCA hydrogen analysis with new assumptions. Also see discussions for page 6.2102 and page 6.2 120.
Change Request Number SA 96 - 108 . 14 Related SI R : SSI:R : Section:
SER/SSER impact N 6.2.$ A- 6 2 Table Revise Ossion product decay energy in sump solution.
Revision Revised table is based on perfonnance of new Post LOCA hydrogen analysis with new assumptions. Also see discussion for page 6.2102.
Change Request Number SA 108 . O Related SER : SSER : Section:
SEIUSSER Impact N
1 Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMl:NT- 95 Dl: Tall.I D DI SCRIPTION Prefix Page Page 48 Group Descrintion Section.
(at.nmcadtd) l 6.2.5 A- 5 2 l'igure Revise hyrdogen production rate curve.
Revision Revised figure is based on performance of new Post 1,0CA hydrogen analysis with new assumptions. Also see discussion for page 6.2102.
Change Request Number SA - 96 108 . 16 Related SI:R - SSI:R : Section:
sit.R/SSI:R impact N 6.2.5A 7 2 l'igure Revises the hydrogen accumulation from all sources curve.
Revision Revised figure is based on performance of new Post 1,0CA hydrogen analysis with new assumptions. Also see discussion for page 6.2102.
Change Request Number S A - 96 108 . 17 Related SI:R : SSI R : Section:
SI:R/SSI:R 1mpact N 6.2.5 A 9 2 l'igure Itevises contalment hydrogen concentration curve.
Revision Revir.ed figure is based on perfonnance of new Post 1.OCA hydrogen analysis with new assumptions. Also see discussion for page 6.2 102.
Change Request Number SA 108 . 18 Related SI:R , SSI:R : Section:
SI:R/SSI:R Impact N 6.3- 2 4 Delete reference to comparison of other facility designs.
I:ditorial Itditorial deletion.
Change Request Number S A 73 . 1 Related SI:R : SSI:R - Section:
SIIR/SSI:R impact N
Attachment to TXX 9801$
CPSliS - UPDATi!D FINAL SAFETY ANALYSIS REPORT AMIINDMI'.NT. 45 DITAILI:D Di'SCRIPTION Prefit Page Page 49 (Atamradul) GInuD DEKdP11ct) Settion.
6.3 $ 4 Page 9 Clarifies description of the mini flow operation related to the Centrifugal Chargmg Pumps during safety injection. Infortnation on the operation of the Alternate mini flow line is included.
Clarification 1hc alternate mini-flow was added to s t>SIIS prior to initial operation and was described in the l'SAR. Ilowever, sufficient detail on the mini flow operation did not exist in all sections.1his change is adding additional detail and clarification.
Change Request Number SA 96 73 . 2 Related SIIR : SSI:R : Section:
SI:lVSSIIR tmpact N 6.3. R 4 Revises the description of the potentialimpact of the failure of an RWST to HilR suction isolation valve to close for the initiation of cold leg recirculation.1he failure efrects are changed to clarify that the affected RIIR pump does not fait do to air intrusion.
Update Previous correspondence with the NRC (TXX 3400) which was accepted in SSI:R 1 Section 6.3.3, by the NRC describes the potential failure. This information was not adequately included in the l'SAR.1his change is being 4 made consistent with the prior correspondence.
Change Request Number SA 1 . I Related Si R : SSI R
- Section:
SI lVS$1:R impact N 6.3-18 4 Clarifies the function of valves 8806 and 8926 with respect to the isolation of i the RWST from the suction of the Safety Irdection pumps during 1:CCS recirculation.
Clarification 1he information had previously been reviewed by the NRC during the Question and Response phase ofI'SAR review. All infonnation was not adequately incorporated into Section 6.3 during the roll up of the Question and Resp (mses into the body of the l'SAR. The existing infonnation was correct but not complete.
Change Request Number SA 69 . I Related SI:R : SSI:R : Section:
SI:lVSSlik Impact N
f Attachment to TXX 98015 CPSIIS - UPDATliD FINAL SAFliTY ANALYSIS Rlil' ORT AMENDMI:NT. 95 DET AILI:D DESCRIP110N l'reux Page Page 50 (as amended) firata 11onipiten Ershem 6.3 29 4 Change teference to step 5 of Table 6.3 7 to step 6 of Table 6.3 7, 1:ditorial Step 6 was the correct teference.1his change is editorial.
Change itcquest Number SA I .2 Itelated SER : SSI R : Section:
SI:R/SSER impact N 6.3 30 1 Page 31 1he available and required volumes of RWST water for the completion of switchover from the RCS to the containment sump are updated.
Update lloth the available and required volumes of RWST water for the completion of switchover from the RCS to the containment sump have been recalculated for CPSES. These calculations were based on modincation of the switch,ver sequence, remodeling ofirdection from the RWST and instrument uncertainty over conservatisms.
Change itequest Number SA i .4 Related SER : SSI:R : Section:
SI IUSSER impact N 6.3- 30 4
. Changes the description of the RWST level instruments from eight to four channels.
Clarincation
'the RWST level function is provided by four instruments via cight bistables.
Rewording is for clarification of this functionality.
Change Request Number SA 97 - I .3 Related SER . SSER : Section:
SEIUSSER Impact N 6.3 32 4 Page 33
'the indications which the operator is monitoring are clarified. With respect to necumulator level it is recognlied that the level may be decreasing and not yet be oliscale for come I.OCAs.
Clarification "the discussions are clarined with no change in the meaning of what indications the operators are monitoring. 'ihe operator res.ponse is unchanged.
Change Request Number SA 68 .2 Related SER - SSER- Section:
Attachment to TXX 9fiol5 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DI:I AILED DESCRIPTION Page $1 Prefix Parc treatutnded) GINI! DnEIlclicIl bet tion.
SI:R/SSER 1mpact N 6.3 33 4 l Clarify that the Technical Specifications do not require that the pump be tagged. 'this is CPSES' current practice but the wording was confusing.
Clarification Clarify wording of tendering the high head safety injection pumps inoperable Change Request Number SA 119. O Related SI;R : SSI:R t Section:
SEIUSSI;R impact N 6.3 34 4
'Ihe alignment ofI:CCS components in MODE 4 is clarified as to how the operator ensures availability for actuation.
Clarification The clarification does not change the operator response.
Change Request Number SA 68 .3 Related SER : SSI:R : Section:
SEIUSSER Impact N 6.3-36 4 and 37 Clarification 1he discussions on these pages typically echo discussions provided in Chapter 15 and were based on the original Westinghouse analysis methods. In order to minimlic duplication.the discussions on these pages are replaced by a reference to more appropriate sections of the l'SAR.
, Change Request Numbe- SA 142 . O Related SER : SSER : Section:
SEIUSSER Impact N
Attachnent to TXX 98015 CPSES - UPDATl!D FINAL SAFIITY ANALYSIS RIIPORT AMENDMENT 95 DETAILED DESCRIPilON Prefit Page Page 52 lat.mucudt.dj Group DsicIlption Section.
6.3 47 4 Add volume of RWST water for consistency with lechnical Specifleation liases.
Clarification 1he actual volume was added to clarify that the statement was referring to the same volume of water as referenced in the liases to Technical Specification 3.5.4.
Change Request Number SA - 97 = 101 I Related SER : SSER : Section:
SI:R/SSER Impact N 6.3- l 4 Sheet 4 Table Infbrmation regarding valves 8511 A/II and 8512A/Il is clarified.
Clarification 1his change is editorial for clarification. No technical information is being changed.
Change Request Number SA 73 .3 Related Sim : SSI:R + Section:
SER/SSER impact N 6.3- 3 4 Sheet i Table Move 8923 valves from the location of' safety injection pump suction from RWS1' to ' safety injection pump suction isolation valves'.
Clarification The 8923 valves provide isolation between the trains of safety injection and are not RWST isolation valves.
Change Request Number SA 69 .2 Related SER : SSER : Section:
SER/SSER Impact N 6.3- 3 4 Sheet 5 Table Infbrmation rega: ding valves 851i A/11 and 8512Allt is being editorial changed for consistent use of nomenclature.
Editorial Editorial update.
Change Request Number SA 73 4 Related SER : SSER : Section:
SER/SSER impact N
Attachment to TXX 980l$
C1'SliS - UPDATED FINAL SAFETY ANALYSIS Rl! PORT AMl:NDMI:NT. 95 ,
DI:TAILI:D DI.SCRIPIION Page $3 Prefis Page Oww Doctip.tkul Strliett; littamended) 6.3 7 i Sheets I snd 2 Table lhe sequence for cornpleting the switchover itom 1:CCS injection to cold leg recirculation are re vised based on the revision of the CPSI S I:mergency Operations Procedures.
(fpdate A complete review of the sequence and timing of the actions to complete switchover at CPSI:S resulted in changes to both the sequence and guidance for the operators.
Change Request Number S A 97 - I .$
Related SI:R : SSI:n : Section:
SI:lVSSI:R 1rnpset N 6.3 10 4 Sheets I thru 13 Tahic Additional inibnnation is being added Ibr valves 851I A/II and 8512A/II.
Other information has minor editorial corrections.
Clarification Clarification ofinfonnation w hich was previously less than comprehensive and editorial conections.
Change Request Number SA 73 .5 Related SI R
- SSI:R : Section:
SI:lVSSI:R impact N 6.3- 11 1 Tahle 'the table for RWST outflow assuming the single worst case failure has been replaced w 'h the current analysis.
Update CPS!:S has donc a thorough review of the RWST switchover from irticetion to recirculation. As part of this efTort, the analysis of the RWST outflow was reperfbnned with more detailed modeling. Additionally, the sequence of some swithover actions were modified as part of the analysis. The riev ta%* is a result of this elTort.
Change Request Number SA I .6 Related SI:R : SSl:R : Section:
SI lVSSl:R impact N i
i i
l'
1 Attachment to TXX 980l$
I CPSliS - UPDATIID FINAL SAltliTY ANALYSIS REPORT AMENDMI:NT. 95 DI:TAILI:D DLSCRIP flON Preflu Page page $4 (as nmindEO OIm!D DriCliP1120 SfEl.lutU 6.4 4 4 Add " Shift Manager's OIYice* in lieu of' Tile Room".
- Men's Toilet", and "Wornen's Toilet" in lieu of " locker Room".
i Update Sec justification for page 9.4.l.
Change Request Number SA 41 .2 Related SI:R : 6.4 SSLR : 23 Section: 6.4 SLIUSSI:R 1mpact N 6.6- l 2 Clarify the discussion regarding the design of the reactor pressure boundary, components, equipment layout, and support structures with respect to accessibility.1he words *te the extent practical" are added.
Clarification 1his change tt ficcts the as built plant and is consistent with the statements from NRC SSI:R 4, Section 6.6.1, Change Request Number SA Il$ . 7 Related SLR : 6 6 SSI:R : Section:
SI:lVSSI:R Impact N 6.61 2 Clarify Section 6.6,l
- Inservice inspection ASM ? Code Class 2 & 3 Components / Components subject to examination". Clarify that during the Unit 2 preservice inspection, Class I systems were inspected using ASMii Code Case N-408.
Correction 1hese chanFes are consistent with the as built plant. This clarification is also consiwtent with the NRC Supplemental Safety Evaluation 26, Section $.2.4.2.
Change Request Number SA 115 . 6 lielated SER : 6.6 SSER , Section:
SLIUSSER 1mpact N e-
Attachtnent to TXX.980l$
CPSIIS Ul*DATl!D FINAL SAltliTY ANALYSIS Rlil' ORT AMI:NDMI:NT. 9$
DI: TAIT.I.D I)l. SCRIP'110N Prens Page Page $$
(ALA!DCDdtd} UNMD DIK1h'llull ficction:
7.1 15 3 Revises section 7.l.2.1.6 to delete "The discussion applies only to that unit j
u hlch has the capability to test in bypass installed."
1 i fpdatc With the completion of the installation of the flypass Test instrumentation modification on both units, this change revises section 7.1.2.1.6 by removing the statement which refers to the unit applicability of the dircussion.
Change Request Number SA - 94 90 , I Related SI:R : SSI:R : Section:
SIT /SSI:R Impact N 7.1 1 R 4 Removen statement referencing the Technical Speci0 cation bases as containing a detailed discussion on the use of allowable value.
Clarincation This statement adds little or no value to the discussion of" allowable value" provided in I'SAR section 7.1.2.1.9. This statement is deleted to reduce the potential for future inconsistencies which could result from changes to the Technical Specification bases.
Change Request Number SA 118. I Related SI:R : SSI:R : Section:
SI:R/SSI R impact N 7.1 20 4 Delete the description for temperature descetors for the motor.
Correction
'the detectors are provided to monitor the motor stator temperature risc. 'lhe description in deleted as the condition is best monitored from the current v/s time characteristics of the motor.
Change Request Number SA 126, 2 Relat d SI:R : 7.1 SSI:R : Section:
SI:R/SSER Impact N
, - , -- , e-., . < w
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFliTY ANALYSIS REPORT AMI;NI)MI:NT- 95 DI;I All l:D DI:SCRIPilON Page $6 Preits Page (as amendt dj ()mDD IJnEfjpiks ficcikitt; 7.1 32 2 Adds item 23,'lligh head safety irdection isolation valves (open)," and item 24," Selected Valves from the inservice testing plan," to list of equipment that cannot be tested at full power so as not to damage equipment or upset plant operation (l'SAR Section 7.l.2.$. "Conformance to Regulatory Guide 1.22").
Update ITEM 23:
The Intervice letting (IST) Plan . Table 13, Safety injection, Note 2 says that valves $801 A A Il cannot be stroke exercised during plant operation because opening the velves results in unnecessary thermal transients on the Reactor Coolant System (RCS) cold leg nonles for which they are not designed and imposes hydraulic transients on the charging sptem and the Reactor Coolant Pump seals which can cause them to cock. Opening the valves also results in an uncontrolled level increase in the pressurlier level and an actuation of RCS isolation check valves 881$, SI 8900A,II.C & D whleh then requires leakage to be verified within its limit per Technical Specification surveillance 4.4.5.2.2.d.1he affected unit must be placed in a shutdown condition (MODI!
3,4 or 5) to support the leak test. I'SAR Section 7.3.2.2.5 says that testing of engineered safety actuation signals requires final devices to actuate. Ilowever, if an end device is actuated that can cause plant upset / equipment damage, the end device will be declared inoperable and then disabled from operating by removing fuses / opening breakers, etc. l'SAR 7.1.2.5 provides the list of exceptions for such end devices; however, valves 8801 A & 11 are not on the list.
1hese valves are exercised during the refueling outages.
1he guidelines of Regulatory Position D.4 of Regulatory Guide 1.22 are met.
ITE M 24:
l'SAR Section 3.911.6.2 states that the inservice testing of valves shall be in accordance with the Inservice Testing Plan. Inservice Testing Plan identities which valves cannot be teued ai full power so as not to damage equipment or upset plant operation (as allowed by the ASME Code). These valves are identified by a footnote and a justification as to w hy the valve cannot be tested at full power.1he guidelines of Regulatory Position D.4 of Regulatory Guide 1.22 are met.
1he Inservice Testing Plan is a 1 icensing Ilasis Document. The information regarding valves is maintained in the IST Plan, therefore l'S AR Section 7.1.2.5 references the IS'I t' ann.1his will eliminate future FSAR updates to be consistent with the IST Plan.
Change Request Number SA 10 . I
Attachment to TXX.98015 t CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT. 95 DETAlllD Dl'. SCRIP I'lON Page 57 Prefix Page DEKIiElleu SIElklD; (DiAtnfnkd] GI1TD Related SI:R : 7.2.3 SSI:R : 24 Section: 7.2.3 SI:R/SSI:R Impact N Section 7.2.3 (SI:R, SSl:R 22 and SSI:R 24) indicated that the I'SAR (l terns 1 thru 22 of Section 7.1.2.5) had properly justified the designs to meet the guidelines of Position D.4 of Regulatory Guide 1.22 and, was therefore acceptable.
1his l'SAR Amendment 95 change provides additional items to the list of equipment that cannot be tested at full power so as not to da.nage equipment or upset plant operation.
7.1 42 2 Adds parayaph describing item 23,'lligh head safety injection isolation valves (open)," and item 24, " Selected Valves from the inservice testing plan" to l'SAR Section 7.1.2.5,"Conformance to Regulatory Guide 1.22").
Update See the justification for Change Request Number SA-9710.1 on l'SAR Page 7.1 32.
Chnnge Request Number SA -97 10 ,2 Related SI:R : 7.2.3 SSI:R : 24 Section: 7.2.3 SI:R/SSI:R impact N See remarks for Change Request Number SA 9710.1 on I'SAR Page 7.132.
- 7. l. 3 4 FSect i Table 'Ihis change removes the references made to Chapter 16 as containing the Technical Specifications. Table references made to I SAR sections containing related information are unchanged.
Clarification Chapter 16 no longer contains the current Technical Specifications.1herefore, references made to l'S AR Chapter 16 as containing the Technical Specifications are removed.
Change Request Number SA - 96 125 , 3 Related SI:R - SSER : Section:
SI:R/SSER impact N I
Attachment to TXX.980l$
l CPSliS - UPDATED FINA!, SAFETY ANALYSIS REPORT AMENL'MI:NT. 95 DETAILI:D OI:SCRIPIIGN Prefix Page Page 58 (as amended) (hnup Descriotion hetion:
7.1- ) 4 Shect 2 lab!c 1his change removes the reft.tnces made to Chapter 16 as the containing the lechnical Specification, and adris a listing ofI'SAR sections containing information related to conformana with the litar";h Technical Position.
Clarification Chapter 16 no lortger contains the currunt Technical Specifications. Therefore, references made to l'S AR Chapter 16 as itimtaining the Technical Specifications are removed. Similarly to the other table enteries. TSAR sections containing infonnation related to confarmance with this liranch lecimical position are added for completeness.
Change Request Number S A - 96 125 . 4 Related SI:R : SSER : Section:
SER/SSI:R impact N 7.2- 19 4 Revise wording to state that the N.16 detectors are mounted on op,msite sides of the hot leg piping rather than on the top and bottom of the hot leg piping.
4 Clarification 1his change makes the description of the mounting of the N 16 detectors consistent with SI'.R Section 7.2.1 and SSER-22 Section 7.2.1, which specifically acknowledge that the detectors are mounted on opposite sides of the hot leg piping.
Change Request Number SA 136 . 1 Related SER : 7.2.1 SSER : 22 Section: 7.2.1 SER/SSER impact N 7.2 19 4 Change the wording associatrd with the frequency at which the RCS flow measurement is perfonned fmm "approximately once a year" to "once per cycle" Clarification 1his change makes the warding consistent with the Technical Specifications w hich require the measurenaent to to performed prior to exceeding 85% power after each fuel loading. Additionally, SSER-22 Section 7.2.1 acknowledges that the flow measurement is performed at the beginning of each plant operating cycle.
Change Request Number S A 136 . 2 Related SER , 7.2.1 SSER : 22 Section: 7.2.1 SER/SSER 1mpact N
.- . -. - - ~ . ,- .- . - . . - - - - - - . . -
- - . .- - - . - __ . - _ _ ._ _=_ . _ - - - _ - . - - - - _ -
Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT 95 Dl:TAILI:D Dl:SCRIPTION Prefis Page Page 59
[es amendtd.) Groun Dng11ptimi section.
7.2 20 4 Change the wording which specifies that, during the RCS flow measurement, the N 16 power monitor channel is placed "in the trip mode (as is done for test purposes) to preclude any control (TITM) and protection (N.16 power) i interaction" to allow the N 16 power monitor channel to be placed in the bypass mode during the measurement.
Correction 1his change is consistent with other sections of the l'SAR and with the app!! cable sections of the Technical Specificaticas which have already been ,
changed to address testing in bypass by Amendment 94 and Amendment 47/33, respectively. There is nothing unique about the RCS ficw measurement or the manner in which the N.16 power monitor channel would be placed in the bypass mode which would cause this activity to be inconsistent with the system descriptions and test methods previously presented. l'utherr cre, interaction hetween the control (TTi~M) and protection (N.16 powe ) functions continues to be precluded.
Change Request Number SA 136. 3 Related SER : 7.2.1 SSER : 22 Section: 7.2.1 SER/SSER Impact N 7.2-27 4 Change the DNilR value of 1.30 to a more accurate description.
Clarification
'the value of 1.30 was correct when the W.3 DNil correlation was used:
however, the use of that DNil co Trelation was replaced by the WRil.1 DNil correlation for the initial cycle of Unit 2 operation and, more recently, by the TUE l DNil correlation.1hese changes to the DNil correlations have been previously discussed in l'SAR Chapters 4 and l$.
Change Request Number SA 142 , O Related SER : SSl:R : Section:
SER/SSER Impact N 7.2 33 4 1his change makes a correction to the equation which specifies the relationship between the elbow tap dilTerential pressure and the RCS Ilow.
Correction 1his change corrects an enor in the equation by indicating that the differential pressure is proportional to the square of the flow (instead of proportional to the flow) and adds a constant of proportionality.
Change Request Number SA 136 , 4 Related SER : 7.2.1 SSER 22 Section: 7.2.1 SER/SSER Impact N l
l
- - - _ . . _ . y - , - _ _ , _ . . _ . .
Attachment to TXX-98015 j CPSES - UPDATED FINAL SAFETY ANALYSIS IWPORT AMl:NDMI:NT - 95 Dl:TAILI:D DI;SCRIPTION <
l'refis Page Page 60
[as amppdtdj Group DesetintioD Section.
7.2-34 4 See change on page 7.2 33 which makes a correction to the equation which specifies the relatio.aship between the elbow tap differential pressure and the RCS flow.
Correction See justification for change on page 7.2 33.
Change Request Nurnber SA 136. 5 Related SIIR 7.2.1 SSI:R : 22 Section: 7.2.1 SI:lVSSt:R impact N 7.2- 34 4 Change the wording which describes that the full flow reference point is established "during initial plant startup to "during plant startup (bliowing each refueling outage".
Clarification
'ihis change clarifles the wordiug consistent with the Technical Specifications which require the sneasureme:it to be performed prior to exceeding 85% power after each fuelloading. Additionally, SSI:R 22 Section 7.2.1 acknowledges that the flow measurement is petibrmed at the beginning of each plant opera?!ng cycle.
Change RequW Number SA 136. 6 Related SI;R . 7.2.1 SSIR. 22 Section: 7.2.1 SI:IUSSI R Lunact N 7.2 46 4 Correct typographical error in line c. from "$2/HTA" to "52/RTII".
I?ditorial I.ine c. should state that the above steps (which describe the method used for testing trip breaker $2/RTA) nre repeated to test trip breaker 52/RTil by using bypass breaker 52/IlYII.
Change Request Number SA 128 . 1 Related SIIR SSl R : Section:
SI:R/SSI:R 1mpact N i
I
Attachment to TXX.980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Prefix Page Page 61 Group Det.cripti & Section.
las amended) 7.2 4 4 Sheets 1. 4,6 & 7 i Table lhis change revises the table references to reficct the current Technical Specifications.
Update This change updat:s the table references to agree with the approved lechnical Specifications.
Change Request Number SA 126 . 1 Related SER : SSER : Section:
4 SER/SSER impact N 7.2 4 4 Sheet i Tnble This change removes the references made to Chapter 16 as containing the Technical Specifications.
Clarification Chapter lo no longer contains the current Technical Specifications. Therefore, references made to l'S AR Chapter 16 are removed and revised to refer directly to the Technical Specifications.
Change Request Number SA 125 . 5 Related SER : SSER : Section:
SER/SSER 1mpact N 7.2. I 2 Sheet 5 l'igure The functional diagram for the Overtemperature N16 trip is revised to add a maximum I second time delay to each channel. (Unit 2 only)
Revision A time delay is added to each bl6 Overtemperature trip channel to prevent unit trip from spurious signals, usually resulting from lightning strikes. The time delay is produced by adding a new card in each 7300 Protection cabinet.
Increased time response isjustified by analysis. Since Reactor Trip system is safety-related, a single failure will not prevent completion of safety function required by accident analyses, and does not constitute a new failure mode.
Setpoints and Allowable Values in Tech Specs remain valid with the increased response time. The response time requirement in TRM Table 1.1.1 (item 7) is revised by LDCR.TR 97-004.
Change Request Number SA 6 .I Related SER : 7.2.1 SSER- 22 Section: 7.2.1 SER/SSER 1mpact N
._ . - _ _ . _ _ - _ _ _ . _ _ _ . _ _ -._ . __ _ _. _ _ m _ - - .m.__.-__.___.
i Attachment to TXX 780l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT ;
AMENDMENT. 9) i j DETAILED DESCRIPTION o Prefiz Page Page 62 l Orcup Docription Section. j (as amendedi 2 Sheet $ f d 7.2. I l'igure lhe functional diagram for the Overtemperature N16 trip is revised to add a ,
l maximum i second time delay to each channel. (Unit I change only) {
l
- Revision A time delay is added to each N f 6 Overtemperature srip channel to prevent unit trip from spurious signals, usually resulting from lightning strikes.1he time delay in produced by adding a new card in each 7300 Protection cabinet.
j increased time response isjustified by analysis. Since Reactor Trip system is !
- safety related, a single failure will not prevent completion of safety function l required by accident analyses, and does not constitute a new failure mode. l Setpoints and Allowable Values in Tech Specs remain valid with the increased .
response time. The response time requirement in TRM Table 1.1.1 (item 7)is revised by Change Request Number LIX'R.TR 97 003.
l j "
Change Request Number SA $ , 1 4
Related SER : 7.2.1 SSER : 22 Section: 7.2.1
' $ER/SSER impact N i
7.3 65 4 1his change revises the reference to Chapter 16 to directly refer to the Technical Specifications.
< Clarification !
j Chapter 16 no longer conialns the current Tecimical Specifications. Therefore, ,
references made to FSAR Chapter 16 are removed and revised to refer directly l to the Technical Specifications. l Change Request Number SA 12$ , 6 !
Related SER : SSEl' : Section:
SER/SSER impact N 7.3 73 3 i Add "and RWST low lew" to the exceptions for equipment that fail to the i actuated position on loss of power. ;
Correction This change makes the discussion ofloss ofinstrument power consistent with rection 7.6.5 that describes the RWST Low Eow level function as normally de-energized and remains de-energized on loss of power, ,
Change Request Number SA 128, 2 ,
Related SER : SSER : Section:
SER/SSER impact N :
e - re r. ,,~...rw .w~...m., rw- ,,,n, wcn-----n.ea.,.,,n--..,,------ n - - - , .+- . ~. - . . . . . . - . . . + - - , , , - . - - - - - + - , - - - - - , - - ---
Attachment to 'I XX.980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT Ahti:NDMIENI . 95 DI:TAILi'.D Di'.SCRlrlION page 63 Prefix l' age (as amended) QJiius Dngdpiks $cction.
7.3-76 4 Deletc *and including" from the description of the solid state logic testing digital signal path from the input relay contacts.
Correction This change makes section 7.3.2.2.5 on overlap testing ofinput relays consistent with the detailed description of Solid State Protection System testing provided in section 7.2.2.2.3. Section 7.2.2.2.3 describes the method for testing the input relays and logic matrices, providing details on how overlap is accomplished by the input relay check and logic matrix check. It Ibrther describes how pulses from the tester are applied to the inputs of the universal logic card at the same terminals that connect to the input relay contacts and that the input relays are not operated during the check of logie matrices. Section 7.3.2.2.$ incorrectly included the input relay contacts as part of the logic matrix test. This change corrects this summary on overlap testing to match the testing methodology in 7.2.2.2.3.
Change Request Number SA 97 - 128. 3 Related SliR : SSI:R : Section:
SI:R/SSl:R Impact N 7.3- 77 4 Delete paragraph 'thich describes maintenace checks on signal cables in radiation environments for resistance to ground as performed during regularly scheduled refueling outages.
Revision All instrument cables are qualified for 40 years at CPSl;S. Therefore, it is not necessary to perfom a resistance to ground check because is has been determined vis type test that the values will not be lower than tested values.
Additionally,10Ci R$0.49 requires that maintenance / replacement be performed on the expired qualified life but doer not require any surveillance check to be pcformed.
Change Request Number S A 105 . I Related Sl:R : SSI.R - Section:
SI:R/SSliR impact N
Attachment to T XX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT. 95 DETAILED DESCRIPTION Page 64 Prefix Page Ong Descriotion Srg11gn; (as amended) 7.3 83 4 Delete refemces to coil "X2" from the discussion of typical schemes for bhicking of protection function actuator circuits.
Correction 1his is an editorial change to make the discussion of slave relay testing consistent with figure 7.3 3.1ho discussion includes a reference to coil "X2",
however the figure does not include an "X2" coil.
Change Request Number SA 128. 4 Related SER : SSER . Section:
SER/SSI:R impact N 4
7.3- 83 4 Change "de cnergized" to "energlied" in the description of continuity test circuits.
Correction 1his change is an editorial correction to the discussion of slave relay block testng. Slave relays are normally de-energlied and energlie to actuate. In describing the operation of the Safeguards Test Cabinet blocking circuit, the description states that the slave relay is de-energlied to close the contact and perfonn continity testing, in actuality, the slave relay energlics to close the contact.1he design shown in figure 7.3-3 is correct in that the slave relay actuates (energlies) and the contact closes thereby permitting the DS lamp to check continuity of the slave relay contact. This correction makes the discussion consistent with figure 7.3-3 and does tiot n' rect the design of the ontact closing when the relay is actuated.
Change Request Number SA -97 128. 5 Related SER : SSER : Section:
SER/SSER impact N 7.3 90 4 Clarification is provided with respecte to operator instructions regarding safety injection wtuation during transient conditions.
Clarification The previous description implied that manual safety injection was available below the P ll permissive, llowever,in events in which a safety injection has already occurred the reactor operators manually actuate ECCS components.
Change Request Number SA 68 .4 Related SER : SSER
- Section:
SER/SSER Impact N
Attachment to TXX 98015 CPSIIS - UPDATliD FINAL SAFETY ANALYSIS REPORT AMI:NDhCNT. 95
, DETAILI:D DESCRIPTION Prefin Page Page 65 (atAtugndsd) Group DsstiElluD Sedum 7.34 2 Sheet 16 Table Adds " Containment Personnel Airlock flydraulic Unit" for Unit I and a note explaining the trip to the table of Safety injection Actuation l'quipment 1,ist.
Revision Seejustification for the changes for page 6.2 77.
Cha. ige Request Number SA 83 .3 Related SER 6.2 SSI:R : 22 Section: 6.2 SEIUSSER impact N 7.3 4 2 Sheet 16 Table Adds " Containment Personnel Airlock flydraulic Unit" to reficct that the Unit 2 equipment :s included in the table of Safety injection Actuation Equipment List.
Revision Secjustification for changes for page 6.2 77.
Change Request Number S A 134 . 2 Related SI:R . 6.2 SSER , 22 Section: 6.2 SER/SSER impact N 7.3- 4 4 Sheet 16 Table Editorial name change for description of valves 18511 A A 11.
Editorial IIditorial change of description.
Change Request Number SA 73 .8 Related SER , SSER : Section:
SI:lVSSER impact N 7.4 4 4 Pages 5,6,7 Section 7.4 terminology for " Power Operated Relief Valves (PORVs)" is being changed to " Atmospheric Relief Valves ( ARVs)" to be consistent with a previous change to the l'SAR and the Technical Specifications.
Chirification Secjustification for paEc 10.3 2.
Change Request Number SA 84 .O Related SER . SSER - Section:
SER/SSER impact N See discussion for 10.3 2.
- - ..-__ _ _ . . _ _ _ _ . ~. - -- - .- .
I Attachment to TXX 98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 66 .
Prefix Page (ai nmendedi Ornyp Descrintion ficction.
7.4-21 4 Section 7.4.1.3.1 Paragraph 7 is clarified to reflect that the llot Shutdown Panel's (IISP) cabinet doors are locked and alanned in the Control Room while the surrounding enclosure door is locked but not alarmed.
Clarification 1his change c'vifies the FSAR description consistent with the as built plant hardware configuration. The cabinet doors of the llot Shutdown Panel's (18SP) ,
are locked and alarm in the Control Room. The surrounding enclosure of the llSP is locked but does not alarm in the Control Room.1hc purpose of the llSP surrounding locked enclosure is for access control to prevent inadvertent plant equipment manipulation from the llSP. Access to the llSP is administratively controlled by Operations personnel located in the Control Room.1herefore, an alarm is not needed on the llSP surrounding enclosure to accomplish this function and the absence of this alarm has no impact on plant safety. This change has no impact on Safe Shutdown.
Change Reqacs: Number SA l17 . I Related SER : SSEk - Section:
SER/SSER Impact N 7.4- l 1 Sheet 5 Table 2 IIV 24521 and 2 IIV 2452 2, tbc stearr admission valves to the turbine 4
driven auxiliary feedwater pump, are being swapped with respect to which valve is associated .vith each steam line for train considerations. This change resulted in the valves being placed on difTerent steara lines and the subsequent nomenclature referring to the steam lines is being changed accordingly.
Revision
'Ihis chan;c is part of the corrective action prescribed to the condition reported in I.ER 197 00100. The modifcation was required to restore the design basis for operation of CPSES. Thoc changes have been implemented for Unit 2 only at this time.
Change Request Number SA 27 .5 Related SER : SSER : Section:
SER/SSER impact N 1
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- Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT + 95 [
~
DETAILED DESCRIPTION j i
Page 67- ;
Prefix Page I Group shE.tipilen firsdun; fas amended) 4-7.4- 2 Sheet I Table 7.4 2 is corrected to delete indication I'l 1776 (Horic Acid l'ilter f
l Table Recovery Line . Ikw) and add indication I'l 18311 (Emergency florate I' low) [
i Correction This change conects Table 7.4 2 by deleting I'l.1776 (lloric Acid l'ilter Recovery Line 11ow) r htch is not i valid plant parameter based on review of 7 the Masta Equipme ~ 'st. Emerge. icy Re r ' Ouldelines (EROS). and !
plant drawings.11 l bsri (Emergency lione e ,w)is added to Table 7.4 2 because the lloric Acid I'llters are in series witn indications 1 l'l.18314 c.d 211 18311 during Emergency llorate operations and thereforti would have the {
same flow. Emergency llorate I' low is a critical plant parameter which is i
' monitoreo from the llSP. This change does not affect the critical parameter monitored or remove any equipment which is used for a Safe Shutdown.
There is no irnpact on Safe Shutdown. ,
Change Request Number SA 117. 2 Related SER : SSER : Section:
SER/SSER Impact N 1
7.4- 2 4 Sheet 3 Table Table 7.4 2 typographical error is corrected by changing A lEL ' 1L to A.l EA2.ll Editorial ,
nis 6hange corrects typographical errors which are considered to be trivial changes in accordance with CPSES guidelines.
Change Requer,t Number SA -97 117. 3 Related SER : SSER : Section:
SER/SSER impact N 7.4-2 4 Sheet 7 Table Table 7.4-2 typogr@ cal error is corrected by changing IIC. 6111 to llc-ol8 Editorial 1his change ccrrects typographical errors which are considered to be trivial changes in accordance with CPSES guidelines.
i Change Rt u est Number SA 117. 4 Related SER : SSER : Section:
SER/SSER impact N-t a
h e
l .-
,.e-._ . , -,J._.. - . , .. - , - - . . _ , . . , , ..,...__,.._,A....,.,,_,,,...-.,.,..._. .-_,.,_.,-...i,--.,..,,.m.mJ,,
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 1 DETAILED DESCRIPTION Page 68 Prefix Page f as amended) OmVp Description Sectiom 7.4-3 1 Sheet 2 Table 2 IIV 2452-1 and 2-IIV 24521, the steam admission valves to the turbine elven auxillery feedwater pump, are being swapped with respect t' which valve is assaciated with each steam line for train considerations. " n i chang.
resulted in the valves being placed on different steam lines and the nosequent nomenclature referring to the steam lines is being changed accordingly.
Revisio" This s .ange is part of the corrective action prescribed to the condition reported in LER 197-001-00. The modifcation was required to restore the design basis
[ for operation of CPSES. These changes have been implememed for Unit 2 only at this time.
Change Request Number SA 27 .6 Section:
L Related SER - SSER SER/SSER impact N
- 7.4- 3 4 Sheet 3 Table Table 7.4-3 is corrected to delete switch IIS-XT (Water chiller control remote
[ local) and add 11S-67101) (Safety Chill Water Chiller Dypass Lockout) b Correction This change deletes switch IIS-XT (Water chiller control remote local) from Table 7.4-3 and adds 11S-67101)(Safety Chill Water Chiller Bypass Lockout).
This change corrects Table 7.4-3 to reflect previously approved Engirecting Change Notice ECN-208 made to comply with Appendix R requirements described in DEP37 Rev.l. This change does not remove the ability to remotely ov.Je the Safety Chill Water Chiller but altes the circuitry to comply wie. Aopendix R. nis change has no impact on Safe Shutdown.
- Change Request isnber SA 117 . 5 Related SER . SSER Section:
SER/SSER impact N 7.5- 7 A 4 +:e Table 7,2s change adds reference note (27) to Instrument Summary Data Table; Quanity information for Core Exit Temperature instrumentation.
Clarification This note is added to provide clari0 cation of the installed Core Exit Themperature instrumentation and conGguration of the thermocouples required to be operable per Technical Specifications requirments.
Chege Request Number SA 128 . I Rc' .cd SER , SSER Section:
7 SI USSER impact N
Atsachment to TXX-98015 i
I CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT I AMENDMENT- 95 DETAILED DESCRIPTION Page 69 Prefix Page Group Descrirstion Srsth,M (as amendsd) 7.5- 7 A 4 Sheet 2 Table This change adds reference note (28) to the Instrt. meat Sem eev Data Table; Quanity infonnation for Reactor Vessel Water 1 ew i insuta aentaten.
Clarification This note is added to provide clarification of the instal ed RVI.ls instrumentation and the configuration of the RVI,lS wnsors required to be operable per Technical Specifications requirments.
Change Request Number SA 127 . 1 Related SER : SSER Section:
SER/SSER impact N 7.5- 71) 4 Sheet i1 Table This change revises Instrument Summary Data Table 7.5-711, Iratrument Range for Safety Chilled Water Flow from 0-300 gpm to 0-400 gpm.
Revision New impellers were installed in each of the safety related chilled water flow pumps in order to achieve the design flow of chilled water through new USP fan coils installed under DM 92-071. The Instrument Range for Safety Chilled Water Flow is revised from 0-300 gpm to 0-400 gpm to accomidate the new normal flow rate of 290-295 gpm, otherwise the new normal flow rate would cause the instruments to " peg" du-ing normal operation and not permit the operators to determine system status.
Change Request Number S A 19 . 1 Related SER , SSER Section:
SEIUSSER 1mpact N 7.5- 7C 4 Sheet 4 Table See description for Table 7.5-7A, Sheet 2, Reference Note 27.
Clarification See justitication for Table 7.5-7A, Sheet 2, Refer:nce Note 27.
Change Request Number S A 128 . 2 Related SER SSER Section:
SER/SSER Impact N l
t
. Attachrnent to TXX.98015 '
- CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 70- l Prefix Page' Group Description brs.Ilgtt,
. (as amended) 7.$-7C 4 Shee'$ ,
Table See description for Table 7.5 7A, Sheet 2, Reference Note 28.-
I- Clarification See, justification for Table 7.5 7A, Sheet 2, Reference Note 28.
Chai ge Requtst Number SA 127 . 2 Related SER : SSER : Section:
SER/SSER impact N a
7.5- 7F 4 Sheet 3 Tab!c Deletes specific TS section numbers f>om reference to Technical i Specification.
i' Clarification The current section aumbers are not correct. Deleting the section numbers will correct the discrepancy while maintaining the intended reference to the Technical Specification.
Change Request Number S A 113 . I Related SER : SSER . Section:
SER/SSER 1mpact' N 4
i 7.6-1 2 Pages 2 and 3 Changes the description / analysis ofInstrumentation and Control Power i' Supply System to reference the correct figure for the single line diagram and -
section for seismic qualification and to identify the new configuration of the
- new inverters and battery chargers.
J Addition The new inverters / battery chargers manufactured by SCI along with the new configuration with the addition of a spare inverter for each train improve the
> reliability and availability of the equipment. Also, by this modification the rating of all the Class lE inverters are standardized and the SCI inverters are less prone to component failures. The SCI inverters are not provided with the 7
rectifier circuit and therefore the new configuration does not require 480 V AC feed to the inverters from the MCCs. This design feature does not reduce the inverter reliability or availability as the inverters still have batteries as DC backup source 480 V AC feed to the battery chargers as the primary AC power source. The deletion of the 480 V AC input feed to the inverter enhances its -
- reliability / availability because it makes the inverter design simpler, climinates the component failures associated with the rectifier circuits and isolates
~
inverter from 480 V AC system surges.
l Change Request Number . SA 60 .I ,
Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact Y SSER (22) states that each Class IE inverter receives incoming normal power o wns, , - n- ev,,-av~ -w,. , - , , - ..,m e
Attachrnent to TXX-98015 l
t CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMENT. 95 DETAll.ED Dl:SCRIPTION Page 71 Prefh Page Group Decriptico ScElh!n;
[numendedi from a Class IE 4RO-V ac motor control center and backup de power from a Class lE 125 V de hattery by means of an auctioneering-type circuit and that if the ac power source fails, the inverter output is maintained witbut interruption frc.m the de power of battery.
Since the new inverter configuration is not provided with the rectifier circuit, the 480-V ac feed from the MCCs to the inverters are not required. This design feature does not reduce the inverter reliability or avnilability as the inverter still has station batteries as de backup source and 480-V ac feed to the battery chargers as the primary ac power source. The deletion of the 480-V ac input feed to the inverter enhances reliability / availability because it makes the inverter design simpler, eliminates component failures associated with the rectifier circuit and isolates the inverter from 45k-V ac system surges / disturbances.
7.6- 17 4 Removes statement regarding the Criticality Accident Alarm System from description ofinstrumentation installed to mitigate the consequences of refueling accidents.
Editorial References made to the Criticality Accident Alarm System have been removed consistent with exemptions granted in the l'acility Operating LJcenses.
Previously, l'SAR Amendment 78 removed references to cnticality monitors from FSAR Sections 12.3.4.2 and Table 12.3-8.
Change Request Number SA 19 . 1 Related SER SSER 26 Section: 9.1 Sl:R/SSER impact N 7.6-21 4 A clarification is made consistent with S AR section 6.3 on when S1 reset can occur.
Clarification This section is being revised for clarification consistent with the detailed discussion of SAR secuan 6.3, Change Request Number S A t ,7 Related SER SSER Section:
Sl:R/SSER impact N
Attachment to TXX-98015 l
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 72 Prefix Page (as amsndsd.1 Group Descrirition Section.
7.6-23 4 Change reference to PAM to SAR section 7.5.
Clarification PAM is not current CPSES SAR terminology. Section 7.5 of the SAR is the correct reference.
Change Request Number SA I .9 Related SER - SSER Section:
SER/SSER 1mpact N 7.6- 23 1 The RWST level instrumentation uncertainity is updated and clarified based on current analysis.
Update The reunalysis which was done as part of the ECCS switchover from irdection to recirculation resulted in minor changes to the RWST level instrument uncertainity. 'these changes are made to update that information.
Change Request Number SA 1 .8 Related SER , SSER Section:
SER/SSER Impact N 7.7-27 4 Delete the description of the Boron Concentration Measurement System (llCMS) provided in FS AR sect ion 7.7.1.10 and add the statement that the llCMS is abandoned in place.
Revision The lloron Concentration Measurement System (llCMS) is a non-safety related system which monitors reactor coolant boren content. It is designed for use as an advisory system that provides information as to when aM.itiont.1 check analyses are warranted rather than as a basis for fundamental operating decisions. Local samples are taken to provide verification of correct boron concentration. Ilecause this system is not relied on by Operations but does require continual maintenance and calibration, as well as the system contains a neutron source, it is beneficial to abandon the system in p ace. No credit is taken for this system in any accident analysis and there are no safety systems or systems important to safety alTected by the implementation of this activity.
Change Request Number SA 79 . I Related SER
- SSER Section:
SER/SSER Impact N
. -. . . - - _ - - _ . - . - - . ~ ~ . - - . - _ . - - _ - . . . - ~ . - - - - - ~ - - . - .
i e
Attachment to TXX.9 sol 5 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 9$
DETAILED DESCRIPTION
- I Page 73 Prefix Page Group Descrintion Section.
. f as amendedi 7.7- 2 4 Table Delete Table 7.7 2 Iloron Concentration Measurement System i
Specifications.
4 Revision See justification for revision to Section 7.7.1.10, page 7.7 27.
Change Request Number SA 79 .2 Related SER : SSER : Section:
SER/SSER Impact N 7.7- 10 4 Figure Delete Figures 7.7 10 thru 7.7-13 for lloron Concentration Measurement System.
Revision Secjustification for revision to Section 7.7,1.10, page 7.7-27, Change Request Number SA 79 .3 Related SER . SSER : Section:
SER/SSER impact N v
7.7- 1 I 4 Figure Delete Figures 7,710 thru 7.713 for 11oron Concentration Measurement System, 4 Revision See justification for revision to Section 7.7.1,10, page 7.7 27.
Change Request Number SA 79 4 Related SER : SSER , Section:
SER/SSER Impact N 7.7 12 4 Figure Delete Figures 7.710 thru 7.713 for lloron Concentration Measurement
- System.
Revision See justification for revision to Section 7.7.1.10, page 7.7-27.
Change Request N amber SA 79 .5 Related SER : SSER . Section:
SER/SSER impact N 4
W
,-.u e , w- --,,,.y ,-,,,a v-- ,y -r--. - - - - - .- -,1- y4 .,
Attachment to TXX 9X015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 74 Prefix Page
[ga amtndsd) fanup Description Section.
7.7- 13 4 l'igure Delete Figures 7.710 thru 7.713 for lloron Concentration Measurement System.
Revision See justification for revision to Section 7.7.1.10. page 7.7 27, Change Request Number SA 79 .6 Related SER SSER : Section:
SER/SSER impact N 7.7- 14 A 4 Figure Control Room Panel Arrangement figure 7.7 14 A is revised to add the I cading Edge flow Meter in place of removed RM 21 Printer and delete removed RMS equipment.
Update This change updates Figure 7.7 14 A consistent with changes to the control room lay out. Changes to the Radiation Monitoring System and Meteorological System were previously evaluated by Safety Evaluation SE-91-082. 'Ihe Leading Edge Flow Measuring System Cabinet is a
- non-safety r. lated system previously described in FSAR Table 17A-1.
Change Request Number SA 117. 6 Related SER SSER : Section:
SER/SSER Impact N 8.1- 1 4 Revise discussion of TU ElectrWs organization.
Revision Organizational update to reficct 1997 reorganization of TU Electric's functional divisions into business units.
Change Request Number SA 129. 3 Related SER : SSER- Section:
SER/SSER Impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Page 75 Prefix Page Group Descriotion Section.
(Atatucnded.)
8.2 2 4 Delete reference to figure 8.2-6 for physical layout of switchyard.
Editorial Figure 8.2-6 was deleted in earlier l'SAR Amendment, but did not remove reference to it in section 8.2.1.
Change Request Number SA 146. 3 Related SER : 8.2 SSER 22 Section: 8.2 SER/SSER Impact N 8.2- 8 3 Clarify that the spare transformer XSTl/2 is provided to prevent an extended interruption of olTsite power in case of startup transformers failure.
Clarification
'the availibility of the spare transformer at site, capability to use it for 345 kV or 138 kV service, availability of transformer foundation with readily accessible services, and control panel to transfer / connect appropriate protection and .:entrols for the spare transformers specific location will reduce the outage time in case of failure of any startup transformer.
Change Request Number SA 161, O Related SER , 8.2.1 SSER . 22 Sectioir 6.2.1 SER/SSER 1mpact N 8.2-16 4 This change clarities that the maximum and minimum grid voltages are as located at CPSES.
Clarification This change is made to clarify that the maximum and minimum voltages are CPSES specific.
Change Request Number SA 107 . I Related SER SSER , 22 Section: 8.2.3 SER/SSER Impact N l
l r
I l
l
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAll,ED DESCRIPTION Page 76 Prefix Page Group Descrintion Section.
ias amended) 8.2-18 4 Replaces the word " spinning" with " responsive."
Update This change inputs the current terminology used for ERCOT system reserve capability obligations.
Change Request Number S A 107 , 2 Related SER : SSER : Section:
SER/SSER impact N 8.2-19 3 Delete pre-operational test summary for AC Power Distribution System.
Correction The pre-operational test summary for AC Power Distribution System is deleted because it is already provided in FSAR Table 14.2 2, Sheets 35,35a, and 35b.
Change Request Number S A 67 , O Related SER H,2.2 SSER. 22 Section: 8.2.2 SER/SSER Impact N 8.2- 19 4 This change updates the description of system reserve coordination by the Electric Reliability Council of Texas (ERCOT) in accordance with ERCOT Operating Guides which have been revised to incorporate Independent System Operator (ISO) functions.
Update ERCOT guide lines for system responsive reserve obligaf.ons are based on system reliability studies. The responsive re erve capability of 2300 MW is sullicient for the security of the system to maintain a high system reliability.
The changes in liRCOT Operating Guides to incorporate ISO functions do not alTect grid stability and reliability.
Change Request Number SA 107 . 3 Related SER - SSER 22 Section: 8.2.3 SER/SSER Impact N l
l r
1
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 77 Prefix Qee Descrintion Section.
(as amendedi Ormin 8.2- 1 4 Table Removes the column on Motor Rated Voltage" from the table.
Update Motor rated voltage infennation is not required for this table because it incorrectly implies that only 6600V and 460V rated motors are used on the Class IE system. FSAR section 8.2.2 clearly states that Class IE equipment can operate continuously for all stated bus voltage ranges and for all modes of plant oper tlon to perform their intended safety function.
Change Request Number SA 26 . O Related SER , 8.2 SSER : 22 Section: 8.2 SER/SSER Impact N 8.2- 1 3 Figure Revise ugure 8.2-1 to remove the connection between structures 2 and I, and provide connection between structure 2 and bay 6.
Editorial Editoilat change, dranitig error und consistent with figure 8.2 5.
Change Request Number SA 146 . 2 Related SER : 8.2 SSER : 2?. Section: 8.2 SER/SSER 1mpact N 8.2- 8 3 Sheets 01 and 02 Figure Delete figure 8.2-8.
Revision Protection, metering and synchronizing details provided in figure 8.2-8 for switch yard one lines are beyond the level of detail required to be provided per R.G.I.70. Switch yard one lines drawings (Ggures 8.2-3 and 8.2-4) meet the R.G.I.70 requirements. Therefore figure 8.2-8 is deleted based on duplication with figures 8.2-3 and 8.2-4.
Change Request Nurnber SA 146 . 1 Related SER 8.2 SEER . 22 Section: 8.2 SER/SSER 1mpact N l
Attachment it. TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 78 Prefix Page OmpJ Descrintion Section.
(as amended) 8.2- 8a 3 Figure Deletes Figure 8.2 8a.
Revision Protection, metering and synchronizing details provided in figure 8.2-8a for switch yard one lines are beyond the level of detail required to be provided per R.G.I.70. Switch yard one lines drawings (figures 8.2 3 and 8.2-4) meet the R.G.I.70 requirements. Therefore figure 8.2-8a is deleted based on duplication with figures 8.2 3 and 8.2-4.
Change Request Number SA 146 . 4 Related SER , SSER : Section:
SER/SSER impact N 8.3- 15 4 Delete ". ..as depicted in Figure 8.3 19,", a reference for Solid State Safeguard Sequencer (SSSS) automatic test circuitry.
Editorial Reference to Figure 8.319 is for
- Excitation Characteristic curve for Diesel Generator" and is inappropriately referenced foi SSSS automatic test.
Reference to inappropriate figure is deleted, llowever, at the end of FS AR Section 8.3.1.1.5.3, item I refers to controlled copics of vendor manuals and CPSES procedures for detailed description of Solid State Safeguards Sequencer (SSSS) test circuitry.
Change Request Number SA 145 . O Related SER 8.3.1 SSER 22 Section: 8.3.1 SER/SSER Impact N 8.3-26 2 Revises FS AR section pertaining to the Diesel generator starting circuits to identify the new digital govemor system added to the EDG (except Unit 1 Train "I!" EDG) to allow slow starting. Unit 1, Train "11" EDG has the EGA Govemor System.
Revision Slow starting is better for the EDG as it reduces wear by avoiding the full fuel rack starts and is recommendation of NUREG-1366 and NUREG-1431.
Change Request Number SA 143 . I ,
Related SER : 8.3 SSER 22 Section: 8.3 SER/SSER 1mpact N
Attachtnent to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Page 79 Prent Page Group Descriotion Section.
(as amended) 8.3-27 3 Revise protection system to delete "DilA" and to describe Diesel Generator starting modes (i.e. " Auto start because of a Safety injection Actuation Signal (SI AS), or when the Diesel Generators are manually started in Emergency mode") when all protection except generator difTerential and engine overspeed are bypassed.
Clarification Diesel Generator protection with the exception of generator differential and engine overspeed are bypassed when Diesel Generator is started in emergency mode. Diesel Generators automatically start in emergency mode by a Safety injection Actuation Signal (SlAS) which may be generated by an accident, or they may be manually started in an emergency mode by the operator under abnormal conditions.
Change Request Number SA 144 . O Related SER 8.3.1 SSER , 26 Section: 8.3.1 SEtUSSER impact N 8.3-37 3 Revise the RTlys section to clarify that if an RTD is bad, it can be abondoned in place and may be replace when the motor is rewound.
Revision Motors are provided with two temperature detectors (RTD's) for each phase for stator winding temperature monitoring purposes where required. These RTD's are not used for an3 motor protection. It is possible that during the life of a motor, these RTD's may go bad. Plant computer capability to monitor the stator temperature may not be available if all the RTD's in motor stator winding have failed. Failure of the RTD's does not alTect the performance of the motor. Ilence the RTD's can tie abandoned in place and may be replaced when the motor is rewound.
Change Request Number SA 126 . I Related SER 8.3 SSER . 22 Section: 8.3 SER/SSER impact N 8.3-38 2 Pages 39,40,10 land 102 Changes the section 8.3.1.1.13 pertaining to " 118-V Uninterruptible AC rower " , to describe the new inverter and the spare inverter configuration; also identilles the correct references of associated Ogures and table in section 8.3.2 (DC Power Systems) pertaining to subsections on " Loading" and
" Identification of Safety Loads" Addition Same as justification for changes to page 7.6-1.
Change Request Number S A 60 2
Attachment to TXX-98015
- CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAll.ED DESCRIPTION Page 80 Prefix Page.
(as amended) ,QT.pyp DOcription Section. ,
Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER 1mpact Y '
Sec justification for SSER impact for page 7.61.
8.3-39 4 Add " manual bypass' to the switch operation for bypass (nonregulating) transformer.
Correction Clarify the type of switch operation for bypass transformer 'make before break' operation.
SA 7 4
s Change Request Number Related SER . 8.3 SSER.: 22 Section: 8.3 SER/SSER impact N 8.3-52 2 Revise penetration conductors primary and backup protection details for Rod Control System Power Circuits.
Correction The 50 Amp fuses in positive and negative legs of the control rod drive nechanical liti coil circuits provide adequate primary and backup protection 4
Ibr # 4 AWO penetration conductors. As such credit is taken for 50 Amp fuse to provide primary protection for the lifi coli circuit penetration conductors.
Change Request Number SA 50 . I a Related SER : 8.4.1 SSER : 22 Section: 8.4,1 SER/SSER Impact Y SSER 22, Section 8.4.1, Para 6th, Page 817 should be revised based on this change.
i 8.3-54 3 Revise penetration conc'uctors primary and backup protection details for Solid -
State Cabinet Circuits.
Correction Fault levels in Solid State Isolation Cabinet circuits are less than the continuous rating of the penetration conductors, as such these circuits do not
. require prima.y and backup protection.
Change Request Number SA 50 , 2 Related SER : 8.4.1 SSER : 1! Section: 8.4.1 SER/SSER Impact N
Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 81 Prefix Page Group Descrmtion Section.
(as amendd) 8.3 54 2 Delete penetration conductors primary and backup protction details for Containment Water Level Transmitters. Also renumber the rest of the sub section numbers.
Correction Fault levels in Containment Water Level Transmitter Circuits are less than the continuous rating of the Penetration Conductors, as such these circuits do not require primary and backup protection, section 8.3.1.2.1.6 item "r" is deleted because it is an instrument circuit and not a control or power circuit which are the subject of this section (Low level signals in instrument circuits do not challenge penetration conductors rating and therefore their protection is not described in this section).
Change Request Number SA 50 .3 Related SER , 8.4.1 SSER , 22 Section: 8.4.1 SER/SSER Impact Y SSER 22 section 8.4.1, last para on page 8-17 and coninuation on page 8.18 should be deleted based on this change.
8.3 55 2 Delete penetration conductors primary and backup protection details for Containment Door Limit 9 witches.
Correction Containment door switch primary and backup protection is deleted because the circuit is spared and cable connection to penetration conductors is determinated.
Change Request Number SA 50 4 Related SER , 8.4.1 SSER , 22 Secti on: 8.4.1 SER/SSER Impact N 8.3- 65 3 Pages 66,67 Adds new Spent Fuel Pool (SFP) level devices (X-LY-4849A 1, X-LY 4849A-2, X-LY-484981 and X-LY-484911-2) to provide 2-eit of 2 logic for Spent Fuel pool cooling pump protection on low-low pool level and continuous level indication in the control room.
Addition Seejustification for I A(H)-53.
Change Request Number S A l 10 . 2 Related SER : 8.3 SSER. 22 Section: 8.3 SER/SSER impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 82 Prefix Page Group Descrirition Section.
(as amended) 8.3-68 2 Page 69 Adds analysis for Unit I (under subsection 71 pertaining to Regulatory Guide 1.75 compliance in the I'SAR section 8.3.1.2.1) for acceptability of reduced physical separation between non-Class IE cables and Class IE cabling located in the pennnnel airlock power feeder control panel CPI-IISCPEll-01.
Revision The analysis pro'< ides thejustification for the reduced physical separation between non Class IE cables and the Class lE cables.
Change Request Number SA 83 .4 Related SER 8.3 SSER . 22 Section: 8.3 SER/SSER impact N 8.3 68 2 Page 69 Adds analysis for Unit 2 (under subsection 76 pertaining to Regulatory Guide 1.75 compliance in the FSAR section 8.3.1.2.1) for acceptability of reduced physical separation between non-Class I E cables and Class I E cabling located in the perso mel airlock power feeder control panel CP2-IISCPEll-01.
Revision
'Ihc analysis provides thejustification for the reduced physical separation between non-Class lE cables and the Class lE cables.
Change Request Number SA 134 . 3 Related SER 8.3 SSER . 22 Section: 8.3 SER/SSER tmpact N B.3- 68 2 Page 69 Adds analysis (under subsection 7k pertaining to Regulatory Guide 1.75 compliance in the FSAR section 8.3.1.2.1) for acceptability oflack of separation / isolation between associated control cables and non-Class IE control cables at the Instrument Air Compressor Termination Cabinet CPI-CICACO-01 A.
Addition The analysis provides thejustification for not requiring the separation / isolation between associated centrol cables and non-Ciass IE control cables at the termination cabinet CPI-CICACO-01 A.
Change Request Number SA 44 . ,?
Related SER 8.3 SSER 22 Section: 8.3 SER/SSER Impact N
~
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 83 ,
Prefix Page Omys Descriplign Section.
(as amendsd) 8.3- 70 ' 2 Adds item (m)(Emergency Diesel Generator control Panel CPI-ECCPEC 01 and 02) to subsection (7) of FS AR Section 8.3.1.2.1 (AC Power Systems /
Analysis / Compliance / Comp
- mec With NRC Regulatory Guide 1.75 and IEEE 384). Item (m) is an anais sis of the lack of separation between the Class IE pressure indicating switch contact and the Non-Class IE time delay relay contact.
Correction Justification for this change is contained within the text of item (m).
Change Request Number S A 34 .3 Related SER . 8.3 SSER+ Section:
SEIUSSER Impact N 8.3-71 2 Add section "n" for Unit 2 Turbine Driven Auxilliary Feedwater Pump Control Panel (CP2-EIPRIN-48)- an anlysis for electical equipment not requiring intemal cable separation as per NRC R.G.1.75 (See Description for Page i A(II) 54).
Revision See justification for Page i A(D)- 54.
Change Request Number SA 36 .2 Related SER 8.3 SSER : 22 Section: 8.3 SEIUSSER Impact N 8.3- 75 3 Page 76 Clarities the label und tag number identification for equipment and cable / raceway in section 8.3.1.3 pertaining to Physical identification of Class IE Power Systems Equipment.
Clarification These are considened cditorial changes consistent with Regulatory Guide 1.70 Revision 2 rmd the Standard Revisw Plan NUREG 0800 Revision 2.
Change Request Number S A 77 . O Related SER
- 8.3 SSER- 22 Section: 8.3 SEIUSSER Impact N
. , - . _. . . . - ~ - - - . ~ ~ . - - . - - . . . - . . - . - - - - . - . . - - _
Attachment to TXX.98015 i
i CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- - 95 DETAILED DESCRIPTION Page 84 Prefix Page (as amended) Onng! Description Ssslimn 8.3 84 2 "
Adds analysis for no separation between the output cables and conduits of the spare Class IE inverters.
Addition The analysis provides thejustification for no separation requirement for certain aspects of the spare inverter configuration. '
Change Request Number S A 60 . 21
- Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSL R impact N 8.3- 89 2 Page 91 Adds description of galvanized steel sheathed cable for consHering as metal sheathed cable.
i Addition Same asjustification for similar change to page i A(II)-52.
g-Change Request Number SA 66 .2 Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N 1
8.3- 92 3 Revise Section 8.3.1.413 add the physical seperation requirements for
, Stainless Steel clad mineral insutu :uables installed in the Reactor Vessel Level Indication System.,
Addition Stainless steel clad mineral insulated cable is used in the Reactor Vesse Level Indication System (RVLIS) in tre Containment 13ui! ding. This cable is Class l
IE qualified to IEEE 323-1974 and to IEEE 383-1974 for flame retardancy.
i; 1he stainless steel cladding on the RVLIS mineral insulated cables is 16 mils thick and is comparable to the 6 mils Stainless Steel llex tested in Wyle test report 48037-02. 'the cladding on the RVLIS cables will provide the mechanical integrity required and for seperation purposes is equivalent to cable in enclosed raceway. The use of Stainless Steel clad mineral insulated RVLIS c cable is acceptable for Regulatory Guide 1.75 seperation requirements, and '
allows the cables to be installed without fire barrier material (sittemp).
Installation of these cables will reduce manhours, man-tem exposure and outage time during every refueling outage.
Change Request Number SA 125 . O Related SER : 8.3 - SSER - 22 Section: 8.3 SER/SSER Impact N f
Attachment to TXX 98015 l
i CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAll.LD DESCRIP110N Page 85 Prefix Page Grepp Description Section.
(as amended) 8.3 1 2 Sheet 1 Adds loads due to the new UPS room fan coil units to the table of" Loading Table Requirements For Loss-Of -Coolant /acident Coincident With Loss Of OITsite Power".
Addition The new UPS toom fan coil units are installed to conservatively mect the cooling requirements. The additional load imposed on the emergency diesel generators (EDGs) is verified to be within the capability of the EDG.
Change Request Nun.ber SA 54 . 1 ,
Related SER
- 8.3 SSER 22 Section: 8.3 SER/SSER Impact N 8.3- l 2 Sheet 6 Revises start time aller Si auto sequencer for the hydrogen recombiner, and Table hydrogen purge system heater and supply and exhaust fans.
Revision Revised start times are based on per(brmance of new Post-LOCA hydrogen analysis with new assumptions. Also see discussion for page 6.2 102.
Change Request Number S A 108 . O Related SER , SSER : Section:
SER/SSER 1mpact N 8.3- 1 2 Sheets I and 2 Table Changes the inverter and battery charger ratings and adds spare inverter rating to the table for " Emergency Electrical Loading Requirements for LOCA Coincident with LOOP" to correspond to the acw inverter / battery charger configuration for Unit 1. Also makes editorial correction to equipment identification.
Addition Same as justifi:ation for changes to page 7.6-1.
Change Request Number S A 60 . 19 Related SER
- 8.3 SSER . 22 Section: 8,3 SER/SSER impact Y See justification for SSER impact for page 7.6-1.
= Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 ,
DETAILED DESCRIPTION Page 86 Prefix Page '
(as amended) Group Descrintion section:
8.3- I D I Sheets 1,2 and 3.
Table - Deletes the relay catalog numbers from the table of"overvoltage/undervoltage protu1lve relay identification and settings" Editorial 1he relay catalog number deletion from the FSAR is considered to to be 4
editorial changes only. *lhese details are not required per Regulatory Guide 1.70.
Change Request Number SA 89 .1 Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N 4
8.3- 2 2 Sheet 4 Table Changes the inverter and battery charger ratings and adds spare inverter rating - ,
to the table for " Emergency Electrical Loading Rcquirements For Loss of 4
Offsite Power Conditions" to correspond to the new inverter / battery charger configuration for Unit 1. Also makes editorial correction to equipment tag
- _ number.
Addition Same asjustificatica for changes to page 7.61.
Change Request Number SA 60 .3
' Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact Y
' Secjustification for SSER impact for page 7.6-1, 8.3- 2 2 Sheet 1 Table Adds loads due to the new UPS toom fan coil unit to the table of "
Emergency Electrical Loading Requirements For Loss Of OfTsite Power Conditions".
Addition The new UPS fan coil units are provided to conservatively meet the cooling requirements. Additional load imposed on the emergency diesel generators (EDGs) by the new fan coil units is within the capability of the EDGs.
Change Request Number SA 54 .2 Related SER 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N 1>
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 87 Prefix Page (as amended) QLUMD Description Section.
8.3- 4 3 Tr.ble Revise the table to reflect the Unit 2 battery loads for ilT2EDI and ilT2ED2.
Revision Unit 2 inverters and battery chargers are replaced under DM 96-011 with 10 KVA inverters and the 300 amp battery chargers. Table 8.3-4 are revised to reflect the new battery loads for 125 volt de battery llT2EDI and 11T2ED2.
Change Request Number SA 7 .2 Related SER . 8.3 SSER , 22 Section: 8.3 SEIUSSER Impact N 8.3- 4 3 Table Revise table 8.3-4 to reficct the additional load on station batteries as a result of design modification 95-081. (See Description for i A(13)-53)
Addition Additional battery load is required as a result of completion of design modification 95-081. (See justification for 1 A(II)-53).
Change Request Number SA 110. 6 Related SER : 8.3 SSER- 22 Section: 8.3 SER/SSER 1mpact N 8.3- 4 2 Table Revises "125-Vdc Class IE Dattery 1,oad Requirements" table 8.3-4 to reficct the total battery loading aller completion of the Unit I inverter / battery charger modi 0 cation. Deletes the detailed description of the loads from the table while retaining the battery load summary . Also consolidates similar data in tables 8.3 4 A,8.3-48, and 8.3-4C into + .ble 8.34.
Addition Detailed battery loading information is reficcted in the relevant calculations.
Pertinent data from tables 8.3-4 A,8.3-4B & R.3 4C are relocated to table 8.3-4. Also seejustification for changes to page 7.6-l.
Change Request Number SA 60 4 Related SER : 8.3 SSER 22 Section: 8.3 SER/SSER Impact N
- ._. - - . - - - - - - - . - . - - - . - ~ - . . ..... - .-- .. . . - _ . - -
- Attachment t'o TXX.98015
- CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT l AMENDMENT - - 95 DETA1ED DESCRIPTION Page 88 Prefix Page Group Description Section:
- - - (as amended) 83-4 2 Table . Revises battery loading table to reflect the additional ampere load for battery IITIEDI following loss of AC power as a result of the new digital govemor
' system for Unit i Train A EDO.
Revision Same as the justification for changes to the page 8.3-26 pertaining to the new digital govemor system for Unit 1 Train A EDO.
- Change Request Number SA 143 . 2 Related SER : 8.3 SSER : 22 Section: 8.3 1 SER/SSER Impact N a
f 8.3- 4 A 2 Table Deletes the information in table 8.3-4A.
i-Addition Pertinent information is relocated to table 8.3-4. See alsojustification for changes to table 8.3-4.
i Change Requ st Numbei SA 60 .5 Related SER 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N 8.3- 4 B 2 Table Deletes information in table 8.3-48.
Addition i.
Pertinent information is relocated to table 8.3-4. See alsojustification for changes to table 8.3-4.
Change Request Number SA 60 .6 Related SER : 83 SSER : 22 Section: 83 l SER/SSER Impact N 8.3 4C 2 Table Deletes information in table 8.3-4C.
Addition Pertinent information is relocated to table 83-4. See alsojustification for changes to table 83-4.
- SA 60 .7 Change Request Number Related SER : 83 SSER : 22 Section: 83 SER/SSER Impact N
_ _ _ _ _ - _. . ~ . ,.
Attachment to TXX 98015 l 1
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 89 Prefix Page f as amended) Group Descrintion helipm 8.3- 7 2 Sheets 3 and 4 Revises table on 'Tallure Mode and EfTects for Auxiliary Power Systems", to Table reficct that redundant loads are supplied by the redundant inverter upon failure of an inverter breaker to demone.trate that there is no e'Tect on the auxiliary DC power system due to failure o."the breaker. Also deletes the justification of availability of 480-V power source to the inverter upon it.verter breaker failure.
Addition See justification ibr changes to page 7.6-1.
Change Request Number SA 60 .8 Related SER 8.3 SSER - 22 Section: 8.3 SER/SSER impact Y See justification for SSER impact for page 7.6-1.
8.3- 8 4 Table Delete table 8.3 8 for 6900 V Main 11us Load Assignmenn Update Table 8.3 8 for 6900 V main bus load assignments is deleted based on the information contained in this table is duplicated by FSAk ligures 8.3-5,8.3 6, 8.3 7, and 8.3-8.
Change Request Number SA 159 . I
!!clated SER 8.3 SSER 22 Section: B.3 SER/SSER Impact N 8.3- 9 4 Table Delete table 8.3-9 for 480 V Main llus Load Assignmerits.
Correction Table 8.3-9 for 480 V main bus load assignments is deleted becausc the information contained in table 8.3-9 is duplicated by FSAR figures 8.3-5, 8.3-6, 8.3 7, and 8.3-8.
Change Request Number SA 159 . 2 Related SER . 8.3 SSER. 22 Section: 8.3 SEIUSSER Impact N
. . . . . - - -. -.- _ -.--.~, - .- .. . _ . . - . - . . . . , _- . ~ . . . . -_ ~
Attachment to TXX 980l$
CPSES'- UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION
' Page 90 j Prefiz Page Group Description - Section: ;
f as amended 1 '
8.3-10 3 Sheet 2 Table Delete Non-lE inverters IV2C2 and IV2C3 frem the table showing list of electrical equipment not requiring internal cable seperation.
Revision The 125 V de input cable 120 V ac input cable and 120 V ac output cable for the Non-Class t 8 inverters are all Non-Class I E, Therefore, internal seperation for the input and output cables for the Non-Class lE inverters are not required.
Charge Request Number S A 7 .3 Related SER : 83 SSER : 22 - Section: 8.3 SER/SSER Impact N 3
8.3- 10 2 Sheets I and 8 Table Deletes Non. Class IE inverters XVIC2 and IVlC3 from the table showing list of electrical equipment not requiring internal cable separation. Adds to ,
this list Non-Class IE bypass transformer TIC 3 and Class IE spare inverters CPI ECIVEC-05 and CPI ECIVEC 06 and a note is added tojustify for not d
requiring separation. ,
4 Addition Seejustification for changes to page 7.61, Change Request Number SA 60 9-j.
Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER impact N 8.3- 10 3 Sheet 7 h
Table Adds new Spent Fuel Pool (SFP) level devices (X-LY-4849A 1,
- X-LY 4849A-2, X-LY 4849fl 1 and X LY 484911-2)to provide 2-out-of 2 logic for Spent Fuel Pool cooling pump protection on low-low pool level and continuous level indication in the control room.
Addition Seejusti0 cation for I A(II)-53.
Change Request Number SA 110 . 4 Related SER : 8.3 SSER* 22 Section: 83 SER/SSER Impact N
, , ..m, . .,, ,, -. m - .. .- .
l Attachment to TXX-980l$
l CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Page 91 Prefix Page Group Section.
Duurmended) Dm:rintion 8.3-10 3 Sheet 9 Table Revise note 16 to add for the applicabilty of the input and output cable classifications for Unit 2 class IE spare inverters..
Revision Units 2 input and output cables for the spare inverters have the same classification like those for Unit I spare inverter cables, llence it is not listed seperately in this table.
Change Request Number SA 7 . I Related SER . H.3 SSER 22 Section: 8.3 SER/SSER impact N 8 3-10 2 Sheet i Table Adds Instrument Air Compressor Termination Cabinet CPI-CICACO-01 A to the table for Electrical Equipment Not Requiring Internal Cable Separation .
Addition SeeJustification for change on page 1 A(B) 54 Change Request Number SA 44 .3 Related SER : 8.3 SSER - 22 Section, 8.3 SER/SSER Impact N 8.3-10 i Sheet 2 Table Add panel CP2-EIPRIN-48 to the list of electrical equipment not requiring internal cable separation (See description for Page 1 A(II)- 54.
Revision Seejustification ibr Page I A(II)-54.
Change Request Number SA 36 3 Related SER 8.3 SSER . 22 Section: 8.3 SER/SSER Impact N 8.3-10 2 Sheets 7 and 9 Table Adds Personnel Airkxk Ilydraulic Feeder Control Panel CP2-BSCPEB-01 to the table for Electrical Equipment Not Requiring Internal Cable Separation.
Revision Seejustification for change on page 1 A(II)-$4.
Change Request Number SA 134 . 4 Related SER 8.3 SSER , 22 Section: 8.3 SER/SSER Impact N
Attachinent to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPT10N Page 92 Prefix Page Gmug Descrintion Section.
f as amende.d}
8.3 10 2 Sheets 7 and 9 Table Adds Personnel Airlock Ilydraulic l' ceder Control Panel CP141SCPEll-01 and itsjustification to the table for Electrical Equipment Not Requiring Internal Cable Separation.
Revision Sec justification for change on page I A(II) 54.
Change Request Number SA 83 .5 Related SER 8.3 SSER . 22 Section: 8.3 SEIUSSER impact N 8.3 10 2 Sheet 7 Table Adds Unit 2 EDG RTDs to the table for Electrical Equipment Not Requiring internal Cable Separation.
Addition The only credible failure modes for the Emergency Diesel Generator (EDG)
RTDs are an open circuit or a short circuit which can cause false temperature indication that does not have a safety function. Since the Pil)s are passive devices, an opea circuit does not result in any unusual voltap or current in the circuit; also the RTDs being connected to high impedence c w onic devices, short circuits at the RTDs produce very small short circuit currutts. Therefore these conditions do not adversely affect the performance of Class IE circuit.
Change Request Number S A 135 . O Related SER : 8.3 SSER* 22 Section: 8.3 SEIUSSER impact N 8.3- 1 I 2 Sheets 2 and 3 Table Deletes inverters XVIC2 and IVIC3 from list of "Non-Class IE equipment connected to safety related power circuits". Adds to the list bypass transformer TIC 3.
Addition Secjustification for changes to page 7.6-1.
Change Request Number S A 60 . 10 Related SER 8.3 SSER- 22 Section: 8.3 SER/SSER impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 93 Prefix Page Oroup Dsstiption Section; (BA amended 1 8.3- 1 I 4 Sheet 2 Table Change tag number in the tab!c from CPI AFAPTD-Ol" to
" CPI-EIPRLV-4 8".
Editorial his change is considered to be of editorial nature to reflect tag numbering change; there is no change to the physical equipment.
Change Request Number SA 138 . O Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N 8,3- l 3 Figure Revise figure to depict new power supplies to MOVs and PLC Addition A new non-safety related MCC, XIll-8 is provided to fec'l the new loads for this upgrade, his MCC will provide for the new motor operators and programmable logic contoller (PLC) for Unit i Condensate Polishing System.
He addition of the new electrical loads has been evaluated t , SE 94-007.
Change Request Number SA 76 4 Related SER 8.3 SSER - Section:
SER/SSER Impact N 8.3- l 4 Figure Corrected Ammeter tag numbers for CCW Pumps.
Editorial Editorial change to be consistent with project documents.
Charge Request Number SA 122 . 1 Related SER 8.3 SSER , 22 Section: 8.3 SER/SSER impact N 8.3- 5 4 Sheets I and 2 Figure Deletes the table identifying relay details from the FS AR figure.
Editorial The relay detail deletion from the FSA R one line diagram for 6.9 kV auxiliaries is considered an editorial change. These details are not required per Regulatory Guide 1.70.
Change Request Number S A 89 .2 Related SER SSER , Sectica:
SER/SSER Impact N
Attachment to TXX 98015 i CPSES - UPDATED FINAL SAFETY ANALYSIS IWPORT AMENDMENT 95 DETAILED DESCRIPTION Page 94 Prefix Page Group Descrintion Section.
(as amended) 8.3- 5 4 Sheets 1 & 2 I'igure Add tag numbers for 6 6 kv bus alternate feeder breaker, Added note referencing cable disconnects for CCW Pump, Circulating Water Pumps, rnd Condesate Pumps.
Editorial Editorial Changes to be consistent with project documents.
Change Request Number S A 122 . 2 Related SER 8.3 SSER . 22 Section: 8.3 SER/SSER 1mpact N h.3 - 3 Sheets 01 & 02 l'iguro Revises the Ogure to show diffstence in the electrical con 0gu ation due to the addition of the new digital governor system for Unit 2, Trains "A" and "B".
Revisio:
Sec justification for the change on page 8.3-26.
Change Request Number SA 153 . 1 Related SER 8.3 SSER 22 Section: 8.3 SER/SSER 1mpact N 8.3- 6 2 Sheet I l'igure Revises the Ogure to show ditTerence in the electrical cot:11guration due to the nddition of the new digital govemor sytem for Unit i Train A EDG.
Revision Same as justification for changes to page 8.3-26 pertaining to the new digital governor system for Unit i Train A EDG.
Change Request Number SA 143 . 3 Related SER 8.3 SSER. 22 Section: 8.3 SER/SSER Impact N 8.3- 7 3 Sheet 2 l'igure Revise figure to depict new power supplies to MOVs and PLC Correction See Summary of Changes for figure 8.31.
Change Request Number SA 76 .5 Related SER . 8.3 SSER Section:
SER/SSER 1mpact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 95 Prenx Page DInup Dsittin112tl Section:
(hs amended) 8.3- 9 3 Sheet 4 i l'igure Add UPS and Distribution Room Fan Coll Units to 480V Motor Control Center (l Eit4-1) Electrical Diagram.
Correction Sec justincation for l'SAR Section 9.4C (Page 9.4C-12).
Change Request Number SA 150 . 6 Related SER 8.3 SSER Section:
SEIUSSFR 1mpact N 8.3- 9 4 Sheets I thru 4 Figure Revise MCC loads descriptions for the following:
- 1. Motor Driven Aux Fewater Pump Room Fan 07
- 2. Safety injection Pump Mininow Isolation Valve.
- 3. Charging Pumps Si llender Isolation Valve.
- 4. Component Cooling Water To Reactor Coolant Pumps Coolers Containment Isolation Valves.
Editorial Editorial Changes.
Change Request Number SA 22 . I Related SER 8.3 SSER 22 Section: 8.3 SEtVSSER impact N 8.3- 9 3 Sheet 2 Sheet 02 Figure Add UPS and Distribution Room Fan Coil Units to the 480 Volt Motor Control Center (1 Ell 3 1) Electrical Diagram.
Correction Sec justincation For FSAR Section 9.4C (Page 9.4C-12).
Change Request Number S A 150 . 5 Related SER 8.3 SSER* Section:
SEIUSSER 1mpact N 8.3-9 4 Sheet i Figure Updates the Ogure to correct draning errors for Motor Control Center (MCC IElli- 1).
Update a
The same 11attery Charger was shown twice. Replaced one with the correc usage (llattery Room Exhaust Fan).
Change Request Number SA 29 .
Related SER 8.3 SSER 22 Section: 8.3 SER/SSER 1mpact N
Attacionent to TXX 980l$
i CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMiiNDMl;NT 9$
DETAILED DESCRIP'!!ON Page 96 Prehn Page Ognyp DEir.Ilpik'D bectfort.
(alJunElided1 8.3 9 2 Sheets I,2,3 and 4 l'igure Revises the figure to show spared 480 Volt circuits and other changes due to the new inverter configuration.
Addition See justification for ci anges to page 7.6-l.
Change Request Number S A 60 . 12 Itcla:cd SI:R t 8.3 SSER : 22 Scv "on: 8.3 SI:R/SSER impact N l
8.3 9 4 Sheet 4 thure Updates the f;gure to incorporate a change to Motor Control Center (MCC 11:114 1) that were inadvertantly not incorporated at the time the modification was performed.
1:ditorial Adds lis.ttery Charger llCID4 which was left out by drafting erret. This change was evaluaied earlier per SE 93 51.
Change Request Nu nber SA 29 .2 Related SER : 8.3 SSER : 22 Section: 8.3 SI;R/SSER impact N 8.3- 13 3 Sheet I thure Revise figure to depict new power supplies to MOVs and PLC Correction See Description of Changes for l'igur 8.31.
Change Request Number S A 76 ,6 Re ated SER : 8.3 SSER : Section:
SER/SSER impact N 8's- 13 2 Sheet i 11gure Revises the figure to show the new inverter configuration.
Addition Seejustification for chanres to page 7.6-1, Change Request Number SA 60 . 13 Related SLR : 8.3 F%ER , 2:: Section: 8.3 SER/SSER Impact N ,
l 4.
. - - . - _ ~ ~__ - ..- _.~ _.._ - - - ..-- --.-
Attachment to TXX 980l$ f CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT j AMENDMENT. 95 DETAILED DESCRIF110N 1 Page 97 PrensPage ilmug Dewrlotion Section:
(as amendsd) '
8.3 13 3 Sheet!
l'igure Revises figure to depict Unit i Steam Gencrutor Pump (50FP) Digital {
Controller being fed via SW IVIC$/6-ilS. j Revision lhe previous speed control for the Unit I turbine was not performing satisfactorily and was upgraded to a digital control. bGFP Digital Controller requires two 10-mmp power supplies AC powcr disconnects must be fed from l l' the 25 kVA inverter static switches due to normal distribntion panels txing l located in the cable spread room.
Change Request Number SA % h5 . 2 Related SLR : 8.3.1 SSER : Section: !
j 4 SER/SSER impact N 2
1 8.3 14 2 Sheets I and 2
- _ l'igure Rtvises the figure to renect the configuration and changes associated with the new inverter / battery charger installation. 1 l
Addition Sec justification for changes to page 7.61, I Change Request Number SA 60 . 14 Related SER : R.3 SSER : 22 Section: 8.3 SER/SSER Impact N ,
i-l R.3 14 A 4 Sheet 01 Figure Add tag number suflixes to Unit t FWp Turbine Emergency Lube Oil Pumps.
l- Editorial .
Editorial Change . Add the correct sullixes to the FWp equipment for proper [
identification. ,
Change Request Nur e er SA 22 . 2
! Related SER : R.3 SSER : 22 Section: 8.3 l SER/SSER 1mpact N i ,
8.3- 14 A 2 - Sheet I
- _-- Figure Revises figure to show the new configuration due to the installation of new inverters.
Addition Secjustification for changes to page 7.6-1.
Change Request Number SA 96 - 60 , 15 i Related SER : 8.3 SSER : 22 Section: R.3 ll SER/SSER 1mpact N h- j I
(L l
l W wvgpg ru'-'wgrwiy w-- - w +g q y re wy y--iggm-- y-rw w r='vQ+Mx1 4 -TM=T'rluw.=-17'
vY"w7-' w4" ' - *$r9D'y4r upy- -f4-'v'gr, - - - ' - -
g 9 y- em-t- w-*y-9-*rg--- Wp*v-r'i-ry + y
1 Attachmer' .i C;X 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILI:D DI.SCRipTION Page 98 Picfix Page Descrintion Stetion.
(as amended) (huur 8.3 14A 4 Sheet I l'igure Updated the Ogure to add "480V AC Switchgear XIl7 Control Feeders".
Update
'Ihis change was completed prict to Unit 2 licensing but the l'SAR Hgure was inadver".antly not updated at that time.1hc change affects a non-safety related Distribution panel (XD2 2, circuit 13). Circuit 13, which was previously shown as " spare" is now used for 480V AC S witchgear to supply non safety related water pretreatment system.
Change Request Number SA 29 .3 Related SER : 8.3 SSER : 22 Section: 8.3 SEIUSSER 1mpact N 0.3- 15 2 Sheets 1,2 and 3 l'igure itevises the Ogure to show the con 0 gun, tion associated with the new inverters.
Addition Sec justincation for changes to page 7.6.l.
Change Request Number S A 60 . 16 Related SEE : 8.3 SSER : 2J Section: 8.3 SER/SSIIR Impact N 8.3-15A 3 Sheet 02 l'igure Revises Ogure to show the power supply to the Unit 2, Trains "A" and *11" Emergency Diesel Generators governor control panels from distribution panel boards 2EC31 and 2EC41.
Revision Sec.justi0 cation for the change to ec page 8.3 26.
Change Request Number SA 153 . 2 Related SER : 8.3 SSER : 22 Section: 8.3 SER/SSER Impact N i
i
-,e---w- - , _ _ - _ , , m ,.
4rm .m---
Attachment to TXX 9Rul5 CPSliS - UI'DATIID FINAL SAFliTY ANALYSIS IlliPol(T AMI:NI)MI:NT. 95 I)l:1 All.1:1)l)l:SCRIPil(IN Page 99 Prefiz Page (MJunfudfdj QfeuD UCKdPd2Il hEEdON 8.3 15 A 2 Sheet 2 l'igure Revises figure to Show the power supply to the tinit i 1 rain A diesel generator governor controt panel from distribution panel board fl'.C31.
Itevision Same justification as for the changes to page 8.3 26 pertaining to the new digital governor system for Linit i Train A 1:1)O.
Change itequest Numler SA - 94 143 . 3 Related SI:n : 8.3 SSI:R : 22 Section: 8.3 SI R/SSI:R impact N 8.3 15A 2 Sheet 3
- l'igure Adds to the figure the configuration ihr 1 rain A and t rain il installed spare inverters.
Addition Sec justification for changes to page 7.61.
Change Request Nurnbet S A 60 . 17 Related SI:R : 8.3 sSI:R 22 Section: 8.3 SI'.R/SSI:R Impact N 8.3-15A 3 Sheet I l'igure Add alternate transibrmer 'l XI:Cl/2 with male-before break transfer switches to the non lli transformers TXI:Cl and TX1 C2.
Addition Non ll transformers TXI:Cl and TXI:C2 iced priority panciboards XI:Cl and XI:C2.1here are critical loads that require extensive contingencies in order to do maintenance on their respective supply transformers TXI-;Cl and TXI!C2.
This modificm.on will provide an altemate inmsformer TXI:Cl/2 with make-before-break switchen, the alternate transformer will fed from Xil2-2 with two new make-before break transfer switches to ensure that power can be transformed without interruption.
Change Request Number SA 96 8 .O Related Sl:R 8.3 SSI:R , 22 Section: 8.3 SI;R/SSI:R impact N
Attachtnent to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS IlliPOllT l AMI:NDMENT 95 DI;I AILI;D DI.SCRipilON page 100 prefix page Description Ecc@n; (as arntudtdj GIEUD 8.). 1511 4 SheetI l'igure Upa -.'s the Ogure to incorporate changes to safety related panel XC l that were inadvertantly not incorporated at the time the modifications were performed.
Update !
lhe changes include:
- 1) Circuit 1: Adds power supply to updated plant computer MUX cabinets.
., t
' 'the circuit previously also supplied the previous plant (1:RI') computer und this change was evaluated under SE's 92 207,93 45,93 78.
- 2) Circuit 2: llecomes termination Rack 1 1 C-41 (used for monitor lights).
1his circuit was previously used for the ERp computer and was " spared" aller the updated computer was installed. 'the change was evaluated under SE 96 34
- 3) Circuit 12 was revised from bcing used fot radiation monitoring to a
- spare".
Change Request Number SA 29 .4 Related SI:R 8.3 SSI;R : 22 Section: 8.3 SI:lUSSI:R 1mpact N 8.3 1511 2 Sheets I and 2 l'igure Revises Ogure to show the con 0guration for the new inverter installation.
Addition Secjustincation for changes to paFe 7.6-1.
Change Request Number SA - 96 60 . 18 Related SER : 8,3 SSER : 22 Section: 8.3 SER/SSER impact N 8.3 15C 3 l'igure Revise Ogure to depict new power supplies to MOVs and plc.
Correction See Description of Ch..nges for figure 8.31.
Change Request Number SA 76 .7 Related SI:R : 8.3 SSER : Section:
SI:lVSSER Impact N
, ~ _ _ _ . . - . _ . . _ - . _.~.._m _ _ . _ _ _ _ _ _ . - . _ . _ _ _ _ _ _ . _ _ _
Attachment to TXX.98015 i i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 -,
DETAlEED DESCRIPilON Page 101 l Prena Page l Group Description Section' (as amtlldsd) !
8.3-15C 4 l'igure Revises usage for circuit I which was previously
- spare" to be used for ERl' teceptacles.
I Update .
Updates the figure to incorporate a change to non-safety related il8v AC l distribution panel XC61 that was inadvertantly not incorporated at the time }
t the modincation was performed. ;
Change Request Number SA 97 -29 . $
Related SER t 8.3 SSERt 22 Section: 8.3 f SER/SSER Impact N i
8.3 l$C 3 l'igure Revises ngure le %ict Unit i Steam Generatro Feedwater Pump (SOFP)
Digital Conu.br leQd via SW IVICS/6-ilS. ,
t Revision ;
See description for ogw d.313 sh.l.
Change Request Number S A 85 , 3 Related SER : 8.3.1 bSER : Section: (
SI:R/SSER tmpact N 1
1 9.1- l $ 3 Pages 16 & 20a Adds new Spent l'uel l'ool (SFP) level devices (X IN-41849A 1, X IN 4849A.2 X.IN-4849111 and X.IN-4849112) to provide 2-out-of 2 logic for Spent Fuel Pool cooling pump protection on low. low pool level and continuous level indication in the control room. l Addition Secjustincation for I A(il) .53.
Change Request Number SA 110. 3 [
Related S!!R : 9,1.3 SSER : 22 Section: 9,1,3 SER/SSER 1mpact N ,
v t
- 9.1= 32 2 Section 9.l .4.2.3(14), ' fuel llandling System / System Description /
Component Description / Polar Crane," is being revised to allow the ,
following. Prior to entering outages, crane operation is required to perform ;
certain inspections, functional checks and preventative maintenance (PM) activities. The polar crane may be energized during MODES 1-4, ne crane will remain essentially in the park position (FS AR Figure 1.2-8). No load .
will be carried during MODES 1 4, A compensatory measure (operator, in direct communication with the control room, at the power supply disconnect outside containment) is established to prevent inadvertent operation of cranc i
h 4
W r ,--.....L ,._-..a.4, f_ .i . --,.._;-, ,L---,J-..._ ...-.m..._A...__,-.
, t. - . .n.. . ,, 1., L. . . 4. . _ - -
Attachment to TXX48015 1
1
(
CPSIIS - UPDATliD FINAL SAFI!TY ANALYSIS RIIPORT )
AMI:NI)MI:NT 95
!)l: Tall.l:1) l>l: SCRIP 110N Page 102 Preils Page Un'itD Dustipik!D SIElic!E LM.Atutndsd) due to liigh Energy 1 ine lireak in containment.
Revision Should e I.OCA or MSI.Il occur during c'ane operation the potential exists for the crane to operate spuriously due to environmental cliccts causing damage to the anfety related SSCs imide the reactor building. To preclude this from occurring during operation of the crane during MODI;S l 4 an operator in communication with the Control Room shall be stationed at the power kupply disconnect outside containment. Should either area become uninhabitable the operator shall open the power disconnect and leave the area. Any movement of the crane should be small enough so that the operator can safely exit the cranc.1he crane is to temmin essectially in the designated park positon (l'SAR l'igure 1.2 81. The hook should not be placed in a hication to impact any safety related structure system or component ( c.g. hydrogen recombiners). No load is to be carried by the crane. The limitations imposed by this change will be incorporated into the appropriate maintenance procedures.1his aulvity does not p%c any unreview safety questions.
Change Request Number SA 35 .I Related SI:R : 9.1.4 SSIR. 22 Section: 9.1.4 SI:luSSisit impact N 1
9.2 17 4 Replace the existing Unit I air compt er. sors and dryers with more capacity and more ellicient units. Ihese compressors are supplied with 480V ll?
power and cooling water from the non safeguards loop of the CCW System, it also changes the system parameters identified in the tables and flow path reflected in the flow diagrams.
Update See Justification of Change for page 9.3 4.
Change Request Number S A 69 .2 Related SI:R 9.2.2 SSI:R : 25 Section: 9.2.2 StilVSSI:R Impact N 4
9.2-36 3 pages 40, $3 A 54 Revision to relicet abandonment and removal of Water Treatment System l'quipment.
Revision
'the addition of more modem Water Treatment System I:quipment has made the abandoned and removed equipment obsolete.
1he abandonment and removal of the Water Treatment System equipment has no impact on the design or operating parameters of any equipment important to safety.
Change Request Number SA 78 .l
Attechment to TXX.98015 CPS!!S . UPDATIID FINAL SAFIITY ANALYSIS RIIPORT AhiEhDMI:NT 95 DETAILI:D DI:SCRIPilON Page 103 Prefla Page Onmp Descrip.110D firEllen; (as amended)
Related SI:R t SSI'R - Section:
SI:lVSSI:R Impact N i
9.2 37 3 Add a new paragraph to the
- System Description" to reflect the current operating philosophy of the radioactive waste systems.
Revision
'ihe current operating philosophy of the radioactive waste systems is to not contaminate the RMWSTs. As such, several system valves are being administratively maintained in the closed position. The new paragraph added to the I'SAR documents the current operating philosophy, This change provides further assurance that tritium contaminated efnuents will not be released to the RMWSTs.1his change does not adversely impact the llR system or other radwaste systems.
Change Request Number SA .97 4 .I Related SER : SSER : Section:
SEIUSSER 1mpact N 9.2 3R 2 Revises the discussion of now restriction orifices in l'SAR Section 9.2.3.3, "Demineraliied and Reactor Water Makup System, Safety Evaluation."
Revision
'the Unit I and common portions of the Reactor Water Makeup system are being modified to reduce overall system pressure problems and enhance pump availability. 'lhis modification includes (1) increasing the slic of the pump miniflow lines and recirculation lines back to the Reactor Water Makup Storage (See Change Request Number SA 96-55.1 on Table 3.911-10, sheets 22 & 23),(2)rehicating Dow restriction orifices from the pump's discharge to the applicable supply lines (Change Request Number SA 96 55.2), and (3) adding surge suppression.
1he Unit I and common changes are being implemented during the Ofth refueling outage of Unit I, The Unit 2 changes are being implemented during the third rufueling outage of Unit 2.
Any credible failure mode of the non-safety non-seismic cross tie header will be isolatabic and will not climinate the Safety-related protection provided for the Reactor Makeup Water Pumps via tbc min! flow to tank recirculation configuration.
l'SAR Figures 9.2 5 (MI 0241-01 & M10242) and 9.310 (MI-0255-02) are also being revised.
t
Attachment to TXX 98015 1
1 CPSl!S - UFDAT1?D FINAL SAFliTY ANALYSIS RiiPORT !
I AMI:NDMI:NT. 95 DI: Tall 1D !?ESCRIPTION Page 104 Preik Page LVJdplina Section.
(AL.amtadt.d) OmuD Change Request Number SA -96 $5 .2 Related SI:R : 9.2.3 SSI:R : Section:
SI:R GSI:R impact N 9.2-38 2 r
Revisen the discussion of flow restriction orifices in i SAR Section 9.2.3.3,
- Deminerailred and Reactor Water Makup System, Sar cty Evaluation.
Revision
'the Unit 2 portion of the Reactor Water Makeup system is modined to reduce overall system pressure problems and enhance pump availability 'this modification includes (1) increasing the site of the pump miniflow line and recirculation line back to the Reacto. Water Makup Storage (See Change Request Number SA-96 56.1 Table 3.911 10, Sheet 22) and (2) relocating flow restriction orifice from the pump's dScharge to the applicable supply lines (Change Request Number SA-96 55.21 1hc Unit 2 changes are being implemented during the third refueling outage of Unit 2.1he Unit 1 and common changes are being implemented during the finh rufueling outage of Unit 1.
Any credible failure mode of the non-safety non seismic cross tie header will be isolatable and will not climinate the Safety-related protection provided for the Reactor Makeup Water pumps via the mininow to tank recirculation configuration.
l'SAR l'igure 9.2 5 (MI-024 l-01 & M2-0241) is also being revised.
Change Request Number SA 56 .2 Related SER : 9.2.3 SSI:R : Section:
SEIUSSER impact N 9.2-41 4 Page 42 Revise description of the sewage treatment plant. The daily flow on the new plant is slighly smaller than the old plant. The sewage treatment plant is now referred to as domestic waste treatment facility. Waste water is now treated with ultraviolet light instead of chlorination. Sludge is now dewatered and bagged for disposal.
Revision
'Ihe changes are required to update the description of the sewage treatment system in the FSAR.1he new domestic waste treatment facility replaces entirely the old sewage treatment plant. 'Ihe innuent and efuuent locations, the plant type, and the permitted ellluent limits are unchanged. No change to the sewage collection system was made. 7hc elliuent is now treated with high
Attachment to TXX 980l$ !
CPSl!S . UPDATI?D FINAL SAFliTY ANALYSIS RiiPORT AMI:NDMI NT 95 vi!! Ai1.l:D DI: SCRIP 110N Page 105 Prefix Page CtMtp Descrintion Struen:
(almutadtd)
' intensity ultraviolet light to disinfect the eIlluent instead of chlorination 1hc sewage sludge is now dewatered on site and baggcd for disposal in landfills.
Change Request Number SA -97 37 .I 1(elated SI:R : SSI:R . Section:
SI::lVSSI:R impact N 4.2 46 4 Update SSI heat load description to match TXX 94325 and Section 9.1.3.1.
Correction
'the spent fuel pool heat load for the SSI in Section 9.2.5.3 has been superseded by TXX 94325 and Section 9.1.3.1.1he primary I'SAR section was updated with the new design basis. TXX 94325 states that the bounding '
SSI heat loads envelope the new spent fuel pool heat loads.
Change Request Number SA 95 . I Related SI:R : SSI:R : Section:
ct:lUSSI:R 1mpact N 9.3-2 3 Pages 6 & 13 Revise Service Air compressor description to describe the new common compressor and note that the existing unit specific Service Air compressors are abandonded in place.
Revision 1his change will install a new common Service Air compressor and revise the equipment description and component characteristics consistent with the new
' compressor, the existing Service Air compressors are inoperative due to mechanical and electrical problems that are too costly to repair. The existing unit specific compressors are abandonded in place and will be removed at a later date.1he new compressor will replace a temporary portable compressor and will provide a reliable source of Service Air to the plant.
Change Request Number SA 97 - 83 .I Related SIIR : 9.3.1 SSI'R : Section:
SI:lVSSI'.R impact Y SIIR Section 9.3.1, ist paragraph 7th sentance, should be revised to state
"'lhe service air system, shared by both reactor units, is supplied by one common compressor."
1he new compressor will replace a temporary portable compressor and will provide a reliable, acceptable source of service air to the plant. 'The Service Air system is non-safety related and not required for safe shutdown, l
l
Attachment to TXL9 sol $
Cl>SIIS - UI'DATIID FINAL S,sFETY ANALYSIS REPORT AMI:NDMENT. 95 DET AILED DI: SCRIP'llON 1
Page 106 Prella Page htth'II; (Atatnttidul) Omup Dusth' lie!!
9.3 4 3 Replace the existing Unit I air compressors and dryers with more capacity and more etilcient units.1hese compressors are supplied with 480V lli power and cooling water from the non-safeguards loop of the CCW System.
i It also changes the system parameters identified in the tables and flow path teflected in the flow diagrams.
Correction 1he replacement of the existing air compressors and dryers with the larger capacity units will enhance the quality and quantity of the high grade clean dry air which supports current as well as future plant operation. The new compressors and dryers have a higher power demand and are analyred for the d;esel generator loading. The changes described here affects various sections, tables and flow diagrams of the I'SAR.
Change Request Number S A . 96 69 . I Related SI:R 9.3.1 SSER : 23 Section: 9.3,1 SER/SSI:R lmpact N 9.3 8 l 1his change revises information with respect to the bases for siring of the air reservoirs associated with operation of the SO power-operated atmospheric relief valves. lhe change is to identify that SGTR is the primary safety function.
Correctinn 1he change is to delineate the actual CPSES as designed plant.1he PORV air reservoirs are sired for 15 operations over a nominal 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of operation, followed by local manual control.
Change Request Number SA .96 38 .2 Related SER : SSER : Section:
SEIUSSER impact N 9.~.- 14 4 1his change revises the reference to Chapter 16 to directly refer to the Technical Specifications.
Clarification Chapter 16 no longer contains the current Technical Specifications. Therefore, references made to l'SAR Chapter 16 are removed and revised to refer directly to the Technical Specifications.
Change Request Number SA 125 . 7 Related SER
- SSI:R : Section:
SER/SSER Impact N
Attachtnent to TXX 98015 1
CPSIIS - UPDA'I ED FINAL SAFIITY ANALYSIS REPORT AMI:NDMENI~. 95 DI:T Alli;D DESCRIPTION Page 107 ;
Prefix Page Otsp Drgdplim ficcum; (as amended) 1 9.3 15 3 Page 20 Addition of the Anslyrcrs and Detectors to continuosly monitor the pil of the
' Steam Generator Illowdown Samples . Add pil as a continously monitored parameter.
Correction 1he new Analyrers will enable the project to inore closely monitor the $ team Generator environment and comply with Epi;l requirements.
Change Request Number SA 29 . 1 Related SI:R : 9.3.2 SSER : Section:
SER/SSI:R 1mpact 9.3 25 4 Clarification to section 9.3.3.2.2 to make the discussion on sumps applicable to both units.
Clari0 cation in the Safeguards lluilding, there are a total of three floor drain tanks. Tank No. I receives drainage from Unit i Safeguard llullding, Tank No. 2 receives drainage from Unit 2 Safeguards lluilding, and Tank No. 3 does not receive drainage from either Safeguards lluilding.1his change to section 9.3.3.2.2 is a trivial clarification to make the discussion on sumps applicable to both units.
'Ihe propried changes do not constitute a change to the facility as described in the l'S AR.
Change Request Number SA . 97 106. 1 Related SI R :
- SSER : Section:
SLR/SSER impact N <
9.3 33 3 Pages 36,40,47,49,6! and 78 Revise Chemical and Volume Control System (C JCS) Section 9.3.4 (Sheets 33,36,40,47,49,61, and 78), and I' low Diagram M 1 0254) to tellect addition of bypass line and valve which allaws additional Ocxibility for eleanup of letdown now. It also reficcts that the lloror. Ihermal Regeneration System (11TRS) demineralliers can now, in add! tion m sheir previous functions, be utillied to prov!de supplemental or enhanced cleanup of CVCS letdown flow.
Revision 1his modi 0 cation will provide additional Acxibility for cleanup of CVCS letdown now during periods of Reactor Coolant System (RCS) contamination.
I'lexibility will exist to allow alignment through various combinations of mixed bed, cation bed, and 11TRS demineralliers.1he llTRS demineralliers may be loaded speci0cally to perform cleanup of CVCS Ittdown Dow. 'the function of the CVCS to maintain the reactor suberitical through boration to compensate for menon decay and burnout is not afTected. Iloration in conjunction with the HTRS to accomodate design plant load follow will
_ . . ..__ _ .. __,,_. _ ___ _ _ _ _ __ _ -. ._ _ _ _ - -_ _ ._ .__ _ _ _ _.m. _._. .._.
Attachment to TXX.98015 4
CI*SliS . UI'DATliD FINAL SAFl!TY ANALYSIS Rill' ORT AMl:NDMl:NT. 95 f I DI: Tall.l:D Di'.SCRil'110N l 4
Page 108 [
j Prefh Page .
02M0 Dustipil9a Snilun; i
{ fan ameridsd) continue to be available.1hc CVCS and IITRS functional requirement and l j
' capability to provide boration and dilution of the RCS will not be affected. ,
lhls modification does not intaxiuce or increase the potential for inadvertent :
dilution of the RCS.1hls change applies to Unit 1. {
Change Request Number SA .96 31 . I l
Related SI:R t 9.3.4 SSIRt Section:
SI:R/SSI:R 1mpact N l l*
93 36 4 2 Replace "1he read out of the boron concentration is given in the Control -
Room" with
- 1he lloron Concentration Measurement System is abandoned ;
I in place".
Revision j
Secjustification for revision to Section 7.7.1.10, page 7.7 27.
Change Request Number S A . 97 79 , 7
!' I Related $1:R t SSI.R : Section:
SI:R/SSI:R 1mpact N i
? f 9.3 39 4 Clarification is added based on the pit control philosophy employed for prhaary chemistry control.
Water Chemistry.
- Change Request Number SA 97 99 . 2 ,
Related SICR : SSI:R : Section:
SI:R/SSI:R 1mpact N 4
+
9.3 42 4
' - Delete the description of the lloron C'ancentration Measurement System and the reference to Section 7.7.
Revision Secjustification for revision to Section 7.7.1.10. page 7.7 27.
Change Request Number SA 97 79 . 8 i j7- Related SI:R. : .
SSI:R : Section:
SI R/SSI:R impact N 4
, - . . - , - _ _ _ , , , . - - + m. ,..e+ ,.,m. _
,,.f.,w .g. g. p-m . , m .9 r.y+# 7,.r#,---. ~ + - + y
Aitachment to TXL98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 l DI:TAIEED DESCRIPTION Page 109 Prefix l' age
[ns amendsdj Group DsEncilun Section:
9.3 47 4 Delete the description of the lloron Concentration Measurement System and the reference to Section 7.7, Revision Sec justification for revision to Sectio 17.7.1.10, page 7.7 27.
Change Request Number S A 79 .9 Related SI:R : SSER : Section:
SI:IUSSER Impact N 9.3-51 4 I
Clarification is provided on the operation and sampling of the botic acid transfer system.
Clarification Clarifications based on operating esperience with the system.
Change Request Number SA 132 . 1 Related SI:R : SSER : Section:
i SI:IUSSER 1mpact N 9.3 87 3 PageR8 Add a new paragraph to the " System Description" to tellect the current operating philosophy of the radioactive waste systems.
Revision See Justificathn of Change for 9.2-37, Change ?* st Number SA 4 .2 Related SER : SSER : Section:
SEIUSSER 1mpact N 9.3- 1 4 Sheets I, 3,4,5,6,7,8,9 Table Replaec the existing Unit I air compressors and dryers with more capacity and more ellicient units. 'Ihese compressors are supplied with 480V IE power and cooling water from the non-safeguards loop of the CCW System.
It also changes the system parameters identified in the tables and flow path reflected in the flow diagrams.
Update See Justification of Change for page 9.3-4, Change Request Number SA 69 .3 Related SER 9.3.1 SSER : 23 Section: 9.3.1 SEIUSSER impact N
.- - - - - __ , - , - - - ~. - ._ .
i Attachment to TXX 9H015 I l
CPSI!S - UPDATI!D FINAL SAFIITY ANALYSIS RIIPORT AMI:NDMI:NT 95 DI Tall.1:D DI:SCRIPTION Page i10 Prefix Page Latsurndui) DInup Ducription firstles
- 9.3 2 3 Sheets 1 & 2
'I able Revise the table to describe the new common Service Air compressor characteristics.
Revision See Justi0 cation of Change for 9.3 2.
Change Request Number SA 83 . 2 Related SI:R : 9.3.1 SSI:R : Section:
SI:R/SSI:R impact N 9.3 4 3 Sheet 3 1able Addition of the Analyrers and Detectors to continuosly monitor the pil of the Steam Generato lilowdown Sarnples . Add pil as a continously monitored parameter.
Correction See Justification of Change for 9.315,20.
Change Request Number SA 29 .2 Related SI:R
- 9.3.2 SSI:R : Section:
SI:R/SSI:R Impact 9.3- 4 4 Sheets 1. 2 and 3 Table Revise the sampling analysis requirements and locations to agree with the Technical Specifications Correction The table has several sample locations which list *O" under parameter measured.1he "O" corresponds to other laboratory analysis as required by the Tecimical Specifications. 'This is an incorrect catch all which should be deleted as it implies further analysis is required beyond the specifics which are listed. Additionally, errors exist in the purpose and application of a few sample hwations.
Change Request Number SA 112 . I Related SI:R : SSI:R , Section:
SI'.R/SSI:R 1mpact N
Attachment to TXX.980l$
CPSI!S - UPDATED FINAL SAFIITY ANALYSIS RIIPORT AMI:NDMENT. 9$
DETAILLD DI:SLlHPTION Prefix Page Page iII Ikuup thaidctlett hndun;
[as amendnD <
9.4 1 4 Change Room 142 from ' laker Room" to "Womens Toilet R(mm" in the l Control Room Complex. Also Rcom 141 from " Toilet" to
- Men's Toilet *.
Addition 1he rest room accommmlations at the Control Room presently consist of a single fac tity. Operations now has female SRO's on duty necessitating that 8
both men and women facilities be available at the Control Rmun Complex.
1he additional water closet and sink will add no 6lgnificant additional water loads to the Potable Water and Sanitary Systems.
1hc changes to the l'SAR documentation are minimal involving identification ;
changer to the existing toilet room and the existing locker room.
Change Request Number SA - 96 4I .I Related SER 9.4.1 SSI:R : Section:
SliR/SSER Impact N 9.4 26 2 Pages 27 and 28 Add normal and backup air conditioning units for Digital Control Room h>cated in Turbine lluilding.
Add Roof Ventilators for Main l'ced Pump area which are installed on the removable steel plate.
Revise the system description to remove the detail design requirements and provide the overall conceptual design of the system.
Addition Addition of Digital Control itoom acquires additional cooling capacity of the air conditioners which cools senisitive electronic equipment utilized to monitor Main I'ced Pump activities.
New roof ventilators were installed over the Main l'ced Pump area on steel plate on the Turbine fluilding deck.1hese ventilators will provide additional heat removal capacity around the area and supports the existing ventilators during summer months.
Ihc system description is revised to remove the detail design parameters for the system and provide conceptual design of the system. This will help in case of addition or deletion of equipment required to meet the overall ventilation design criteria during summer months.
Change Regnent Number S A 3 .I Related SER : 9.4 SSER : Section:
SI:R/SSER Impact N
l i
Attachment to TXX 98015 CPSIIS - UPDATIID FINAL SAFIITY ANALYSIS REPORT AMENDMI;NT 95 DI:TAILI:D DI:SCRipl10N l Page 112 Prefix Page (ALamcaded) Oteup Descrintio2 Srctietu 9.4 2 4 Sheet 4 l able Add to the note *"","1he reactor cavity exhaust temperature in 15 degrees higher (e g.,1501' and 190 i respectively)."
Correction Clarify that the reactor cavity temperature is 15 degree higher than 135 F -
normal temperature and 175 F. occasional temperature spike (e g.,150 F and 190 F respectively).
Change Request Number SA 97 - 135. 8 Related SLR : 9.4 S$t:R : 22 Section 9.4 SER/SSER Impact N 9.4 2 3 Sheet 03 1 able Delete relative humidit3 of *50%" for Turbine lluilding Tool Room and add '
"*" indicating to maint. sin uncontrolled relative humidity.
Correction Oflice and Scryice alt is mixed with the Primary Plant supply air in the Turbine llullding tool Room 1his mixing of air supplies negates the humidity control feature of outside supply air, Change Request Number S A - 97 = 120 . 2 Related SER : 9.4 SSER
- 22 Section: 9.4 SER/SSI:R impact N 9.4 4 3 Sheet i Table Correct the prefilter atmospheric dust spot emclency rating from 85 % to a range of 80 to 95 %.
Correction 1hc prefilter emeiency as per ANSI N5091980 should not be less than 45%
according to the average dust spot test. The prefilter media typically comes in rangen of emeiency, such as 80 - 85 % emcient or 90 - 95 % efficient media.
1he revised filter emciency, in ranges, still meets the requirements of ANSI N509 1980. Widening the allowable prefilter emciency range will not alTect the llEPA fiter downstream or change the emeclency of the total filtration unit, lhe prelliter function will protect the llEPA filters from the mqjority of particles.
Change Request Number SA 98 .O Related SER : 9.4,6.5. SSER : 22 Section: 9.4,6.5.
SER/SSER impact N
__ _ _..m.._____-_.-__ _ _ _ . _ _ _ _ . _ - - - . - - _ _ _ . _ _ _
J Attachment to TXX.9160l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENr+ 95 DETAILED DESCRIPTION Page 113 Prefla Page
' Group Descrintion Section.
(as amendsd) i 9.4 4 2 Sheet 3 j
Delete R ll2 and add Approved attemate for filter leakage test reouirements.
Table Add " allowable for in place tents" to Peretration. %. ,
Clarificatkin l
Addition of approved alternate of R ll will provide the use of other refrigerant ,
for lekage acceptance test of the filters.
- Clarify that " Penetration, %" is the allowable vaues of the leakage fbr in-place ;
test of the filter units.
j SA - 97 13$ . 9 Change Request Number SSER : Section: !
Related SER t SI R/SSER impact N l
! i 9.4 5 1 Sheets 1 & 2 Table - 1) Delete llent removal capacity of the cooling coils for Containment Air Recirculation and Neutron Descetor Well Units.
- 2) Add "(PPV Supply / Exhaust Units)" to Number installed for Normal Containment Purge Supply and Exhaust Subsystem.
1 Revision '
4 1)1hc tooling coil capeity will change frequently and is already exists in the Procject Controlled Design Bases Documents.
- 2) Clarify that the number installed is meant to say 1 for Primary Plant Supply f' Unit and 2 lbr Prirnary Plant Exhaust Units.
Change Request Number SA - 97 13$ . 10 Related SER t SSER : Section.
SER/SSER 1mpact N ,
l, 9,4 6 3 Table l'ollowing changes are made for todine adsorbers of the various plant filter systems:
- 1) llumidity control for Preaccess Filtration (2) Units and Controlled Access ;
Air Cleanup (12) Units are changed from "70(Max.)" to" Net controlled" (denoted by
- and footnote). ;
- 2) Correct the inlet air temperature to llydrogen Purge (2) Units from "250 (Max)" to "160 (Max.)".
3)llumidity control for Control Room Emergency Filtration (2) Unlis are #
changed from "70 (Max.) to " Contmlled by Control Room Air conditioning -
Units"(denoted by " and footnote).
Correction 1)'Ihe Cootainment Presccess Filtration Units and Nonnal Primary Plant -!
Filtation Units are designed without heaters for controlling the humidity below 70 %.
2)1hc ilydrogen Purge Units can operate with up to 160 r inlet air .
l I
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI NDMI:NI'. 95 .
Dl! Tall.l:D Dl SCRIPTIDN Page i14 henn Page f.hwp Dei,criotion hrstion; (tiputruded) '
temperature and is consistent with 1*SAR Section 6.2.5.1.3.
3)1he Control Room I'lltration LJnits are designed without heaters for ,
controlling the hurnidity below 70%, however humidity is controlled by Control Room Air-conditioning Units.
Change Request Number SA 135. 11 Related SI:R t 9.4 SSI:R t 22 Section: 9.4 '
SI:R/SSI:R trnpact N 9.4 A. I 3 Pages 4 & 5 tJpdate the description of Containment Ventilation Systems to describe the function of the CRDM coils.
11pdate 11pdate the Containment Ventilation Systems to incorporate the CRDM cooling coils, which is consistent with as-built design. 'Ihis change does not change technical function of the systems und their is no safety impact on these nan safety systems.
enange Request Number SA 135 . 3 Pelated SI:R : 9.4 SSER : 22 Section: 9.4 SER/SSER 1mpact N 9.4A 5 3 l } Correct the description to delete "Gltered" and add "two cooling coils"for each cooling unit for the Neutron Detector Well Cooling System.
- 2) Change the description from " Preaccess ultration equipment is .. . to "
Preaccess filtration equipment can be . . ".
- 3) Add "with clean filters" for total air now of 30.000 cfm.
Correction
- 1) Neutron Detector Well Cooling System is a 100 % recirculation system in the Containment, which do not need air utter.1his chang is consistent with I'SAR Cow diagrams M10300-A and M2-0300-II.
Corrects the description to add "two cooling coils" for each Neutron Detector Well Cooling System and is consistent with the now diagrams M1-0300-A and M2 0300-A.
2)1hc Preaccess l'iltration IJnits are oper Aled only when the containment atmosphere requires cleaning up prior to entry.
- 3) Clarify the conditions at which it yields the 30.000 efm total for Preaccess l'iltration 1Jnits.
Change Request Number SA 135 . 4 Related SI:R 9.4 SSER : 22 Section: 9.4 SER/SSI:R Impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT- 9$
DI:TAILI:D DESCRIP110N I Page 115 Psefix Page f as amendgi) Onmp Descrirstion Section.
9.4 A 7 3 1his change deletes reference to the FSAR statement that the containment pressure reliefline is located in an enclosed room which does not contain any safety related equipment.
Correction The previous statement was incorrect. 'Ihe change is acceptable because isolation of safety related equipment is not required to protect the equipment following a LOCA.1he only potentialleakage path fro;n the containment building to the penetration area during power operation is the 18 in. diameter pressure relief line. A separate enclosed room is not required to protect nearby safety related equipment from affects of escaping air and steam following a postulated LOCA because: 1) the 18 inch pressure reliefline is orificed to 3 inches; 2) a control room alann alerts the operator if pressure
! exceeds nonnal maximum containment operating pressure,3) both pressure relief Containment isolation valves automatically close within three seconds after receiving the signal if high radiation is detected by the containment particulate lodine-gaseous monitor, on a phase A isolation signal, or on containment ventilation isolation, and 4) leakra testing of the containment penetration and the penetration isolation valve response time surveillance are performed quanctly.
Change Request Number SA 160, O Related SER : SSER : Section:
SI R/SSI:R impact N 9.4 A- 7 4 Correct the sentence to read as, "Two Primary Plant Ventilation Exhaust System (PPVS) Alter plenums with associated fans are required to maintain design purge rate", for Containment Purge Supply and Exhaust System Clarification Clarify that each Containment Purge Supply and Exhaust System has one-100% Exhaust l'an, whlch delivers exhaust flow to the two PPVS Exhaust Plenums. "Ihis Exhaust is process through the PPVS filter units and exhausted by the associated exhaust fans to the plant vent stack.,
Change Request Number SA 135 . 5 Related SER . 9.4 SSER : 22 Section: 9.4 SER/SSER 1mpact N
Attaarnent to TXX.9hol5 i
CPSES - UPDATl!D FINAL SAFETY ANALYSIS ItEPOllT AMI:NDMI:NT. 95 DI:TAl!J.D DI:SCRIPTION Page 116 Prefis Page fitws Drsticlien Srstletu (atamendtd) 94A-R 3 Delete,
- functional testiag of these valves is accomphshed concurrently with the other containment sentilation valves, rather than individually" t 'ection s :tional testing of the Containtnent Ventilation valves are described in the l'5AR Section 7.3. It in deleted from this section to avoid duplication.
Change Request Number SA 13$ . 6 Related SLR : 9.4 SSI;R : 22 Section: 9.4 Sl:R/SSl:R Impact N 9,4 A 11 3 Delete the statement that the Containment Preaccess Iiltration Units have charcoal tested at intervals not exceeding 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.
Correction All non-l:SF I iltration Units have a charcoal canister removed every l 8 months regardless of filter unit operation. This meets the requirements of Regulatory Guide 1,140, para C 6h and table 2.1his thange is also consistent with I S AR Sections I A(ll) for R.U.l.140 and 12.3.3.$.
4 l'.SF l'iltration Systems has a requirement to test the charcoal at intervals not exceeding 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> as per R.O.l.52, para C.6b and table 2.
Change Request Number SA 135 . 7 Related SFR 9.4 SS!'.R . 22 Section: 9.4 SI:lVSSI:R impact N 9.4C- l l 4 Correct the Ollice and Service Area llVAC System description as follows:
- 1) Deletc
- roof mounted inlet penthouse" and add " missile protected inlet".
- 2) Delete " an isolation Damper and" before roughing filter.
Correction Corrections are made to reflect the au built design as follows:
1)1hc inlet air to the llV AC System is through the west side of the Control flullding in lieu of inlet air through roof mounted inet penthouse.
2)lhe isolation damper is locatr at the outside air intake instead inlet of the Air llandling Unit. .ie inlet air and return air mises and passes through the roughing filter of the Alt llandling Unit.
Change Request Number SA 120 . I Related SER : 9.4 SSIR- 22 Section: 9.4 SI:R/SSF.R impact N
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(as amtuded) 9.4C- 12 2 Addr new safety related, class IE l'an Coil Units to the UPS equipment roorns 'lhe existing UPS chiller units will be retained and placed in standby mode of operation. 'Ihe new fan coil units will be powered from the respective 480V 11 safeguards bunes.1he cooling coils will be cooled by the Safety Chilled Water System. The existing safety chilled water pumps will be modined by the replacement of the existing impellers with a larger slie.
Addition
'Ihe existing UPS Room flVAC System consists of 2100% A/C chillers which provide coolinF for the four UPS l'quipment and Distribution Rooms. The UPS A/C units are common to both Units at CPSES and function to maintain the UPS Equipment and Distribution Rooms below the Technical Specifications ami, lent temperature limit.1his activity will add a safety related class Ili l'an Coil Unit to each UPS I.quipment and Distribution Room which in conjunction with the existing UPS A/C units will provide redundant safety related cooling to each UPS rooms.
1he new I'an Coil Units will provide cooling to the UPS rooms utilizing cooling water from the Safety Chilled Water System.1hc electrical power is
.cnlied from the 480V class lE MCCs. The new fan coil units are controlled from a % cal pannel anounted on the unit.
Change Request Number SA 127 . O Related SI:R : 9.4 SSER , 22 Section: 9.4 SI:R/SSER Im;sact N 9.41'. I 3 Pages 2 and 3 Modify the chiller pump impellers to handle the extra water flow required for the l'an Coil Units.
Correction Seejustification for l'SAR Section 9.4C(Page 9.4C 12).
Change Request Number SA 150 . 1 Related SER : 9.4.6 SSER , 22 Section: 9.4.6 SER/SSER impact N
Attachment to TXX 98015 i
CPSES - UPDATIID FINAL SAFIITY ANALYSIS REPORT AMI NDMI:NT . 95 DETAllt.D DI SCRIP 110N l Page i18 Pic0x Page (Atamtndnij 011M! Donipth!!! SIC 1hE 9.5-6 4 Change reference itom " Technical Specl0 cations
- to
- lire Protection Report".
Update lhe reference to the " Technical Specifications" is incorrect as the requirements has been trkicated to the "l' ire Protection Rep ert".1 heir is no technical change involved by reloction from 'lechnical Specificaions to l' ire Protection Report.
1hc l' ire Protection Report was earlier approva d by NRC.
Change Requer,t Number S A ~ 96 - 116 . O Related SI:R : 9.5 S$liR : 26 Section: 9.5 SER/SSI:R impact N 9.5 33 4 Change reference from " Technical Specifications" to "l' ire Protection Report".
Update lhe reference to the "Tecimical Specl0 cations" is incorrect as the requirements has been relocated to the "l'ir i Protection Report".1 heir is no technical change involved by relocation from Technical Specifications to l' ire Protection Report. 'the l' ire Protection Report was approved earlier by NRC.
Change Request Number SA 121. I Related Sl:R : 9.5 SSI:R . 26 Section: 9.5 SER/SSER Impact N 9.5-34 4 Page 35 Revise I'SAR Section 9.5.1.6.1 " Comparison with Appendix A ofIlranch Technical Position APCSin 9.51 of Standard Review Plan 9.$.1" Revision Secjusti0 cation for change request number SA.97 59.1 for pages 13.15,7,15,and 17.
Change Request Number SA $9 .5 Related SI:R : SSER : Section:
SER/SSER impact N
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DETA! LED DESCRIPTION Page 119 Prefix Page ias amends;1) Group DuniplicD fiEEliOE 9.5-47 4 Revise " Nuclear Production" to
- Nuclear Generation".
Revision Changed to tellect 1997 organization or1U Liectric.
Change Request Number SA - 97 129. 4 Related SER : SSER : Section:
St.R/SSER 1mpact N 9.5-68 4 Change reference from " Plant Technical Specifications" to "Olbite Dose Calculation Manual (ODCMP.
Update The reference to
- Plant Technical Specifications" is incorrect as the requiremnets has been rekicated to "ODCM". Iheir is no technical change involved by relocation from Plant Technical Specifications to ODCM. 'the ODCM was apprmed earlier by NRC, Change Request Number SA 121, 2 Related SER : 9.5 SSER : 26 Section: 9.5 SER/SSER impact N 9.5- 143 2 Correct the diesel generator piping and valve section to delete. "SA 105 Grade 11" and add stainless steel material for the fabrication of piping and valves for the Diesel Generator l'uct Oil and Transfer System. Editorial change from *oit diesel" to " diesel oil".
Correction Clarification that either stainless steel or carbon steel materials are used for the fabrication of piping and valves and meets the the ASME, Class 3 Code requirements of the Diesel Generator Fuel Oil and Transfer System.
' SA 94 ,1 Change Request Number Related SER : 9.5.4 SSER : 24 Section: 9.5.4 FER/SSER 1mpact N
Atta<.hment to TXX 9k015 CPSliS - UI'DATliD 1 INAI. sal:IITY ANAI.YSIS I(lil'OltT AMI:NI)MI:NT 95 DI:I All.1:D DI. scrip! ION Page 120 Prefis Page (nimmttided) 01 cup Donipik'11 Snlium 9.5- 145 3 Correct the description to clarify the effects of fhoding, truierate energy breaks on the Diesel Generator Systems.
Clarification
<' Clarify the eficcts of moderate energy line breaks (fioodingl, on the Diesci e Generator Systems, such that it may not be misinterpreted as to the function of the watertight doors and the basis for not alTecting any other equipment in the safeguards building is not solely based on the watertight doors since the compartenents are not watertight.1hc drain system and the opening to the pipe tunnels are shown on the figure 9.3 6. This clarification does not alter the I meaning of previous response to Q & R 040.19.
Change Request Nurnber S A 66 .O Related SI:R 4.5.4 SSI;R 22 Section: 9.5.4 SI:R/SSI:R Impact U 9.5 149 2 Co, rect the Diesel Generator Cooling Water Sysicm description to deletc
- fuel injectors" .
Correction Diesel Generator Cooling Water System provides cooling water to engine Jacket to cool the engine, w hich indirectly cools the fuel injectors.
Change Request Number S A 94 .2 Related Si R , 9.5.5 SSI:R 22 Section: 9.5.5 SI:R/SSI R impact Y SI:R, Page 9-40, Section 9.5.5, Second Para needs to delete the 'fuct injectors' from the components cooled by the Diesel Generator Cooling Water System.
Clarify that the fuelinjectors are indirectly cooled by the engineJacket which in turn cooled by the Diesel Generator Cooling System.
9.5- 152 2 j Correct the dew point requirements for the Diesel Generator Starting System supply air leaving in line dryer from " Dew point is minus 40 deg F at 250 j
psig" to "1hc air dryers are designed to maintain a dew point of at least 10 degree F less than the lowest espected ambient temperature."
Correction Clarifies the design data for the system supply air dew point requirements.
1he present dew point requirements in the l'SAR is from the in-line dryer vendor data and is not used specifically for the CPSliS Diesel Ocnerator g
y Starting Air System. A revised dew point requirement will essentially preclude moisture buildup in the compressed air system and is still consistent with SRP J
4 9.5.6 (Il-4.j).
Change Request Number SA 94 ,3 Related SI R 9.5.6 SSI R , 25 Section: 9.5.6
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SI:R/SSER Snpact Y !
SSER 22, Page 9 15, Section 9.5.6, Second Para should be revised to correct i
?
the dew point requirement frorn " Dew point is minus 40 deg F at 250 psig" to "1he air dryers are designed to maintain a dew point of at least 10 degree F '
less than the lowest expected ambient temperature".1his still tncet the j >
J requirements of SRP 9.5.6, Section ll.4.J. l 9.5- 153 2 Delete the phrase *(including seismic 11 requirements)" from FSAR Section f 9.5.6.3 (Diesel Generator Starting Syste n / Safety Evaluation).
Correction This phrase was referring to the compressors, aftercoolers, and air dryers.
' These componente are not sicsmic II.1hc supports for these components are siesmic 11 as described in Table 17A l.1his is an administrative change to ,
j incorporate the comment from SSER 25, Section 9.5.6.
Change Request Number SA 34 ,4 ,
Related SER : 9.5.6 SSER : 25 Section: 9.5.6 i
SER/SSER impact _ N j ;
This chege is consistent with Section 9.5.6 of SSER 25 which states:
3 "In Section 9.5.6 of SSER 22, the statistated that the air compressors, after-coolers, and air dryers were designed as seismic Category 11 components. In Amendment 80 to the FS AR, the applicant clarified that only the anchors and supports of these components are seismic Category ll. This does not change ti.e stalTs conclusions and the design is still acceptable because, despite a seismic event, the components will not fail due to a seismic event in a manner that will afTect safety related components in accordance with the guidelines of RO 1.29."
~
T -
9.5- 12 3 Table - Correct #om *IE02" to "lEGl" in the 'elTect on system' column for Diesel Generator Cooling Water System's Components . Jacket Water keep-wann >
i pump and standby electric heater.
Correction Revise the table to indicate that losing the Jacket water keep warm pump or standby electric heater have no efTect on the operability of Diesel Generator I EOl.1hese systems are plovided to enhance 6 tarting performance, reliability and reduce wear on the Diesel Generator. The Diesel Generator (IEOl) will start and run as reqGred w B' ,ut these support systems.
Change Request Number SA 94 ,4 Related SER : 9.5.5 - SSER : 22 Section: 9.5.5 SER/SSER Impact N- ;
9 s
-. .-. = - _ . -. - . _ __ _ _ - _ . _ _ . - _ _. .
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(Almnutdnl) OMI! DEKIF1h!D t 9.5- 13 2 Table Inserts two items (Compressor & Starting Air presmre floundary Solenoid Operated Valve l.SV.3421.ll:)into Table 9.5-13,"l'ailure Mode and I:ffects Analysis of Diesel Generator Starting System" Correction
'Ihese changes correct the table by adding missing functions to the single failure analysis.
'Ihe compressor refills the starting air storage tank. In a seismic event the DG starting air systern is protected from a loss of air (compressor failure) due to the Safety Class 3 isolation pressure boundary.
1hc starting air pressure boundary solenoid operated valve (1.SV.3421.ll!)
isolates the air receiver tank. Mechanical or electrical failure of the SOV results in loss of starting air for emergency IX) start. 'Ihis failure has no efrect on the starting air system since a redundant starting air subsystem is available.
Change Request Number S A 34 .$
Related SI R : 9.5.6 SSI R : Section:
SI:IUS$1:R 1mpact N 9.5 14 3 1able Correct from "II:G2" to "I f.Gl" in the 'elTect on system' column for Diesel Generator 1.ube Oil System's components . lube oil heater and pre-lube pump.
Correction Revise the table to indicate that losing lube oil heater or pre lube pump have no efTect on the operability of Diesel Generator II:Gl. 'lhese systems are provided to enhance starting performance, reliability and reduce wear on the Diesel Generator. 'Ihe Diesel Generator (11:01) will start and run as required without these support syuems.
Change Request Number S A 94 .$
Helated SI R 9.5.7 SSI:R 22 Section: 9.5.7 SI :R/SSIER Impact N 10.2-21 4 Revise l'SAR to indicate that the Condenser tilectric tow Vacuum Trip function will be tested via the F.xtended Turbine Protectiion (l?TP) test circuitry.
Revision Section 10 2.2.7.8 Testing and Trip Devices was revised as follows:
Clarifies item 1.c to more clearly describe that the Automatic Turbine Tester is capable of testirc the Condenser " hydraulic" vacuum safety devices. Adds description that the Condenser lilectric tow Vacuum Trip devices are tested
Attachment to TXX.98015 CPSIIS - UPDATiiD FINAL SAFIITY ANALYSIS REPORT AMENDMI:NT. 95 DI: TAILED DESCRIP110N Page 123 Prefix Page Grouo 12rstiption fie(tlon, LittDmmded) via the Extended Turbine Protection (ETP) continuous cyclic test feawre. 'ihe present Elec.ric Low Vacam Trip system and its associated A1T test program have been removed. Two separate pressure transmitters have been installed with separate sensh.g lines into the Vacuum Pressure Transmitter Rack. The pressure transmitters are connected such that a 2 of 2 logic is achieved. The preswee transmitters are wired to the ETP cabinet. The ETP circuitry performs cyclic diagnostic tests on the pressure transmitters for fault de'ermination and detection; hence the Electric Low Vacuum A1T test program was deleted. 'the Electric Low Vacuum Trip System was converted from a I of I to a 2 of 2 logic, in the event of a detection fault of one pressure transmitter, the ETP will automatically disconnect the faulted pres <ure transmitter and impose a i of I trip logic using the functioning pressure transmitter.
Change Request Number S A 70 . I Related SER 10.2 SSI:R : Section:
SER/SSER impact N 10.2 1 4 l'igure Revises Figure to add tag number to the Low Vacuum Trip logic input line.
Revision Pressnes switch (PS) SDl0P007 was tested as part of the automatic turbine trip
( A1T) test program but not by the surveillance program. This PS was replaced with a pressure transmitter and a second pressure transmitter (assigned tag number SD10P008) was installed with a separate sensing line in order to achieve a 2 of 2 trip logic. The testing of the pressure transmitters will be donc via the I:TP internal test logic. See description for Page 10.2 21.
Change Request Number SA 70 ,2 Related SER : SSER : Section:
SER/SSER impact N 103-2 4 Pages 3,6,7. 8 and 21 Section 103 Main Steam Supply System, terminology " Power-Opc.ated Relief Valves (PORVs)" is Scing changed to " Atmospheric Relief Valves (ARVs)" to be consistent with a previous change to the FSAR and the Technical Speci0 cations.
Clarification Sections 103.1 Main Steam Supply System Design Ilasts ,103.2.2 Power-Operated Relief Valves,103.4.2 Power-Operated Relief Valves and Table 103 3 Power Operated Relief Valves have been revised to consistently use the correct CPSES-specine terminology for these relief valves. These changes will make the rest of Section 10.3 consistent with a previous FSAR change to Section 103. 2. 2 in Amendment 79 which incorporated the
Attachment to TXX-98015 3
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 174 Prefix Page (as amended) Group Dngripliga Section.
CPSES-specilic nomenclature ' Atmospheric Relicf Valves" in lieu of
" Power-Operated Relief Valves (PORV)."
Change Request Number SA 84 .1 Related SER .10.3.1 SSER : Section: '
SER/SSER impact N SSER 10.3.!,3rJ paregraph, references that power-operated relief va!ves (PORVs) are provided for cach steam generator.1he change to FSAR Section 10.S to consistently use CPSES specific terminology " Atmospheric Relief Valves ( ARV6) in lieu of PORVs does not change the meaning of the previous description but merely improves its clarity Therefore, the change in tern.inology does not create a signficant impact to the SER.
10.3 22 4 Sheets 23 & 24 Update text with editorial changes to clarify the content of the FSAR ,
concerning water chemistry.
Clarification The proposed changes clarify the content of the FS AR and enhance the ability to understand the system description. This is not a technical change and does not change the meaning of the previous description and is therafore classified as a trivial change.
Change Request Number SA 119 . I Related SER 5.4.2.3 SSER. Section:
SER/SSER 1mpact N 10.3-2 4 Tcble Add Main Steam Safety Valve (MSSV) oritice size to FSAR Table 10.3-2.
Revision This is design information that is not required to be in the Technical Specifications and will not be in the improved Technical Specifications. This infortnation will be captured by adding it to the l'S AR.
Change Request Number SA 60 .I Related SER . SSER Section:
SER/SSER Impact N
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10.3 3 4 Table Section 10.3 Main Steam Supply System, terminology
- Power-Operated Relief Valves (PORVs)" is being changed '.o " Atmospheric Relicf Valves (ARVs)" to be consistent with a previous change to the FSAR ac 8 t; e Technical Specifications.
Clarification Sections 10.3.1 Main Steam Supply System Design liasis ,10.3 2.2 Power-Operated Relief Valves,10.3.4.2 Power-Operated Relief Valves and Table 10.3-3 Power Operated Relief Valves have been revised to consistently use the correct CPSES specific nomenclature for these relief valves. '!hese changes will make the rest of Section 10.3 consistent with a previous FSAR change to Section 10.3. 2. 2 in Amendment 79 which incorporated the CPSES-specific nomenclaturc " Atmospheric Relief Valves" in lieu of
" Power-Operated Relief Valves (PORV),"
Change Request Number SA 84 .2 Related SER 10.3.1 SSER Section:
SEIUSSER Impact N SSER 10.3.1,3rd paragraph, references that power-operate (t relief valves (PORVs) are provided for each steam gencrutor. The change to FSAR Section 10.3 to consistently use CPSES- specific terminology " Atmospheric Relief Valves ( ARVs)" in lieu of PORVs does not change the meaning of the previous description but merely improves its clarity. Therefore, the change in terminology does not create a signficant impact to the SER.
10.4- 6 4 Pages 7 and 9 Deletes references for installed conductivity elements.
Revision Section 10,4.1.1.3, Main Condenact Safety Evaluation, item 6 Control and Detection of Condenser I cakage, has been revised to delete "it illed" condensate conductivity meters. Section 10.4.1.1.5, Main Condenser Instrumentation Requirements, has been revised to delete " Conductivity elements detect leakage of circulating water into the condenser. These elements are located in the condenser hot wells and provide a continuous readout on a local panel." Section 10.4.1.2.5, Auxiliary Condenser Instrumentation Requirements, has been revised to delete " Conductivity elements descct the leakage of circulating water into the condenser."
Idghteen (18) conductivity c'. aments in each unit and associated hardware were removed from the Secondas, Sampling System and the Condensate System.
These specific conductivity elements were taken out of service due to air in-leakage problems. Ahhough these elen.ents were intended to pinpoint circulating water in-leakage into the condenscrs, they are not needed to comply with regulatory requirements regarding the monitoring of secondary side water chemistry because the possible inleakage will still be identified by the installed I
1
i Attachment to TXX 980l! 1 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 126 Prefix Page Descrintion Sssikgt; Lie.ntnsudsd) Omun sodium analyzers. This change will make the FSAR consistent with changes to the Design liasis Documents.
Change Request Number SA 106 . I Related SER 10.4.1 SSER : Section:
SER/SSER impact Y SER Section 10.4.1. 4th paragraph. 2nd sentence should be revised to state:
"The applicant monitors condensate conductivity by means of condensate monitors and by installed sodium analyzers at the condensate hotwell,"
Since the condensate conductivity monitoring will be performed by the installed sodium analyzers, any possible inicakage in the condensers will still be monitored. The FSAR and TS nqurements are still complied with regarding secondary side chcraistry.
10.4-33 4 Revise FSAR section 10.4.5.2 to clarify the existing piping materials used in the Circulating Water system and replace .he lining product name with the material type.
Clarification The proposed change clarifies tl.e FSAR to reflect the piping installed in the Circulating Water system. ONE Form 97 758 identified that FSAR section 10.4.5.2 stated the piping in this system should be Plasite lined carbon or stainless steel. This update to the FSAR reflects the materials used in the system as shown on the system flow diagrams /FSAR figures. All of the existing piping materials added (unlined carbon st<,el and plastic) meet the material selection requirements for piping materi Js used in this system. The pipe lining manufacturers product name (Plasite) has been replaced with that products material type (cpoxy). This information is contained in the system description portion of the FSAR for a non-safety related system. It is not the basis for any commitment or NRC acceptance in any SER/SSER nor is there any safety impact associated with the change.
r Lange Request Number S A 94 . I Related SER . SSER : Section:
SER/SSER Impact N
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CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAll ED DESCRIPT]ON 1 Page 127 Prefix Page Group Descri91ica Section.
[as amendssD 10.4- 36 4 DM 95-013 and DM 95-014 have provided plant computer inputs for the monitoring of containment dewpoint temperatures, as well as auxiliary and main condenser temperatures. These computer points are replacing existing recorders. Reference to the plant computer inputs .s included and reference to the recorders is deleted.
Correction include reference to the plant computer inputs for monitoring containment dewpoint temperature and delete reference to the previous recorders.
Change Request Number S A 100 , 2 Related SER SSER Section:
SER/SSER Impact N 10.4-37 4 in the last sentance of the second paragraph, delete the words "through diffusers located" and insert " Sodium hypochlorite and sodium bromide are drawn from storage tanks by 100% capacity pumps and distributed to the circulating water at the intake bajs".
Revision Initially, the sodium hypochlorite and sodium bromide were irdected into an 8 inch line containing Circulating Water that was pumped to the Chlorination fluilding. The " rated Circulating Water was then retumed to the Circulating Water intake Structure through ditTusers into the intake bays liigh pressure was noted at the normal chemical injection port due to restriction of the Circulating Water chlorination dilution headers, and Temporary Modification TM 94-005 was implemented to run the chemicals from the Chlorination fluilding directly to the bays in the Circuh. ting Water intake structure. As this method has proven to be acceptable and cost efTective, Design Change Notice 10264 was intiated to replace the abber hose allowed by the Temporary Modification with standard CPVC piping which currently exists on the skid.
The design basis and functional requirements are unaffected as the required chemicals will still be mixed into the Circulating Water to prevent fouling of the heat exchangers. The piping involved is all non-safety, non-seismic and is not quality related.
Change Request Number SA 64 , I Related SER 10.4 SSER Section:
SER/SSER impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAll.ED DESCRIPTION Page 128 Prefix Page (as amended) Group Descrintion $cetion.
10.4-44 3 Summarire Table 10.4-4 into Section 10.4.6.3.
Revision This activity removes data which is excessive and not required by R.G. l.70.
Section 10.4.6 of the FSAR rettates any pertinant data removed from Table 10.4-4.
Change Request Number SA 104 , 2 Related SER
- SSER . Section:
SER/SSER Impact N 10.4-45 3 Page 46 Remove reference to the recorders on the Condensate Polishing Control Panels.
Revision The manual control panel in each unit was replaced with an upgraded d a.1 .
Programrnable 1.ogic Controller (PLC) and field instrumentation (eg. limit switches, position indicators, transmitters) was added or upgraded to interface with the new control system. This activity enhanced overall effectiveness and reliability of the Condensate Polishing System, reduced the amount of maintenance, and minimized the operator interface required for reliable system operation.
Change Request Number S A 104 . 3 Related SER - SSER , Section:
SER/SSER Impact N 10,4-63 2 Page 64 Revises description for Unit i Steam Generator Feedwatei .' ump turbine speed control.
Revision The previous speed control for the Unit 1 SGFP was not performing satisfactorily and was upgraded to a digital control. FSAR Section 10,4.7.5, Instrumentation Requirements for the Condensate and Feedwiter Systems, is revised to describe the performance of the new digital control for Unit 1. The new digital will alarm controller for loss of signal or excessive noise in the signal and transfer automatically to manual control. The transfer to manual
'ontrol is also alarmed.
Change Request Number SA 85 , I Related SER .10.4.7 SSER Section:
SER/SSER impact N
-__ . . .. _ __ _ _._ _m _ _ ._, _ _ _. .. ____ ,~, . . _. _
Attachment to T %98015 i CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT :
AMENDMENT- 95 DETAll ED DESCRIP110N .
Page 129 Pres Page (an amended) OmW Dsscription Section:
10.4-63 -3 Revises text to indicate that an orifice in the main condensate line is used to provide design flow to the Unit I aux and gland seal condensers.
Revision
- Ac restricting orifice plate has been sized to distribute flow as stipulated in calculation CPE-ME-CA-0204-869 Rev. O. His will ensure that both the Gland Steam and the Auxiliary Gland Steam Condensers will be provided with sufficient flow. In addition flow may be controlled via manual valves on the branch lines to limit the flow through the condensers as desired. Replacing the flow control valve (1-FV 2243) with a restricting orifice plate will distribute system flow without the possibility of starving the Main Feedwater Pumps as would happen if the flow control valve were to fait closed. This change contributes to making the system less prone to transients.
Change Request Number SA - 96 . ?6 . I Related SER : 10.4 SSER : Section:
SER/SSER Impact N j 10.4-63 3 Delete Condensate Pump trip by " low feedwater pump lube oil pressure and".
Correction l The change involves deleting the interlock which trips the Condensate pumps on a low lube eil rressure on both feed water pump turbines (FWPTs)J lt does not afTect the trip of the FWPTs on loss of tube oil. If the conJensate pump is running and their is a loss of tube oil to the FWPTs and the FWPT isolation valves are open, the FWPTs would ' windmill' with no lubrication to the bear;..g.a leading to FWPT bearing failures. Ilowever, with 2100% redundant
+ AC lube oil pumps and a DC driven emergency tube oil pump, a loss of tube oil to the FWPT is unlikely During maintenance evolutions, operations practice is to secure the tube oil to the FWPTs by shutting the FWP suction and discharge isolation valves as part of the clearence. This change does not
- impact the non safety related portion of the Condensate and Feedwater System and no credit has been taken in the accident analysis.
Change Request Number - SA 25 .I Related SER : 10.4.7 SSER : 21 Section: 10.4.7 SER/SSER Impact N J
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3:
e CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 ,
DETAILED DESCRIP110N Page 130 Prefix Page Group Description Section.
(as amended) 10.4 87 1-2-IIV.2452 1 and 2 IIV.2452 2, the steam admission valves to the turbine
' driven auxiliary feedwater pump, are being swapped with respect to which valve is associated with each steam line for train considerations.
1 Revision This change is part of the corrective action prescribed to the condition reported in LER 197-001-00. The modification was required to restore the design 4 basis for operation of CPSES. These changes have been implemented for Unit
- i. 2 only at this time.
Change Request Number S A 27 . 7 Related SER : SSER : Section:
SER/SSER impact N 10.4-132 3 Page 134
- Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
- . Addition Section 10.4.16, Secondary Sampling System (SPS), was revised to indicate that the SPS will also monitor water chemistry in steam generator blowdown.
Section 10.4.16.2, System Description was revised to describe the location of
- the Local Dissolved Oxy .:n Monitors and the Secondary Corrosion Product Monitor panels. Four (4) Corrosion Product Monitors and two (2) Local Dissolved Oxygen Analyzers have been permanently installed to provide for i improved secondary side sampling cepability. Corrosion Product Monitoring and Dissolved Oxygen control is essential for secondary side chemistry which is conducive to preserving secondary side components from accelerated aging and premature replacement. Corrosion product monitor components require a
- sample temperature of around 100 degrees F. The Steam Generator lilowdown, Feedwater and IIcater Drains samples will require cooling to meet the reduced sample temperature requirements.
Change Request Number SA 96 ,0 4
Related SER : 10.4. SSER : Section:
- SER/SSER 1mpact i
t 4.
< _ -+
Attachment to TXX 98015 4
CPSES'- UPDATED FINAL SAFETY ANALYSIS REPORT '
AMENDMENT- 95 DETAILED DESCRIPTION Page 131 Prefix Page Section.
(as amendgd Goup Description i 10.4 4 3 Table This Table is being deleted and the information is summarized into Section i 10.4.6.3
- Revision See .lustification of Change for 10.4-44.
4 Change Request Number SA 104 . 4
- Related SER : SSER. Section:
SER/SSER impact N i'
10.4- 9 i Sheets 6 & 7
. Table Two additional failure modes have been identified and are being added for Unit ?
4 Revision i This change is a result of the new possible failure scenario which was reported -
I in LER l 97-00100. The modes are being added for Unit 2 only as the corrective action has been accomplished only on Unit 2 at this time.
Change Request Number SA 27 . 8-7.
Related SER : SSER : Section:
SER/SSER Impact N 10.4- 10 3 Sheet 2
' Table Revise the table to delete reference to the Service Air compressor.
Revision See Justification of Change for 9.3 2.
Change Request Number SA 83 .3 i Related SER 9.3.1 SSER : Section:
SER/SSER Impact N 10.4- 10 3 Sheet 2 Table Addition of Secondary Corrosion Products Monitors and Local Dissolved .
Analyzers.
Addition Revis- the Maximum System ileat Sink Requirements table for " Secondary Samf ' system" and " Total" to reDect additional required cooling to meet samt e nperature requirements. See Description for pp. 10.4-132 and 134 Change Request Number SA 96 .-0
~
Related SER : 10.4.- SSER - Section:
p SER/SSER Impact i
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AMENDMENT- 95 DETAILED DESCRIPTIDN Page 132 INIix Page (as amended) Group Descrintion Srction:
10.4- 18 3 Table Addition of Secondary Corrosion Product Monitors and local Dissoiwd Oxygen Analyzers.
Addition Revised Sample Point Pressure and Temperature Conditions table as follows:
Corrected the Condensate pump discharge, Polisher outlet, lleater drain pump discharge, steam generator feedsater and Main steam Design Temperature descriptions to specify actual design temperatures in lieu to maximum operatirs temperature values. Added the Steam generator blowdown Design Tempera . se and Design Pressure values. See Description for pp. 10.4 132 and 134.
Change Request Number S A 96 .O Related SER : 10.4. SSER , Section:
SER/SSER Impact 10.4-20 4 Sheet 3 Table Deletes references for installed conductivity elements.
Revision See Description of FSAR pp.10.44,7 and 9.
Change Request Number S A 106 . 2 Related SER 10.4 SSER : Section:
SER/SSER 1mpact N 10.4-20 3 Sheets I,2,3 and 4 Table Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Secondary Plant Sampling System Measured Parameters as follows.
See Description for pp. 10.4-132,134 and 135. For the Condensate pump dit .trge and Final feedwater dissolved oxygen, the Receiver and Function description was revised from " recorder with high alarms" to " recorder with high alarms; local analyzer data fed to plant computer," For Condensate pump discharge, lleater drain pump discharge and Final feedwater, reivsed the Parameter Measured and Receiver and Function description to add " Secondary Corrosion Products" and " Local sample panel monitored by Chemistry personnel," respectively. Added new Sample Source " Steam Generator Blowdown IIcat Exchanger outlet"; Parameter Measured " Secondary Corrosion products";i.nd Receiver and Fun ion " Local sample panel monitored by Chemistry personnel".
Change Request Number S A 96 .O Related SER 10.4. SSER* Section:
SER/SSER 1mpact
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 '
DETAILED DESCRIFilON Page 133 Prefix Page dim!p Descrintion Section.
(as amendnD 10.4 12 I Figure lhe change shows the steam line configuration supplying the steam driven auxiliary feedwater pump for Unit 2.
Revision This change is part of the corrective action prescribed to the condition reported in LER l>97-001-00. De modification was required to restore the design hasis for operation of CPSES. Rese changes have been implemented for Unit 2 only at this time.
Change Request Number SA 27 .2 Related SER : SSER . Section:
SEIUSSER impact N 11.2- 5 3 Add a new paragraph to the " System Description" to re0cet the current operating philosophy of the radioactive waste systems.
Revision See Justification of Change for 9.2 37.
Change Request Number SA 4 .3 Related SER SSER : Section:
SER/SSER Impact N 11.2- 26 4 P? vise description of the Liquid Waste Processing System. Filter iinera..zer System (FDS) to reflect the piping connection to the Recycle JupTanks 1 & 2 as a source ofliquid radioactive wastc.
4 Re .sion This change reflects a plant minor modification; see justification for Change Request Number SA-95 58.1 for Figure Ml.0258.
Change Request Number SA 58 .3 Related SER 11.2 SSER Section:
SER/SSER impact N
_ _ _.____m _ _ _ _ . _ . _ _ _ _ _ _ . ~ . _ - _ - ... _ . _ . _ . _ . . _ _ _ - _
Attt hrnsnt to TXX 98015
-l CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 -
DETAILED DESCRIPTION Page 134
, Prefix Page .
DescriptiOD Section, (as amended) Omgp ,
i 1.2- 2 3 Sheets 2,3,4,7,8,9 Table Revise Table 11.2 2 Expected Process Parameters for the Liquid Waste Processing System (LWPS)" to update the estimated concentration and inventory of selected radionuclides in the LWPS.
4 Revision The current analysis for estimated radionuclide concentratior.s and inyt ntories in the LWPS is based on a representative 18-month reload fuel ':ycle (two unit operation). Recent core designs (including Unit 1, Cycle 5) are characteilzed by different parameters (c.c., higher average core burnups) than the representative cycle. Herefore, new radionuclide concentrations based om a more enve!oping core design have been calculated and the corres,%nding i
change ir, estimated LWPS radionuclide concentration and inventories have r
been calculated.
Change Request Number SA 30 ,5 Related SER - SSER : Section:
' - N SER/SSER 1mpact f
11.2 8 4 Sheets 1,2,3
- - Table Revbe Table i1.2-8, " Liquid Waste Processing System Component Design Inventories" to update selected radionuclide concentrations and inventories.
Revision See thejustification for change request number SA-96-80.5 for Table 11.2-2, sheets 2,3,1,7,8,9 ll Che.nge Request Number SA 80 ,6 Related SER SSER. Section:
SER/SSER Impact N 11.2- 9 4 Sheets 1,2,3 Table Revisc Table 11.2-9," Expected Release Concentration Versus I,i' ' ting Concentrations" to update selected radionuclide concentrations.
Revision See thejustification for change request number SA-96-80.5 for Table 11.2-2, sheets 2,3,4,7,8,9.
Change Request Number SA 80 ,7 Related SER : SSER : Section:
SER/SSER Impact N
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l Attachment to TXX 98015 l
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 135 Preux Page fggyp Description Section.
(as amended) ,
11.2 10 4 Sheets 1,2 Revise Table 11.2 10,
- Design Release With 1. Percent Failed Fuel", to update Table selected radionuclide activities in reactor coolant at l'A fuel defects and ,
design release concentration.
Revision See thejustincation for change request number SA 96.80.5 for Table 11.2 2, sheets 2,3,4,7,8,9.
Change Request Number SA 80 . 8 _
Related SER : SSER : Section:
SER/SSER Impact N i
! l .3- 8 4 Page 9 In the description of the Gaseous Waste Processing System (GWPS), delete the til llydrogen alarm if the catalytic hydrogen recombiner feed hydrogen j gas concentration exceeds 6 percent by volulme, in the description of the GWPS, delete the Oxygen alarm if nxygen h the recombiner discharge exceeds 15 parts per million (ppm).
, Update A Plant design modincation to the Gaseous Waste Processing Syste m (GWPS) replaced the llendix hydrogen and oxygen gas analyr.crs with Orbisphere analyzers and deleted the indication only feed gas III hydrogen and product gas !!! oxy;;en alarms. LDCR SA.93-071 previously changed the FSAR (Amendment 90) with exception of these two items in Section 11.3.2.1.2 This activity is a document update change and does not involve any additional field work nor does this change have any adverse impact on the safe operation of the i GWPS. The alarms / control points retained in the GWPS continue the capability to meet requlatory requirements and design requirements.
Change Request Number SA 9 . I Related SER : SSER : Section:
4 SER/SSER Impact N I 1.3- 8 4 Shs .t 9 Change the III 112 product alarm set point for the catalytic hydrogen recombiner of the Gascous Waste Processing System (GWPS) from 0.25% to 2.0 % i12.
1 Change the O2 product alarm from 60 ppm to 2500 pp ,. t'or the catalytic hydrogen recombiner of the GWPS. This change also changes the set point for automatic isolation of the O2 supply valve (recombiner O2 feed) to 2500 ppm product 02.
4 Revision i
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Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS IGPORT AMENDMENT 95 DETAILED DESCRIPTION Page 136 Prenx Page Ias amendedi Grouri Description Sectlon.
The set points were set too low for normal operation of the system. Raising the set points doc s not n!Tect the safe operation of the system. 'this will reestablish the high 112 product alarm as a useful function.
Change Request Number SA 133 . I Related SER SSER Section:
SER/SSER 1mpact N I 1.4- f. 4 Page 7 Revise summary description of the CPSES Process Control Program (PCP) in Section 11.4.
Revision This change clarifies the FSAR description of the CPSES PCP to reflect the provisions of the most recent version of the CPSES PCP as approved and documened in Station procedure STA 713 (Rev 0)" Process Control Program" etTec;ive 5/5/97. The PCP approved in STA-713 (Rev 0) was a revision of version PCP (Rev. 4). Changes involved from the PCP (Rev 4) to the PCP as STA-713 (Rev 0) were reviewed and evaluated under Safey Evaluation SE-97-26 which concluded that there was no unreviewed safety question involved. This activity simply updates / clarifies the existing FSAR description to reflect the current prirnary document for the PCP, i.e., STA-713 (Rev 0).
Change Request Number SA 58 . 1 Related SER SSER. Section:
SER/SSER 1mpact N 11.5- 18 4 This change retnovcs the refer-nces made to Chapter 16 as containing the Technical Specifications.
Clarification Chapter 16 no longer contains the current Technical Specifications. Therefore, references made to FSAR Chapter 16 are removed and revised to refer directly to the Technical Spceifications.
Change Request Nt..nber SA 125 . 8 Related SER SSER Section:
SER/SSER Impact N
- - - -- . . . . ~ . - - - .- - - - . - - - -- - . - . - -
h Attachment to TXX-98013 -- .
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95
- 4 - DETAILED DESCRIPTION
.Page 137 Prefix Page .
Group Descriotion Section;,
} ~ (as amended) llA-8 4 Revise Section ll A.3, " Estimated Doses from Liquid Emuents", to update j
the estimated radiation doses from liquid emuents.
i Revision lhe :urrent 10 CFR Part 50, Appendix 1. analysis is based on a representative IP-month reload fuel cycle (two unit operation). Recent core designs "
(including Unit 1 Cycle 5 ) are characterized by different parameters (e.g.,
higher average core burnups) than the representative cycle. Therefore, new
' radionuclide concentrations based on a more enveloping core design have been calculated and the corresponding change in estimated liquid emuent radiation doses have been calculated. -
Change Request Number S A - % - 80 .l Related SER : SSER : Section:
4 SER/SSER Impact N 1IA-1 4 Sheets 1,2 Table Revisc Table 11 A 1, dxpected Concentrations of Radioactive Materials in Environmental Media from Liquid Emuents of CPSES", for selected radioisotopes and corresponding values of annual release and expected long i term concentratbn of Squaw Creek Reservoir.
Revision
- Secjustification for change request number SA-96-80.1 and page number
- - 11 A-8.
Change Request Number SA 80 .2 Related SER , SSER : Section:
SER/SSER Impact N l
-11A-2 4 Sheets 2,4 -
Table Revise Table 11 A 2, " Summary of Calculated Liquid Pathway Doses", for selected pathways and corresponding values of organ received maximum dose -
and total-body dose.
Revision
. Seejustification for change request number SA-96-80.1 and page number i 1 A-8.
Change Request Number SA 80 .3 Related SER. : SSER . Section:
SER/SSER Impact N T
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, l Attachment to TXX.980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 '
' DI! Tall.ED DESCRIPTION l
Page 138 Prc0x Page Group Description Srs:1[ gin - ,
i (ag,mngndsd)
- I1A-5 4 i
4 Table Revise Table ll A 5,' Appendix I Conformance Summary Table l'or Liquid Einuents", values for calculated dose. .
Revision See justi0 cation for change request number SA-96 80.1 and page number 1 i A 8.
Change Request Number SA 80 . 4 Related Sl?R : SSER : Section:
SI:R/SSER 1mpact N
!~ 12,3 43 4
' Delete " ESP" from hydrogen purge exhaust system preux.- Add primary plant before description of these units for clarity, Clari0 cation
' ilydrogen Purge exhaust units were downgraded to Non-Q and Non ESF
- cxhaust units. This change is consistent with references to these units in Table 9.44.
Change Request Number SA 134 . 4 j
, Related SER : SSER : Section:
SER/SSER 1mpact N 12.4. I 4 Add clarifying paragraph to Section 12.4 Clari0 cation Clarifys that FSAR Section 12.4 includes historical estimates of personnel
' occupancy in plant radiation zones and personnel radiation exposure expected annually during CPSES operations. Clarifics that this information will not bc ..
maintained in FSAR Section 12.4 but is addressed by personnel exposure records and reports routinely developed, maintained, reviewed or distributed as part of the ongoing Radiati . Protection Program.
Change Request Number SA 90 ,I-Related SER : SSER : Section:
SER/SSER Impact N 1
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Attachment to TXX-980!$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 139 Pre 04 Page Omyp Description Sssilun; (auntisudsdj 12.9 10 4 Revise Section 12.5.2.5, discussion of personnel exposure monitoring equipment, to add the practice of using personnel contamination moniton as a method of performing in-vivo radiation meaurements of personnel.
Revision The personnel contamination moniors were evalulated and determined to detect intemal radioactive isotopes at levels consistent with current CPSES monitoring pr actices, Personnel contamination monitors are used to perform passive whoia body counting which provides fast, qualitative results. Current whole body courding techniques tusing Nal detectors) will continue to be used for those individuals requiring quantitative analysis for dose monitoring and control.
Change Request Number SA 103 . I Related SER - SSER . Section:
SER/SSER Impact N 12.5- 10 4 Revisc Section 12.5.2.5 to delete reference to the use of" linger rings" for personnel monitoring assignments that require special dosimetry monitoring methods, i.e., extremity monitoring.
Revision The use of" finger rings" is being deleted as these rings have a single TLD chip which does not provide dosimetry data as reliable as the standard UD-802 four chip TLD used at CPSES for other types of routine and special dosimetry applications (multibadging). A four chip TLD placed on the wrist provides an alternative method resulting in better dose data for extremity monitoring than using a single chip TLD finger ring.
Change Request Number SA 108 . I Related SER SSER - Section:
SER/SSER Impact N 12.5-15 4 Revise Section 12.5.3.5 to delete reference to the use of" finger rings" in the description of additional dosimetry equipment that is availiable for personnel monitoring assignments.
Revision Seejustificatian for change request number SA 97108.1 for page 12.5-10.
Change Request Number SA 108 . 2 Related SER . SSER. Section:
SER/SSER Impact N
- - . . .. _.-.. - - _ - . . . _ . - - ~ . . - . _ - - - . - - _ - . _ . _ ~ . _ . - . . - _ . . . . . . - . .
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT i AMENDMENT- 95
- DETAILED DESCRIPTION Page 140 i Prefix Page Group Description Section.
.{at e cnded) '
12.5- 16 4' 2
Revise Section 12.5.3.5, discussion of personnel exposure' monitoring, to add ,
the practice of using personnel contamination monitors as a method of performing in-vivo radiation measurement of personnel.
j Revision -
Sec justification statement for change request no. SA 97103.1 for page .
j 12.5 10.
Change Request Number SA 103 2 Related SER : SSER : Section:
SER/SSER impact N 12.5- 1 4 Sheet 2 Table Revise the line item listing of personnel contaminatiordportal monitor to note I
additional use of the personnel contamination monitor as a passive whole i body counter.
Revision Secjustification statement for change request no. SA 97103.1 for page 12.5 10, Change Request Number SA 103 . 3 4
Related SER . SSER : Section:
SER/SSER impact N 13.1= 1 4 Sheets 3.5,8,9,12 Revise discussion of TU Electric's organization and change " Nuclear Production" to " Nuclear Generation".
Revision Organizational update to reflect 1997 reorganization of TU Electric's functional divisions into business units.
Change Request Number SA 129 . 6 Related SER - SSER : 27 Section: 13;17 SER/SSER impact Y TU Electric organiation update; no changes in responsibilities for CPSES.
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(as ameinled)
I 13.!- 3 4-Revise " Executive Vice President, Production" to " President, Generation 3
ilusiness Unit"; " Group Vice President, Nuclear Production" to " Senior Vice President & Principal Nuclear Ollicer" ; and " Nuclear Production" to
" Nuclear Generation".
f Revision Changed to reflect 1997 organization of'111 Electric. Position title changes reflect new organization position titles only; there_ are no responsibility changes for these senior executives with respect to CPSES.
Change Request Number SA 129 . 7 Related SER : SSER : 27 Section: 13;17 SER/SSER impact N TU Electric organization update; no changes in responsbities for CPSES.
4 13.1-4 1 Pages 9,10,12 Revised title of" Group Vice President, Nuclear Production" to " Senior Vice i President & Principal Nuclear Oflicer".
Revision Changed to reflect 1997 organization of TU Electric and organizational title
[
update for this postion. There is no change in responsibilities for this position regarding CPSES. P Change Request Number S A 129 . 8 Related SER : SSER : 27 Section: 13:17 I SER/SSER Impact Y TU Electric organization update; no changes in responsbilities ihr CPSES.
13.1- 05 4 Pages 6,7,12 Revise Section 13..l.1.2.1, " Organization - Nuclear Operations", and Section
- 13.1.2.1 " Nuclear Operations Organization" to reflect organizational change combining " Plant Support" and " Nuclear Planning" into a new organization under " Plant Support" and managed by the Plant Support Manager. This change deletes the previous organzation title of" Nuclear Planning" and
" Nuclear Planning Manager". Also, relocates Emergency Planning from organizationally reporting to Plant Support Manager to reporting directly so the Plant Manager (Vice President of Nuclear Operations).
Revision Organizational change per plant management decision for best use of current personnel resources; no responsiblities/ functions are deleted from the Nuclear Opertions organization for CPSES.
Change Request Number SA 130 . I Related SER : SSER - Section:
SER/SSER Impact N i
g e.*(- yes- ..ws ,w... .-=m.. a-3,w3 .v *-
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Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAll,ED DESCRIPTION Page 142 Prefix Page (as amended) Group Descrintion ficction.
13.1- 5 4 Pages 7,15,16,17 Revise FS AR Section 13.1 to reflect organizational reassignment of Fire Protection Program responsibilites.
Revision
'ihe responsibility for the plant fire protection program has been reassigned from the Plant Support Manager / Safety Services Manager to the Maintenance Department Manager. The Maintenace Department Manager has assigned the responsbility for the fire protection program to a specille SMART Team Manager within the Maintenance Department..
Change Request Number SA 59 ,I Related SER - SSER : Section:
SER/SSER Impact N 13.1- 7 4 Page 8 Revise Section 13.1.1.2.2 " Organization - Nuclear Engineering and Support" responsibility statements of the VP Nuclear Engineering & Support and update description erd rect reporting Engineering managers.
Revision The responsibility statement of the VP of Nuclear Engineering & Support for providing direction and guidance to direct report managers is revised to reflect the current Engineering Organization and the manager positions of System Engineering Manager, Reactor Engineering Manager Engineering Technical Support Manager, and Mod Team Manager. The description of tne Engineering manager responsibilities is updated to refleet these current organizational postions and the current TU Electric organization.
Change Request Number SA 1i .I Related SER : SSER Section:
SER/SSER Impact N
't 3.1- 15 4 Revise Sccion 13.1.2.I.3 " Maintenance Department" to replace description of the Electrical and Mechanical Maintenance and Instrumentation und Controls (l&C) Sections with description of the Scheduled Maintenance And Repair Teams (3M ART).
Revision This changes reflects the reorganization and use of Malatenance Departm nt resources. SMART Teams are multi-discipline teams designed to be trained, responsible and accountable for the systems / areas assigned. Included in each team are mechanics, electricians, and i&c techn*cians so rather than send repair and maintenance intructions to a discipline, the instructions are sent to the appropriate SMART team which uses its resources to complete the work task / assignment.
Attachment to TXX-98015 CPSFS - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 143 Prenx Page Group Descripuon Sectton.
(as amendsd)
Change Request Number S A 17 . I Related SER - SSER
- Section:
SER/SSER 1mpact N 13.1- 17 4 Delete Section 13.1.2.l.5 " Nuclear Planning", renumber Section 13.1.2.1.6
" Plant Support" to 13.1.2.1.5 and revise disussion of Plant Support to incorporate responsibility / function discussions of the pr evious Nuc! car Planning organization and reflect current responsibilitys/ functions of the new Plant Support organization including reassignment ei Emergency Planning out of Plant Support, incorporation of previous Nuclear Planning into Plant Support, and deletion of Supervisors described as reporting to the Security Manager. Also, revise existing discussion of Emergency Planning to identify as new Section 13.1.2.1.6.
Revision Seejustification for change Lquest number SA 97-130.1 for pages 13.1 5,6,7 and 12.
Change Request Number SA 130 . 2 Related SER . SSER Section:
SER/SSER 1mpact N 13.1- I 4 Sheets I & 2 Table Revise Table 13.1 1 " Minimum Qualifications of Plant Personnel in accordance with Regulatory Guide 1.8, Revision 2".
Revision Table revised to reDect the organization position titles and minimum qualificatons of managers in the current Engineering Organization, i.e.,
System Engineering Manager, Engineering Technical Support Manager, Reactor Engineering Manager, Mod Team Manager, and Core Performance Engineering Supervisor.
Change Request Number SA 11 .2 Related SER : SSER : Section:
SER/SSER Impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 144 Prefix Page Group Description Stetion:
(as amended) 13.1-1 4 Sheet 1 Table Revise Table 13.1-1," Minimum Qualifications of Plant Personnel in accordance with Regulatory Guide 1.8, Rev. 2" to reflect reorganization of the Maintenance Department by lacorporating the Scheduled Maintenance And Repair Teams (SMART). Table 13.1 1 revised to reflect a generic entry for "Maintenace Department Managers".
Update lhe Maintenance Department resources were reorganized.1he previous postions ofI&C Maintenace Manager, Mechanical Maintenance Manager and Electrical Maintenance Manager were replaced with SMART Managers ( see justification for change request number SA 97-17.1 for page 13.1 15) 1he minimum qualifications listed in Table 13.1-1 for "Maintenace Department Managers" meet the requirements for appropiate individuals listed in ANSI 18.1-1971.
Change Request Number SA 17 .3 Related SER : SSER - Section:
SER/SSER impact N 1.s.1- 2 4 Sheets 1 & 2 Table Revise Table 13.1-2," Minimum Shin Crew Composition" and table footnotes. Increased the Table 13.1-2 specified minimum number of RP Fechs on shin from I to 2 AO's from 3 to 4, and STA requirement when both units in MODE 5,5 or DEFUEl.ED from NONE to I.
Revision These changes provide a reference to 10 CFR 50.54(m)(2)(1) in footnote (a) and reflect that this r:quirement is specific to providing temporary deviation requirements for licensed operators. Temporary deviation requirements for the minimum stafling oflicensed operators are covered within the scope of the footnote (a) temporary deviation criteria stated for the minimum Operations shin crew composition. The temporary deviation criteria currently stated in CPSES Technical Specifica: ion 6.2.2 for the onshin Radiation Protection and Chemistry Technicans is restated (i.e., c.dded) under footnote (b). Other changes / additions provide consistency to n.inimum onshift stafling requirements or criteria specified in TS 6.2.2 and the CPSES Emergency Plan.
Table 1.1. Footnote (c) now references FSAR users to additional minimum on-shin stafling requirements contained in the CPSES Emergency Plan.
Change Request Number S A 104 . 1 Related SER - SSER - Section:
SER/SSER impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 145 Prc0x Page (as amendedi OmuD Descrintion Section.
13.1- l 4 Figure Revise Figure 13.1 1 to reflect TU Eiectric's current organization.
Revision Organizational update to reflect 1997 reorganization of TU Electric's functional divisions into 1 usiness unitc.
Change Request Number SA - 97 = 129 . 9 Related SER SSER - 27 Section: 13;17 SER/SSER Impact Y TU Electric organization update; no cnanges in responsibilities for CPSES.
13.1- 2 4 Figure Revisc Ogure block of" Nuclear Planning Manager" to " Emergency Planning Manager".
Revision Change reflects the current managers reporting directly to the Plant Manager (Vice President of Nuclear Operations). See justincation for change request number S A-97 130.1 for pages 13.15,6,7 and 12.
Change Request Number SA 130. 3 Related SER : SSER Section:
SER/SSER impact N 13.1 2 4 Figure Revise Figure 13.1-2 to change " Executive Vice President, Production" to
" President, Generation Business Unit"; " Group Vice President, Nuclear Production" to " Senior Vice President & Principal Nuclear Ofucer"; " Plant Manger'" to "Vice President of Nuclear Operations **; and " Nuclear Production Group" to " Nuclear Generation Group" Revision Position and organizational title changes to rencet 1997 organization of TU Electric.
Change Request Number S A 129 , 10 Related SER . SSER ' 27 Section: 13;17 SER/SSER Impact Y TU Electric organization update; no changes in responsibilites for CPSES.
b
, . . . . .-_ . - - . . , - - - - - - . - . . - . . . - - - - - - . . - . . . - . ~ . . . ~ . . . . - . -
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7 Attachment'to TXX 98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT ,
AMENDMENT 95 DETAILED DESCRIPTION 4
Page 146 Prefix Page .
Group Descriotion - Section:
, ias amended) ,
13,1- 2 . 4 Revise Figure 13.1-2 " Nuclear Production Group" l Figure
__ Revision _
i Figure revised to reflect the currentTU Electric and CPSES Engineering '
- Organization and remove Note I from selected organization positions now located at the CPSES site instead of the corporate offices. ,
Change Request Number SA 1I .3 >
Related SER : SSER
- Section:
c
' SER/SSER impact N 13.1- 3 4
- Figure Revise Figure 13.1-3 " Nuclear Operations" to reficct the reorganization of the ,
Maintenance Department by incorporating the Scheduled Maintenance And .
Repair Teams (SMART).
Revision Sec justification for change request numbers SA 97-17.1 and SA.9717.3 for page 13.1 15 and Table 13.1 1, respectively, Change Request Number SA 17 .4 i Related SER : SSER : Section:
SER/SSER 1mpact N 13.1- 3 4
- Figure Revise Figure to reflect reassignment of the responsibility for the plant's Fire Protection Program.
Revision Secjustification for change request number SA 97-59.1 for pages 13.1-5,7,15, and 17.
J Change Request Number SA 59 .2 Related SER : SSER - Section:
SER/SSER Impact N 13.1-3 4
~
Figure Revise " Plant Manager *" to "Vice President of Nuclear Operations *".
Revision Position title change to reflect 1997 organization of TU Electric ard new organizational posrion title assignment.
Change Request Number SA 129 . 19 -
Related SER : SSER : 27 Section: 13;l7:
' SER/SSER impact Y TU Electric organizational update; no changer in responsibilities for CPSES, 4 ,.
1
-- .+ .,
. - . - . - _ . - . - - . - - . . . _ ~ _ . . ..- - _ .-. - - .-
l Attachment to TXX-980l$
l CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 ;
-i
- DETAILED DESCRIPTION Page 147 Prefix Page (as amended) Group Description Section.
13.1-3 4 l'igure Revise figure to reficct Emergency Planning Manager reporting to the Plant Manager instead of Plant Support Manager, delete Nuclear Planning Manager, relocate Outage Mgr. and Work Control Mgr, (revised as CORPS Mgr.) to show reporting to the Plant Support Manager, and delete Supervisor block -
under Security Manager.
Revision i Change reflects the current organization for Nuclear Operations under the Plant Manager (Vice President of Nuclear Operations) ead the Plant Support Manager. Also, see. justification for change request number SA-97130.1 for i pages 13.15,6,7and 12.
Change Request Number S A 130 , 4 Related SER : SSER : Section:
SER/SSER impact N 13.1 A- 01 4 Revise " Group Vice President, Nuclear Production" to " Senior Vice President
- & Principal Nuclear Oflicer"; " Plant Manger" to "Vice President of Nuclear Operations"; and position not assigned statement from "Vice President of 1 Nuclear Operations after 10/31/95" to " Plant Manger . aller 12/31/97",
Revision Position title changes to reficct 1997 organization of TU Electric and new organizational position title assignments.
Change Request Number SA 129 , II Related SER : SSER , 27 Secrian: 13;17
^
SER/SSER impact Y TU Electric organization update; no changes in responsbilities for CPSES.
13.1 A- 1 4 Pages 9,13,17,19,23 Revise resumes of key TU Electric CPSES personnel in Section 13.1 A. Add resume for Rafael Flores, System Engineering Manager; delete resume of James W. Mu!Tett, Station Engineering Manager; revise resume and title for Mickey R. Killgore, Reactor Engineering Manager; add resume for Duerksen J. Reimer, Engineering Technical Support Manager ( Acting); add resume of Dale L. Walling, Mod Team Manager; update resume of C. Lance Terry, Group Vke President, Nuclear Production.
Revision
. .The resumes of key personnel are revised to reficct new personnel assignments j in the current 'll! Electric and CPSES Engineering Organizations.
, Change Request Number SA - 97 '- 11 ,4 4 ' Related SER : - SSER - Section:
SER/SSER 1mpact N
%- p r +-a
Attachment to TXX 98015 f
r
' CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT j J
AMENDMENT. 95 !
DETAILED DESCRIPTION -
Page 148 Prefix Page (an.amngisd) Group Deserintion Sectlon:
- r I!.i A- 1 4 Pages 2.3,13,14 Revise resume list of key TU Electric personnel for CPSES to change title of i
Robert D. Ilird, Jr. from Nuclear Planning Manager to Plant Support Manager, delete resume of Dobby T. Lancaster as Plant Support Manager, and I
revise resume of Robert D. Ilird.
Revision Changes re' lect organizational position and pe sonnel changes within the CPSES Nucelar Operations organization. Sec justi0 cation for change request number SA-97130.1 for pages 13.15,6,7 and 12. ,
Change Request Number SA 130, 5
- Section
Related SER : SSER :
! SER/SSER 1mpact N 1
' 13.1 A 04 4 Page 5 Revise resume of M. R. illevins to reflect position title change from " Plant i.
Manager" to "Vice President of Nuclear Operations".
Revision 4 New postion title assignment within TU Electric organization; no changes in responsibilities for CPSES.
Change Request Number SA 129. 20 Related SER : SSER : Section:
i-SER/SSER impact N t
- 13. l A- 10 4 and Page 11 i Change resume for Shin Operations Manager from David Kross to William Guldemond Revision Change of personnel for the organizational postion of Shia Operations Manager. This is a routine administrative activity related to organizational -
1 maintenace and upadate due to the CPSES Manager Rotation Program.
William Guldemond has a SRO license and meets all of the requirements for thr. subject position Change Request Number SA 21 . I Related SER : SSER : Section:
SER/SSER impact N d
- - - -w. -- ~- m
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 149 Prefix Page (as amendsdj Group Descrintion Section.
13.1 A- 19 4 Page 20 Revise resume of C.1,. Terry to change title of" Group Vice President, Nuclear Production" to " Senior Vice President & Principal Nuclear Officer" Revision New position title assignment within TU Electric organizaticn; no changes in responsibilities for CPSES.
Change Request Number S A 129 . 2 i Related SER - SSER Section:
SER/SSER Impact N 13.2- 3 4 Revise Section 13.2.1.2 (8) to delete "QA" from the list of personnel to receive training on the emergency diesel generator (EDG)
Revision The requirement for QA personnel training on the EDO was part of the prescriptive and outdated post-TMI recommendations. There are no current requrements with respect to the provisions of 10 CFR Part $5,10 CFR 50.120 or Regulatory Guide 1.8 (Rev 2) which would require QA personnel to specfically have . raining on EDGs. Adequate qualifications / training of CPSES QA personnel are required per Appendix 13 to 10 CFR Part 50 and this is addressed for CPSES by the commitment to FSAR SecQn I A(13) and US Regulatory Guide 1.58 (Rev I) which conditionally endorses ANSI N45.2.6-1978.
Change Pequest Number S A 102 , !
Related SER : SSER Section:
SER/SSER impact N I 3.3- 2 4 Page 3 Revise FSAR Section 13.313 "CPSES 1-ir Protection Program".
Revision
> Sec jutification for change request number SA-97-59.1 for pages 13.1 5,7,15 and 17.
Change Request Number SA 59 .4 Rela' J SER ' SSER Section:
SE' /SSER Impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAll.ED DESCRIPTION Page 150 Prefix Page (as amendtdj Group Descrintion StEli2tn 13 ?-2 4 Revise " Group Vice President, Nuclear Production" to
- Senior Vice President & Principal Nuclear Officer".
Revision New organizational position title assignment within TU Electric; no change in responsibi!ities for CPSES.
Change Request Number SA 129 , 12 Related SER : SSER - Section:
SEIVSSER Impact N 1
13.3- 6 4 Add further clarification to Fire !!rigade Staffing Requirements.
Clarification Clarification is added to the existing FS AR Section 13.313.2 requirements of l
Fire Brigade Staffing Requirements of 5 personnel in each shift. The 5 personnel should not include the Shift Supervisor and Shill crew required for Safe Shutdown of the Plant. This is consistent witrh the existing Plant Technical Specifications Section 6.2.2d.
Change Request Number SA 96 . I Related SER ,13,1.2.1 SSER : Sr tion:
SEIUSSER Impact N I 3.5- 2 4 Revise FS AR 13.5.1.2, " Preparation of Procedures and instructions" to restate the approval authority for Security 1 lan and Emergency Plan implementing procedrues.
Revision The specific management approval authority for the Emergency Plan and Security Plan implementing procedures is more appropiately specified in the CPSES Emergency Plan and Security Plans, respectively. This approval authority is already specified/ identified in the subiect plans and it is therefore redundant to also identify this authority in the FSAR. The revised FSAR states Dat approval authority for the subject implementing procedures is "in accordance with provisions in the CPSES Security Plans and Emergency Plan Change Request Number SA 81 . I Related SER SSER - Section:
SER/SSER Impact N
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 151 Prefix Page (as amended) Group Descrirition St.ction:
13.5- 10 4 Revise FSAR Section 13.5.2.2.1, " Maintenance and Modification Procedures", to restate organizational responsibilities for the maintenance program for safety-related instruments and controls and for providing -
assistance in performance testing of safety-related mechanical and electrical equipment.
Revision FSAR Section revised to reflect current organization and organization assigned responsibilities.
Change Request Number SA 17 .2 Related SER . SSER : Section:
SER/SSER 1mpact N 13.5- 10 4 Revise Section 13.5.2.2.1 "Maintenace and Modification Procedures" to che.nge " Maintenance Engineering Manager" to " System Engineering Manager" for the responsibility of who assists in the performance testing of safety-related mechamcal and electrical equipment to assure adequate levels of performance.
Revision This change updates the discussien of the subject responsibility in accordance with the current Engineering Organization.
Change Request Number SA 1I .5 Related SER - SSER : Section:
SER/SSER Impact N I3.5- 15 4 Revise Section 13.5.2.2.10 " Test Pmcedures" to change the statement of responsibility for design modification acceptance, station performance, initial startup tests, and those surveillance tests assigi.ed to the " Maintenance Engineering Manager" and " Maintenance Engineering Department" to the
" System Engineering Manager" and " System Engineering Department",
respectively.
Revision This change updates the discussion of the subject responsibility in accordance with the current Engineering Organization.
Change Reqcest Number SA l1 .7 Related SER : SSER. Section:
SER/SSER impact N
Attoclunent to TXX 980lf I
Cl'S!!S UPDATIID FINAL SAFliTY ANALYSIS IWl' ORT AMI:NDMt:NT. 95 DI: Tall.l:D DI: SCRIP' LION Page 152 Prefix Page
[nanttukd] GmuI Docrartion Strilen.
13.5- l $ 4 P esise Section 13.5.2.2.R "l'uct llandling Procedures" to change the responsibility for developing fuel handling procedures from the "I'ogineering Analysir Manager" to the "Peactor Engineering Manager" and ' Operations Manager".
Revision 1h;s change updates the discussion of the subicct ter,ponsihility in accordance with the current CPSI;S Engineering Organisation and Operations organization responsibilities.
Change Request Number SA -97 11 .6
"; lated SI:R SSI:R - Section:
SI:lUSSI:R tmpact N 15 0-21 2 Clarify total residual heat.
ClariEcation 1hc paragraph is reworded to more precisely obte the assumption concerning the calculation of the tcsidual decay heat.1his discussion is consistent with the NRC approved topical report RXI; 91001 A and the descAlptions of the ofrected analyses presented elsewhere in Chapter l$.
Change Itequest Number S A 100 . 20 Related SI:R . SSER : Section:
SI:R/SSER impact N 15.0- l 4 lable Iteplace "NSS" with NSSS" I:ditorial 1 ditorial, one "S" was inadvertently deleted ir. the text of the tabic.
Change Request Number S A 100 . 21 Related SER SSI:R : Section:
SI:lVSSER impact N
Attaciunent to TXX.980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS RIIPORT AMENDMENT. 95 DETA11.ED DESCRIPI10N Page 153 l'rch Page (as amended) Group [ksnip110D $rf42n:
15.0- 4 2 Sheti Table lhe overtemperature N 16 trip function in 't able 15.0-4, " Trip Points and Time Delays to 1 rip Assumed in Accident Analyses," is clarified by additkin
- of note.
Revision
'Ibe Tahle indicates a time delay of 2 sec<mus for the overtemperature N.16 trip function.
An asterisk and footnote are added to clarify that the total time delay, including RTD response time is 8 seconds.1his total time delay has been evaluated for RTD resp (mse times of $ and 6 seconds; u remainder of the total response time for each cr + is an allowance for ciectronic sesp' ac time.
(Note the conesponding time delay for Unit 2 is revised by Change 11equest Number SA.97 006.)
See related change for FS AR Figure 7.2.1,
- Functional Diagram," Sheet $.
(Change Request Number SA 97 005.1)
Change Requot Number SA -97 $ .2 Related SER : 7
- I SSER : 22 Section: 7.2.1 SER/SSER impact N
. 15.1 3 4 Move information under results irdo method of analysis.
Clar:0 cation This is a consistent fonnat used throughout Chapter 15.
I Change Request Number SA 100. 22
. Related SER : SSER : Section:
- SER/SSIIR Impact N i
l$.b 4 4 Add References to Appendices 4 A and 411.
Clari0 cation Provides ecference to the latest mformation regarding the current cycle.
g Change Request Number S A 96
- I t) . 23 Related SER , SSER ; Section:
SER/SSER Impact N l
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Attachment to TXX 98015 l
CPS 11S - UPDATI!D FINAL SAFIITY ANALYSIS RIIPORT AMI:NDMI:NT. 95 DI:TAILI:D Dl:SCRIPTION Page 154 Prefis Page GrmR ThEtipikul Ecttion.
(as amended) 15.1- 13 2 1.evise the steam flow conditiors assumed to exist at the time of a secondary system release.
Revision Relief or safety valve events are bounded in neverity by the steamline break event presented in Sectiuon 15.1.5 because the return to power aspects of the rero power steam line break.1hc presented analysis is assumed to be initiated ,
from full power conditions in order to demonstrate that the DNil limit is not execeded near the time of reactor trip.
Also, the relief capacity of a steam dump valve is now greater than an ARV; therefore, the " case studied" is revised to reflect this more severe event.
Change Request Number SA 100. 24 Related SI:R : SSI R : oon:
SI:lVSSI:R impact N 15.1-14 4 Clarify wording in the conclusions for the inadvertent opening of a steam generator relief or safety valve.
Clarification Additional detail is added to clarify the conclusion of the inadvertent opening of a steam Fencrutor relief or safety valve.
Change Request Number SA - 96 100 , 25 Related SIIR - SSER Section:
SI:lVSSliR impact N 15.1-19 2 Page 25 Text is revised to remove the obsolete reference to the 1,OITRAN computer code.
Correction The 1U Electric methods are described in appendix 4 A AND 41), which do not include the LOITRAN computer code. Reference [1] no longer applies.
Chans Request Number S A 100 . 26 Related SER : SSER : Section:
SI:lVSSER impact N
Attachment to TXX.98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMI:NT. 95 DisTA1EED DESCRil'IlON Page 155 Prefis Page Group DOEtiplica SEElkE 4
(ni.amtudril.)
15.l-24 3 Correction of x/Q and resulting radiation doses.
Omo tion A more realistic x/Q has been applied as the design basis for calculation of of1 site thyroid and whole body radiation doses at the 1.;xclusion Area lloundary
(! All). 'Ihe doses, x/Q value, and EAll distance have been corrected for ti Main Steam 1.ine lireak accident.
Change Request Number SA 54 .O Related SER : SSI:It : Section:
SI:R/SSER Impact N I5.2 I8 4 Replace word " incentives" with *uncertsinties."
Editorial Typographical error incorrect usage of the word.
Change Reg aest Number S A 10'i . ?7 ,
Related SI:R . SSER . Section.
S!!R/SSIIR Impact N 15.2-20 2 Sentence was reworded to tellect the CPSES analysis and not the Westinghouse analysis.
Correction 1he steam generator parameters used in the analyses are conservative for the Unit for which the analysis is performed, but will not necessarily be bounding for both units.
Change Request Number S A 100 , 2R Related SER : SSER : Section:
SER/SSI:R impact N 15.2 26 i Page 27 Clarification is added as to the manual t,perator actions which may be necessary based on the scenario which is present.
Revision
- lhis change is a result of the new possible failure scenario which was reported in I.ER l-97-001-00.1hese opvator actions may be necessary at some time following the reactor trip.
Change Request Number SA 27 .9 Related SER : SSER : Section:
SER/SSdR 1mpact N
l Attachment to TXX 98015 l
CPS 11S - UPDATliD FINAL SAFliTY ANALYSIS RIIPORT AMI:NDMfiNT - 95 DI:TAIEl:D DESCRIPl10N Page 156 Prefix Pope SEvtion; LuiAmtDdtd.) iltullP DEhttiPik.0 I5.3 3 4 Itemove duplicative infocmation regarding initial conditions.
Editorial As stated in subsection 15.3.1.2, the plant initial conditions are previously discussed in subsection 15.0.3. This informatrion is repetative and therefore unnecessary, Change Request Number S A 100 . 29 Related SI'R : SSI;R : Section:
SI'.R/SSER impact N l $.3- 5 4 Page 6 change reference "4" to "2".
Editorial 1he correct references for analyses to grid frequency disturbances is reference 2.
Change Request Number S A 100 . 30 Related SI:R
- SSER : Section:
SER/SSI:R Impact N 15.4-26 4 Typographical error.
Editorial liigh charging liow rate alarm plus 5% is 157.5gpm.
Change Request Number SA 100 . 31 Related SER : SSER : Section:
SER/SSI:R impact N 15.4-26 4 Pages 27 & 30 Remove redundant infomiation regarding the unit and cycle specific shutdown margins.
Clarification Unit and cycle tpecific shutdown margins are relocated to Appendices 4A and 4H.
Change Request Number S A 100 . 32 Related SER , SSER' Section:
SER/SSL'R impact N
Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMI:NDMENT. 95 i DETAILED DESCRIPTION Page 157 i Prefix Page Omug Description Sitetion: l (as amended) 15.4- 27 2 Replace the maximum design flow rate (167) with the maximum assumed dilution flow rate (based on the charging high flow alann setpoint plus 5% for uncertainties) 157.5.
Correction in the accident analyses, the assumed dilution flow for all modes is 157.5 gpm, based on the charging high flow niann setpoint, plus uncertainties, the value of 167 gpm represents a description of the system design.
Change Request Number S A 100 . 34 Related SER : SSER : Section:
SER/SSLR impact N I5.6-20 4 Change " reload" to *reflood".
Editorial As further described in subsection 15.6.5.2. the third phase of the event following a large break I,0CA is reflood Change Request Number SA 100 . 33 Related SER : SSER : Section:
SI:R/SSER Impact N 15,6-22 4 Clarification The TU Elcetric methodologies are now used for both Unit I and Unit 2.
Changes clarify that alternating hot and cold leg irtlection occurs approximately every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Change Request Number SA 142 . O Related SER : SSER : Section:
SER/SSER Impact N
' Pages 24,27,28 A 42 15.6-22 2 Clarification of the TU Electric small break LOCA methodology to make the FSAR description consistent with the topical report.
Update his change clarifies that the Unit I small break LOCA analysis is nuw performed with NRC-appre .ed TU Electric methodology.
Change Request Number SA 28 . I Related SER : SSER : Section:
SER/SSER Impact N
l l
Attachment to TXX.98nl5 l
l CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENI> MENT. 95 DETAILED DESCRIPilON Page 158 Prefix Page Group Dsicription MEllen; (as amended) 15.6- 24 2 Remove reference to NOTRUMP analysis.
Revision TU Electric methodology is now used for small break LOCA analysis for Unit 2.
Change Request Number SA 142 . O Related SI:R
- SSER : Section:
SER/SSER impact N 15.6- 25 4 Remove reference 9.
Editorial Reference 9 was deleted in a previous amendment.
Change Request Number SA 100 . 35 R6 lated SER : SSER . Section:
SER/SSER impact N 15.6- 25 2 provide additional infonnation regarding location of small break 1.OCA analysis input parameters.
Clari0 cation Additional information provided for clarification.
Change Request Number SA 28 .2 Related SER SSER : Section:
SER/SSER 1mpact N 15.6-26 2 also page 27 Revision Delete reference to Westinghuse small break 1.OCA analysis for Unit 2.
Change Request Number SA 142 . O Related SER : SSER : Section:
SER/SSER 1mpact N
Attaciunent to TXX 9kol5 CPSIIS - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DEI All.ED DESCRIPilON Page 159 Prefix page Omtp 1)kElirLkm Scclion; (as amendedi
, 15.6-40 4 Page 42 l
Rernove references 1,2,24,and 27.
l Editorial
'these references are not mentioned in the preceding text,
' Change Request Number SA 100 . 36 Related SER : SSI:R : Section:
SEIUSSER 1mpact N 15.6 40 2 Replace the words "the small break IDCA" with "a typical small break LOCA".
Clarification 1his clarification is done to avoid linking what should be cycle-specific and/or method-specific small break EOCA analyses conclusions regarding radiation doses to cycle-independent bounding acceptance criteria, Change Request Number SA 28 .3 If elated SER : SSER , Section:
SER/SSER impact N 15.6-41 4 Page 42 Clarification References to Westinghouse letters were inappropriately added in a previous l'S AR amendment. These letters are included in appropriate calcualtions or other programs, but are not direct references for l'SAR discussions.
Change Request Number SA 142. O Related SER : SSER Section:
SEIUSSER Impact N 15.6-42 2 Revision Delete references pertaining to the Westinghouse methodology for small break LOCA analysis, Change Request Number SA 142 . O Related SER : SSER Section:
SER/SSER 1mpact N e,... r n,- v. . -.w. ..e <
Attachment to TXX.98015 CPSES - UFDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Page 160 P: Os l' age Descriotion Section.
(as amended) Onns ,
I 5.6- 3 e
'I able Clarify preaccident iodine Spike concentrations table.
Clarification input parameters identitled in I'S AR Table 15.6 5 include ll:ensed thermal power for operating CPSES. 'the note on Table 15.6-3 was revised to indicate that the preaccident iodine spike concentrations certespond to Rated Thermal Power (Licensed thermal power level).
Change Request Number SA 114 . 1 Related SER SSER : Section:
SEIUSSER impact N 15.6 5 2 Table Update LOCA analysis input parameters.
Update LOCA analysis input parameters require updating to reflect the use of NRC approved methodologies.
Change Request Number S A 100 . 37 Related SER : SSER : Section:
SEIUSSER Impact N I 5.6- 5 2 Table Clarification of the TU Electric small break LOCA methoJology to make the I'S AR description consistent with the topical seport.
Update This change clarifies that the Unit I small break LOCA analysis is now performed with NRC. approved TU Electric methodology.
Change Request Number SA 28 4 Related SER : SSER Section:
SEIUSSER Impact N 15.6-5 2 l'igure Delete figure 15.6 5.
Clarification
'this figure applies to the Westinghouse large litcak LOCA methodology which has been superceded with the NRC-approved TU Electric methodology.
Chnge Request Number SA 28 .5 Related SER - SSER* Section:
Se.IUSSER Impact N
P Attachment to TXX-980l$ l i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 9$ [
DETAILED DESCRIPTION {
i Page 161 Prefiz Page 4 (as amende,dl Omig! Descriptiorg $setion: ,
l
]_
l $.6- 6 2 t
l'igure Delete 11gute l$.6-6.
Clarification !
' 'this figure applies to the Westinghouse large lireak LOCA methodology l 1
which has been superceded with the NRC spproved 11J Electric methodology.
Change Request Number SA 28 . 0 Related SI R t $$1:R : Section:
l N SEIUSSER impact
' 2 l $.6- 6 l'igure
- l Revision Delete figure pertaining to Westingimuse small break LOCA analysis. ;
Change Request Number SA 142 . O Related SER : SSER Section:
! SER/SSI:R impact N k
" 16.2- l 3 Page 2 Update l'S AR Chapter 16.0, " Technical Specifications". Also updates Table
' of Contents, c
Update I'SAR Chapter 16.0, " Technical Specifications" was written and submitted to NRC before issuance of operating licenses for CPSES Units 1 and 2. The I write.up at present discusses the prepartion and submittal of Technical
!- Specifications to NRC. Chapter 16.0 is updated to reflect the maintenance of i Technical Specifications after issuance of operating licenses for CPSES Units I and 2.
I Change Request Number SA 30 .O Related SER : 16.0 SSER : 27 Section: 16.0 f SER/SSER Impact N 17,2- l 4 Pages 2 thru 9,11,14,17,19,20,22 3
- . Revise " Group Vice President Nuclear Production" to " Senior Vice President
& Principal Nuclear Ollicet" and " Nuclear Production" to " Nuclear
. Ocneration".
Revision Changed to reflect 1997 organization of TU Electric and new position title within TU Electric organization.
Change Request Number SA 129 . 14 Related SER : SSER : 27 Section: 13;17 i
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AMI:NDMENT- 95 DETAILI;D DESCRIPTION Page 162 ih h Fuge Cum Description $151kg (asEnended)
SER/SSER Impact Y TU Electric organization update; no changes in respansbilities for CPSES.
17.2- 2 4 Revise Section 17.2.1.1.2
- Plant Manager" list of specific duties and responsibilities to dek te providing technical and administrative direction to the Nuclear Plarming Manager and add same for the Emergency Planning Manager.
Revision Seejustification for change request number SA 97130.1 for pages 13.1.$,6,7 and 12.
Change Request Number SA 130. 6 Related SER : SSER : Section:
SEIUSSER 1mpact N 17.2-4 4 Page 11 Remove reference to Technical Specification for audit function of ORC.
Update Technical Specification has been revised to remove reference to ORC functions.
Change Request Number S A - 9' - 15 , i Related SER : SSER - .section:
SEIUSSER impact N I 7.2- $ I Pages 5,10,14,17.23,24,28,30,45,47 Add titles and editorial corrections Editorial Corrected the inadevertly deleted titles and editorial items from FSAR nmendment 94 Change Request Number S A 15 . 2 Related SER : SSER. Section:
SER/SSER impact N l
- . - . - . - - . ~ . _ - . . ~ . _ _ _ _ . - _ - - -
Attachment to TXX-9801$ l l
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CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT s AMENDMENT 95 i l DETAILED DESCRIPTION j i
Page 163 Preux Page _
Description Section: j (as amended) Groun '
l 17.2 14 j
Revise the requirement for preparing and forwarding ORC meeting minutes l from 14 days to 30 days.
Change the requirement from 14 days following each meeting to 30 days i following each meeting. ;
j Change Reque-t Number SA - % 132 . O !
,' SSER : Section: i Related SER :
SER/SSER impact N i ,
17.2-22 4 Revitic Section 17.2.3 " Design Control" to change " Station Engineering personnel" to " Nuclear Engineering and Support personnel" and revise the discussion of who may change the design for those design modification requests approved by the Plant Manager.
I Revision
- ' *lhis change clarilles the discussion of who may actually change the design control documents in accordance with the current Engineering Organization and tellects the current Engineering organizational title, i.e.." Nuclear 4
Engineering and Support".
. Change Request Number SA 11 .8 Related SER SSER : Section:
{ SER/SSER 1mpact N l'
17.2-33 . 4 Pages 37 & 48 Redse " Nuclear Prmiuction" to Nuclear Generation". ,
Revision
! Changed to tellect 1997 organization of ni Electric. ,
j Change Request Number SA 129 . 15 Related SER : SSER: 27 Section: 13;17 SER/SSER impact Y TU Electric organization update; no changes in responsibilities for CPSES.
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CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAlli:D DESCRIPTION Page 164 Prefix Page Group Descrintion Section.
{as arnended) 17.2 33 4 Clarify the reporting structure for the inspection program by indicating that the Maintenance Overview inspectors report to the Maintenance Overview Manager and the receipt / source inspectors report to the Plant Support Overview Manager.
Clarification Clarify the reporting structure for the inspection program Change llequest Number SA 34 .O Related SER : SSER : Section:
SER/SSElt impact N 17.2 3M 4 Revise Section 17.2.12 " Control of Measuring and Test Equipment" to change discussion wording from " responsible discipline Engineering Manager" to
" responsible Engineering group".
Clarification Change provides clarification with respect to the current Engineering Organization.
Change Request Nuraber SA 1I 9 Itclated SER SSER - Section:
SER/SSER Impact N 17.2 43 4 Remove references to specific record centers.
Clarification Reference to specific record storage locations exceeds the detail specified in the SRP. In order to maintain a clearer, simpler l'SAR, the excessive detail is being removed..
Change Request Number SA 45 .O Related SER : SSER Section:
SER/SSER 1mpact N
i Attachment to TXX-98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 165 Prefix Page (as amended) 01g93 Descrintion Section.
17.2-44 Allow records to be stored on optical disk as specified in GL 8818 Add
- Quality Assurance Records may be stered on op;ical disk. For those records, the Optical Dis! Imagina System used will meet the requirements of NRC Generic letter 88-18.*
SER/SSER Impact N 17.2-45 4 Clarify records retention section Ed".orial Add " Technical Specification" before Table 5.71 Change Request Number S A 10! . O Related SER : SSER : Section:
SEIUSSER Impact N 17.2- l 4 Figure Revise Table 17.2 1 " Nuclear Production Group" Revision Figure revised to tellect the current TU Electric and CPSES Engineering Organiration and remove Note I from selected organization positions now kicated at the CPSES site instead of the corporate offices.
Change Request Number SA 11 . 10 Related SER : SSER : Section:
SEIUSSER 1mpact N 17.2-1 4 Figure Revise Figure 17.2 1 to change " Executive Vice President, Production" to
" President, Generation llusiness Unit"; " Group Vice President. Nuclear ProI;ction" to " Senior Vice President & Principal Nuclear Officer";" Plant Manager *" to "Vice President of Nuclear Operations *"; and " Nuclear Production Group" to " Nuclear Generation Group".
Revision Position and oranizational title changes to reflect 1997 organization of TU Electric.
Change Request Number SA 129. 16 Related SER , SSER . 27 Section: 13:17 SEIUSSER Impact Y
_ = _ .__ - . . -. - _ .-. _ _ _ _ - -
1 Attachment to TXX 980l$
CPSES IJPDATED FINAL SAFETY ANALYSIS ItEPORT AMEhDMENT 95 DETAILI:D DESCRIPTION Page 166 ,
Prefix Page (as arnended) Qtwp Description SIction:
'f1) I:lectric organiiation update; no changes in responsibilities for CPSES.
17.2.I 4
- l'igure Reviw figure block of" Nuclear Planning Manager" to
- Emergency Planning Manager".
Revision Change reflects the current managers reporting directly to the Plant Manager (Vice President of Nuclear Operations). Secjustification for change request number SA 97130.1 for pages 13.1 $,6,7, and 12.
Change Request Number SA 130. 7 Related SER
- SSER : Section:
SER/SSER Impact N I 7.2- 2 4 l'igure Revise l'igure 17.2 2 " Nuclear Operations" to reflect the reorgantiation of the Maintenance Department by incorporating the Scheduled Maintenance And Repair Teams (SMART).
Revision Secjustification for change request numbers SA 9717.1 and SA 9717.3 for page 13.1 15 and Table 13.1 1, respectively.
Change Request Number SA 17 .5 Related SER : SSER : Section:
SER/SSI P Impact N 17.2-2 4 l'igure Revise " Plant Manger *" to "Vice President of Nuclear Operations *"
Revision Seejustification for change request number SA 97129.19 for Figure 13.13.
Change Request Number SA 129. 22 Related SER : SSER : 27 Section: 13;17 Sl;lVSSER Impact Y TU Electric organizational update; no changes in responsibilities for CPSES.
l
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- i h
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT i I AMENDMENT. 95 DETAILED DESCRIPTION l
t Page 167 Preils Page (as amendsdj Group Description Section:
172 2 4 Revise figure to reficct Emergency Planning Manager reporting to the Plant I l'igure Manager instead of the Plant Support Manager, delete the Nuclear Planning l
}
Manager, rek>cate Outage Mgr. and Work Control Mgr. (revised as CORPS t
Mgr.) to show reporting to the Plant Support Manager, and delete Supervisor block under Security Manager. ;
i- Revision 2 Change reflects the current organization for Nuclear Operations under the i
i Plant Manager (Vice President of Nuclear Operations) and the Plant Support Manager. Secjustification for change request number SA 97130.1 for pages 13.15,6,7 and 12.
} Change Request Number SA + 97 - 130 -. 8 I Related SER : SSER : Section:
SER/SSER Impact N
, i 17.2-2 4 Figure Revise Figure to reflect reassignment of the responsibility for the plant's Fire ,
Protection Program, p i
Revision Secjustification for change acquest number SA 97 59.1 for pages 13.1 5,7,15, l and 17.
! Change Request Number SA 59 . 3
- Related SER : SSER : Section:
4 SEl%3ER impact N 17A.2 4 Revise " Group Vice President, Nuclear Production" to " Senior Vice President A Principal Nuclear 01ficer". ..
Revision Changed to reflect 1997 organization of RJ Electric.
Change Request Number S A 129 , 17 j Related SER . SSER : 27 Section: 13;17 SER/SSER 1mpact Y TU Electric organization update; no changes in responsibilities for CPSES.
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CPSCL - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 l DETAILED DESCRIPTION l
' 1 page 168 j
Prefiz Page - ~
proun Description Srctiort:
l (as amendedl
' .j 17A 6 4 i
Add chlorination systems to list of seismic Category 11 systems as shown on flow diagram figure 9.21 i Addition Class $ piping shown on diagram applies. 'this is a trivist clarification for the f user of Section 3,2 and 17A to find the applicable systems and drawings for programatic scismic Category ll requirements discussed in the FSAR.
Change Request Number S A - 97 113 . O N Related SER - SSER : Section:
4 SER/SSER lmpact N i
17A.1 4 Shect 48 ;
Table Added Note $1 to Compressed Air Systems.
Clarification ;
Added for completeness. ,
Change Request Number SA .97 147. 0 Related SEk : SSEP.: Section:
- SER/SSER impact N 17A.1 4 Sheet t l ;
T.ible Add the airlock control instrument and test connection tubing to System 8.
i
< Clarification Clarification to tellect the level of detail added to the FS AR Figure in as i- earlier amendment.
Change Request Number SA .97 147. O Related SER : SSER : Section:
SER/SSER Impact N i.
17A.1 4 Sheets 2,13.14,15. 28 I
Table Delete Code Class 3 from check valves and accumulators for air control piping for air operated valves. Change the discription of the accumulator from air to nitrogen for RCS system.
- Clarification
- Trivial change consistent with Note 41. the control piping need not be N. stamped (i.e, within a Code boundary).
Change Request Number S A - 97 147 . O i Related SER
- SSER : Section:
SER/SSER 1mpact N 1
. . . , . ~ . _ _ - , _ . . - , _ _ . _ . , . . _ , - . - _ _ _ _ _ _ , _ -.._..-..,._._-,,--_i:
_ _ _ _ . _ - ~ - _ - _ . - . . - _ - _ - _- . - .-_ _.- - _ . - -
j Attachment to TXX-9hol:,
CPSES UPDATED FINAL SAFETY ANALYSIS REPORT AMIINDMENT 95 DETAILED DESCRIPTION Page 169 Prefix Page Onutp Uccription Section:
[ar.rrtntdtd) 17A-1 4 Sheet 53 Table Correct Note 27 in Table 17A 1 to read as it was pre-A91. I Correction 1 DCR 92 225 incorrectly revised this note from " Meets certain portions.. " to
" Meets pertinent requirements....". This note applies to those non-safety items to which the requirements of Appendix 11 do not apply except by commitment, llence the wording " requirements" is incorrect and was not used in the CPSES response.1hc word " portions" was intentially used to distinguists a commitment from a regulation.
Change Request Number S A 72 .O Related SER : SSER : Section:
f SEIUSSER Impact N 17A-1 4 Sheet 50 Table Add chlorination systems to list of seismic Catrgory 11 systems shown on flow diagram l'igure 9.2 1.
Addition
> Class 5 piping shown on diagram applies. 'Ihis is a clarification for the user of Section 3.2 and 17A to find the applic.,ble systems and drawings for programatic seismic Category 11 requirements discussed in the PSAR.
Change Request Number SA -97 I13. O Related SER : SSER- Section:
SER/SSER Impact N 17A.I 4 Sheets 28 and 31 Table Add " Deluge and drain piping for filtration units" and the applicable code and reference notes.
Clarification Revise Table 17A (LIST OP QUALITY ASSURED STRUCTURES, SYSTEMS AND COMPONENTS) to modify the Primary Plant Ventilation S) stem and Control Room Air-Conditioning System to clarify the applicable codes and standards and QA program requirements for the deluge and drain connections to filtration units.
Change Request NumLer SA 23 .O Related SER : SSER : Section:
SEIUSSER Impact N
Attachment to 1XX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DI.SCRIPilON Page 170 Prefix Page Dunty De:.crintion Sullen; (as amended) 17A.I 4 Sheets I thru $0 & $$
i Table Added Note 40 & 45 to Table header, Clarification Note 40 added to Code Class Column for clarincation os ASME 111, Code Class " ".
Note 4$ added to clarify that the term
- PIPE" means more than pipe.
Change Request Number SA 147. O Related SI:R - SSI;R - Section:
SI R/SSER impact N 17A.I 4 Sheets 2,11.14,15,28,33 and 46 Table Correct eniscellaneous tubing infonnation in Tl7A 1 Correction Sheet 2,14, l$ remove code class for tubing and supporta (between check valves upstream of air occumuator and AOV)
Sheet i1,33 remove the word "and" between Process and Sampling Sheet 28 add code ( ASME 111) for Tubing and supports (between check valve upstream of accumulator and AOV)
Sheet remove the words
- process and sampling" from Impulse process and sampling tubing, fittings, valves and supports; and from Supports for process and sampling tubing, fittings an alves.
Change Request Number SA 137 . O Related SER , SSER : Section:
Sr.R/SSER impact N 17A.I 4 Sheet $5 Table Added Notes 40 and 45. Added clarification to Note 44.
Clarification Trivial change for clarification.
Change Request Number SA 147 . 0
.. Related SER . SSER . Section:
SER/SSER Impact N
___ _ _ _____.__._._.__ _ ___.__ _ .. _ . - _ .m._ _ ..__.._._.____..__m Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT ;
AMENDMINT 95 DETAILED DESCRIPTION i
- [
Page 171 j Preux Page Omg Description Section. ;
(as amended) 17A-1 4 Sheet $3 Table Delete Table 17A.I Note 29 which applies only to the lloron Concentration I Measurement System. [
Revision 9eejustification for revision to Section 7.7.1.10, page 7.7-27.
Change Request Number SA 97 -79 . II Related SER : SSER : Section:
- SER/SSER 1mpact N P j
17A.I 4 Sheet 5 Table Delete the lloron Concentration Measurement System from Table 17A 1.
Revision Sec justification for revision to Section 7.7.1.10, page 7.7 27.
Change Request Number SA 79 . 10 Related SER : SSER : Section: !
- SER/SSER impact N P
17A 1 4 Sheet 24 Table Repalce API 620 with API 650 for Laundry lloidup and Monitor Tanks.
Correction
'The specification 2323-MS-066 (retired) states that both API 620 and API 650 may be used; however vendor drawing D 700 pased the tank design on API 650 and FSAR Section 3.2.3 ref. 3 uses API 650. This change is to ellrninate a discrepancy between FSAR sections.
Change Request Number SA 102 . O Related SER : SSER : Section:
SER/SSER Impact N 17A-1 4 Sheets 4 A 7 Table Clarify the safety classification and quality attributes of the centrifugal charging pump and safety injection pumr, lube oil piping systems.
Clarification Revise DCA 95973 per IX7411447 to clarify the safety class and quality attributes.
Change Request Number S A 107 . O RelateelSER : SSER : Section:
SER/FSER impact N
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Atis.chment to TXX 98085 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95
- )ETAILED DESCRIPTION Page 172 l Prens Page '
l Description Section.
1 (m amendedi Group l
17A.I 2 Sheets 45 & 60 Add Personnel Air lock Ilydraulic system to Table and nes Note 85. l
- Table j
Addition '
1he applicable code is currently shown on the Personnel Air leck flow diagram, but was not shown in Table 17A.I and was not included in the existing descriptions. This makes lext and Table more complete by including
[
i~ the additional information from Table 3.8 22.
Change Request Number SA 84 .2 Related SER : SSER : Section:
l #
SER/SSER Impact N
- 17A.I 3 Sheet 20 ,
Table Add ASME Section III, Class 3, stilling wells Level to table 17A.I. (See description for 1 A(II) $3)
Addition Secjustification for I A(ll) $3.
i Change Request Number SA 110 . 5 Related SER : 17 SSEn : 22 Section: 17 SER/SSER Impact N 1 17A-1 4 Sheets 45 and 60 Table Add level sensing instrumentation to the steam supply and exhaust lines of the i
AFWPT.
Addition Ad:8 description of non-lE switches to Table 17A 1 Change Request Number S A 92 . 0 Related SER : SSER : Section:
SER/SSER 1mpact N 17A-1 3 Sheet 16 Table Revises table to show Non-Appendix 11 QA program for Steam Generator Feedwater Pump turbine speed control for Unit 1.
Revision The previous speed control for the Unit 1 SOFP was not perfomiing satisfactorily and was upgraded to a digital c<mtrol. A specifically .itructured Non Appendix 11 QA program will be implemented by CPSES to control software in the SOFP turbine speed control. ,
e Change Request Number S A 85 .4 Related SER : 17 SSER : . Section:
SER/SSER Impact N ,
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CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMINDMENT. 95 Dlil AILED DESCRIPTION Page 173 Prc0x Page Group Description Section.
(as amendnu l.C- 4 4 Revise " Group Vice President, Nuclear Production" to " Senior Vice President
& Principal Nuclear OHicer".
Revision Changed to reficct 1997 organization oflU Electric.
Change Request Number SA - 97 129 . 18 Related SER
- SSER
- Section:
SER/SSI:R impact N 1.C- 7 4 Change to section I.C.$ to identify that vendor technical correr.pondence is reviewed for operating experience as part of the VETIP program.
Clarification
'Ihis change is to clarify that vendor technical correspondence is screened for operating experience as a part of the VETIP program, rather than naming a specific group within the program 1he screening for operating experience has been and will continue to be part of the VETIP program.
Change Request Numher SA 47 ,.I Related SI:R
- SSER . 23 Section: 7.2.6 SER/SSER impact N 1.C. 8 4 Revise " Nuclear Planning" to " Plant Support" Revision Secjustification for change request number SA-97-130.1 for pages 13.1 5,6,7 and 12.
Change Request Number SA - 97
- 130 , 9 Related SLR : SSER . Section:
SER/SSER Impact N
Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMI:NT. 95 DETAILED DESCRIPilON Page 174 Prefis Page Qwup DescrintioO Section.
f an amendtsi)
II.D- 3 2 Clarifies that the piping between the pressurint and the PORVs does not include a loop seal but is uninsulated and slopes to the valve providing a water seal at the inlet to the PORVs.
Clarification
'Ihc confusing description was identified and resolved in accordance with the CPSES corrective action procedures. This discussion appeared unclear and inconsistent with the CPSES design which was reviewed and accepted by the NRC.
Change Request Number SA 11$ , I Related SER : SSER
- 26 Section: II.D SER/SSER impact Y SSER 26 Appendix iT provides discussion indicating that the staff was aware that a water seal was provided on the inlet to the PORVs. Ilowever, some statements include the term loop seal which is not an accurate description.
til A-01 4 Revise title for Section lil.A and Ill.A.I.
Revision Secjustification for change request number SA 96-87.1 and page TMI vil.
Change Request Number SA -96 87 . 2 Related SER . SSER . Section:
SER/SSER Impact N Ill.A. 03 4 Revise CPSES response to items 3) and 4) with respect to NUREG-0640, :'t Ill.A.1-9 and licensee actions to upgrade emergency preparedness.
Revision TU Electric describes the current emergency response facilities (1 SC, OSC and EOF) required to be established by NUREG-0660 in the CPSES Emergney Plan. Section 6 (i.e., response to item 3). Requirements for upgraded ofTsite monitoring (i.e., response to item 4) are described in the CPSES Emergency Plan, Section 7. These changes provide references to the appropiate Emergency Plan Sections; redundant description in TSAR lil.A.I.2 has been relocated to the Emergency Plan.
Change Request Number SA 87 . 3 Related SER
- SSER : Section:
SER/SSER 1mpact N
.-._ _. _.-_ _ _.._ ____. _.-._- _ _..-.. _ _.y 1
j Attachment to TXX 980l$
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT :
AMENDMENT. 95 ;
DETA1EI) DESCRIPTION Page 175 Prefix Page Description St etion, j las amended] [ing!
l 1
lil.A. 03 4 I
Revise title for Section Ill.A.I.2. ,
Revision Revised to be consistent with the title in NUREO-0660 for the same section. l 1
Change Request Number S A 87 , 4 Related SER t $$ER : Section:
SER/SSER Impact N
= ;
Ill.A 04 4 and Page $ ;
7 Revise Section Ill.A.I.2., Subsection I." Introduction". ,
Revision Revised to reflect that the the required emergency response facilitica (TSC, y OSC and LOF) have been established, are described in the CPSES Ernergency Plan (vis. FSAR Section Ill.A.I.2), and have been upgraded to include an :
integrated data acquistion system which is further described in FSAR Section Ill. A.I.2, Subsection II.
Change Request Number SA - 96 87 . $
Helated SER : SSER : Section:
SER/SSER 1mpact N !
Ill. A- 05 4 and Page 6 Renumber and retitle Section Ill.A.I.2, Subscetion l1.11 "TSC Instrumentation, Data System Equipment, and Power Supplies" to become Section Ill.A.I.2, Subsection ll.'Tanergency Response Facility Instrumentation, Data System Equipment, and Power Supplies"; revise this section description.
Revision Renumber to be consistent with revised numbering sequence for Section Ill.A.I.2; revised to be inclusive of similar description for both the TSC and EOF data display equipment. Relocated' clarified certain statements from the EOF data display d' -8 iption in Subsection IV.I concerning the EOF data .,
display power supps. .nd that there is no loss of data if display power is lost, This revision supports the relocation of EOF description within FSAR Section Ill.A.I.2 and/or to the Emergency Plan.
Change Request Number SA 87 . 7 Rel4.M SER : SSER : Section:
SER/SSER Impact N f
l l
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. . _ - . , _ , . _ . _ . . . ~ . _ _ . . _ . . . ~ . _ . , _ . - _ -
i i Attachment to TXX 980l$
r CPSIIS - UPDATl!D FINAL SAFl!TY ANALYSIS RF. PORT AMI:NI)Ml:NT. 95 I)l: Tall.l:D DI:SCRIPIION Page 176 Prefin Page l
i lhLAIMadat) Omus usstiptIon Stilkn; j lli.A. 06 4 and Pages 7,8 4
Renumber Section Ill.A.I.2.. Subsection 11.1 "'l SC Technical Data and Data 4
System" to become Section Ill.A.I .2., Subsection ill, " Technical Data and t i Data System".
Revision Renumber to be consistent with revised nambering sequence for Section l' ill.A.I.2; revised to be inclusive of similiar description for the 1:OP and to e e
' reflect that this equipment has been installed and is currently availlable in the 1:RI"s. I Change Request Number SA #7 . . N 4 Related SIER : SSI:R : Section:
SI:R/SSI:R impact N i'
j- lil.A 0h 4 i Renumtwr Section all.A.I.2. Subsection ll."Tecimical Support Center" to '
i become Section Ill.A.I.2, Subsection IV; provide reference to the appropiate section in the CPSI;S l'.mergency Plan and delete the TSC description from l '
l'SAR lli.A.l.2.
a j Revision Renumber to be consistent with revised numbering sequence for Section .
4--
Ill.A.I.2. 'the current description / function of the CPSI:S cmcrgency response facilities (TSC, OSC and I:OF) are maintained in t*-c CPSI;S limergeny Plan.
- 1he CPSI S 1
- mergency Plan in the primary CPSI:S licensing basis document i for analntaining and describing emergency preparedness at CPSI;S; accordingly, redundant facillity descriptions have bxn relocated from the *
- I SAR to the CPSI S limergency Plan. l'igures Ill.A.I.21 (TSC), Ill.A.I.2 3 (OSC) and lil,A.I.2 4 (1:017) are being deleted in conjuction with rchication of ,
3 i the discussion / description of the 1:RI's, l c., teference to description of the j I:RIs in the !!.mergency Plan.
] Change Request Number S A 87 . 6
, Related SI:R t SSI:R . Section:
SI:R/SSI:R impact N lil.A.0R 4 Renumber Section Ill.A.I.2, Subsection Ill. " Operational Support Center" to 4 become Section Ill.A.I.2. Subsection V; delete the OSC description from I'SAR Section !!!.A.I.2 and provide a reference to the CPSI:S F.mergency Plan.
Revision Secjustification for change request number SA 96-87.6 for pages Ill.A 8.
Change Request Number SA 87 9 Related SliR : SSliR ' t Section:
5 l
u,-. - ..n . ~..._a, . _ . . , . . _ _ _ _ . _ _ _ . .__- ._ . _ _ _ _- _ - -
i Attachment to TXX-98015 l CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT .
AMENDMI:NT- 95 UET All,1:D DI:.SCRIPilON Page 177 Prefir Page (its amended) Orcup Denripdeu Stetion:.
SEIUSSI:R 1mpact N i
til A 08 4 Delete statement "To rnaintain profiency the 1 SC (1:OF) staff will participate in 1!"'(LOl') activation drills that will be conducted perioically in 4
accordwice with the Emergency Plan."
Revision 1his statement was not relocated to the CPSES bnergency Plan. Section 12 of the CPSES Ernergency Plan already provides for periodic exercies to be conducted. These exercises require that the facilities be activated; therefore, by participating in periodic exercises as required by the Emergency Plan, facility activation drills are conducted.
Change Request Number SA 87 . 20 Related SER : SSER : Section:
SEIUSSER Impact N lli. A. 08 4 Renumber Section III.A.I.2, Subsection IV. Emergency Operations Facility",
to become Section Ill.A.l.2, Subsection VI; delete the LOF description from I'S AR lli.A.l.2 and provide a reference to the CPSES Emergency Plan.
Revision Secjustification for change requrest number SA-96-87.6 for pages lli.A 8.
Change Request Number SA 87 , 10 Related SER - SSER : Section:
SEIUSSER Impact N lil.A- 14 4 Revise " data de multiplexors" to " data multiplexors".
Correction Change tellects correct technical wording.
Change Request Number S A 87 . 12 Related SER : SSER , Section:
SEIUSSER Impact N
Attachment to TXX 98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT l AMENDMENT 95 DETAll.ED DESCRIPTION l Page 178 Prefix Page 012U2 DnE.ticil2D SEElieni
[as amtnded) i Ill.A.16 4 Renumber Section Ill.A.I.2, Subsection VI, "Intergrated ERF Computer System" to become Section Ill.Al.2, Subsection Vill; delete use of words l
" proposed for CPSES'.
Revision Renumber to be consistent with revised numbeering Sequence for Section Ill.A.I.2 and delete outdated wording since the ERF Computer Sy tem is now installed at CPSES.
Change R quest Number SA 87 . 13 Related SER : SSER : Section:
SER/SSER impact N lli.A.17 4 Revise all. Implementing Shedule" to change "will be" to "was".
Revision Resised to . flect that the ERF Computer System has been installed instead of will be instwied.
Change Request Number SA = 96 - 87 . 14 Related SER : SSER : Section:
SI:R/SSER 1mpact N lli.A 19 4 Revise CPSES response in Section Ill.A.3.3" Communications".
Revision Revised to reflect installation of the Federal Telecommunications System (I'1 S) at CPSES.
Change Request Number SA 87 . 15 Related SEit - SSER Section:
SER/SSER impact IJ lil. A.1,- 2 1 4 I igure Delete Figure Ill. A.I.2 1, " Technical Support Center".
Revision Figure was deleted in conluction with the relocation of the discusslorvdescription of th 3RFs from the FSAR to the CPSES Emergency Plan. Figure has been delet from the FSAR and is not in the CPSES Emergency Pla :. The figure was a rough outline of the boundary for the sub.icet ERF; m the CPSES Emergency Plan there is discussion about the site and location of each of the ERFs. This discussion includes an approximation of the square Icet of available floor space, building location, and general area that is used, as appropiate, llased upor the discussion provided in fhe 3
._ _ _ _ . . _ _ ___ . .__ __.- _- - _ _ _ _ _ _ _ . _ _ . _ . _ _ . . . , _ ~ _ . _ _ _ _ _ _ _ _ . .
Attachment to TXX 9sols CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95
< DETAILED DESCRIPTION Page 179 Prefix Page i (an amended) Group Dcscrintl2D Section:
Emergeny Plan, the figure of the ERF is considered redundant and not needed.
l l Also, see justification for change request number SA 96 87.6 for page Ill.A-8.
! Change Requer.t Number SA 87 . 16 i Related SER : SSER : Section: l SER/SSER Impact N 4
I til.A.I. 2 3 4 Figure Delete Figure Ill.A.I.2 3,
- Operations St iort Center". .
1 Revision Seejustification for change rer;uest number SA 96 87.16 for Figure lil.A.I.2 1.
l Change Request Number SA 87 . 17
{
Related SER : SSER : Section:
- SER/SSER Impact N l
Ill.A. l .- 2-4 4 Figure Delete Figure III.A.I.2 4," Emergency Or eations Facility".
Revision i Seejustification for change request number SA 96 87.16 for Figure Ill.A.l .2 1.
Change Request Number SA 87 . 18 I Related SER t SSER : Section:
SER/SSER impact N III.D.10 4 Revise discussion for Section Ill.D.3.4,
- Control Room liabitability Requirements", responses to items (k), (1),(n) and (o).
Revision Revise item (k) to delete reference to CPSES Emergency Plan Section 8.5.1 as
- Scil A no longer discussed in this E. Plan Section. Revise item (1) to change the reference from the E. Pean Section 8.5.1 to the FSAR Sec' ion 6.4.1.3 I- where bottled air supplies are discussed. Revise item (n) to change " shift supervisor" to " Shill Manager" due to organizational position title change.
Revise item (o) to clarify this FSAR statement about what is spe:sfied in the -
Emergecy Plan concerning KI, i.e., the Emergency Plan specifies provisions for use and avaliablity.
Change Request Number SA 87 . 19 Related SER : SSER : Section:
1 SER/SSER Impact N 4
. - - - ~ . . , ,.,va~ v-- - , ,, . , -n,m-, --.-.-,~.-.-,----r.- w,~,v- -r--e e- ---.---.1+.,.--,,m , --.-~.ev,1, --v-m,-m--.:w-+r,m.. + w
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT . 95 DETAILED DESCRIPTION Page l'.0 Pru. Page
[RuimtDilnt) Ctmtm DescriplinD SEEliPJE M i- 0202 3 (F10.3-1)
Figure Add new figure to show the new arrangemcot of the steam supply lines to the TDAFW pump.
Addition See summary of changes for Ml-0202.
Chan;c Request Number SA 75 .2 Related SER - SSER - Section:
SER/SSER impact N M i- 0202 - 03 3 (F10.3 1)
Fipure Remove the " tee" conocction and the associated valves and piping for the two steam supply lines to the TDAFW pump from the figure, Revision Per DM 95-054, this scetion of the system was relocated and modined to improve overall reliability of the TDAFW pump.
Change Request Number SA 75 .1 Related SER SSER : Section:
SER/SSER impact N g
Mi-202 03 4 (Flo.3 1)
Figure Restores level indication to the Unit 1 Main Steam drip pott-MS-27, located in the steam supply piping to the TDAFW Pump.
Revision This inodincation provides operators a means to ascertain if excess condensation exists in the steam supply to the Turbine Driven Auxiliary Feedwate Pumps or if en.ess condensation accumulates in the exhaust drain system. A temperature compensated thermal dispersion type level sensor capahic of reliable operatioit in the design service conditions is being added to both the supply and exhaust condensate drainage system. A common alarm will annunciate at the Main Control floard when condensate is detected at the high level sensing point of either or both instruments. This alarm will be indicative of potential rcadensation drair blockage. Local independent indicating lights will enable operators to determine which sensor has tripped the local relay. Corrective actions such as manual operation of bypass valves can be taken. The source of the liquid for. nation can be desmined and adequate steps taken such as inspecting or cleaning trap strainers to limit condensate formation.
Change Request Number SA 72 . O Related SER : 10.3.2 SSER Section:
SER/SSER Impact N
Attachment to TXX.98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT i AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Page 181 Group Descrintion Sectton.
(as amended)
Mi-0203 3 (F10,4-9)
I igure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Steam Generator Feedwater System algure to indicate flow to Secondary Sampling Syste .. . See Description for pp. 10.4-132 and 134.
Change Request Number SA 96 .O Section:
i Related SER .10.4. SSER SER/SSER impact M l- 0204 02 4 (F10.4 8)
Figure Deletes references for installed conductivity elements.
Revision See Description for FSAR pp.10.4-6,7 and 9.
Change Request Number S A 106 . 3 Related SER 10.4 SSER : Section:
FSR/SSER Impact N Mi- 0204 3 (F10.4 8)
Figure Revise figure to depict new manually operated Vee-Ilall valve ICO-0255 and bypass valve, ICO-0505, is aoded across manual valve ICO-0256.
Correction Gate valve (ICO-0255) was previously used for component isolation. The new Vee-liall valve will provide suflicient shut-olTcapability along with excellent throttling chatacteristics. The bypass valve across the gate valvt ICO-0256 will aUow filling the condenser which in turn will reduce the forces necessary to open the isolation valve.
Change Request Number SA 76 .2 Related SER : 10.4 SSER : Section:
SER/SSER Impact N M1- 0204 02 4 (F10.4-8)
Figure Add a sample point from the Auxiliary Condenser for chemistry.
Addition A sample point from the Auxiliary could be benencial is locating tube leaks, thus enhance plant performance.
Change Request Number SA 13 , I Related SER SSER . Section:
SER/SSER impact N k
Attachm,nt to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DSTAILED DESCRIPTION Page 182 Prefix Page (as amendnt) Group Descridion krction:
Mi- 0204 01 4 (F10.4-6) l'igure Revise Mi-0240-01 to delete the R inch lines that are routed to the Chlorination llullding along with the diffusers. Mc lines and diffusers are abandonded in phico Revision Sec Justification of Change for 10.4 37.
Change Request Number S A 64 ,2 Related SER ,10.4 SSER : Section:
SER/SSER Impact N M1- 0204 3 (F 10.4-8)
Figure Addition of Secondary Corrosion Pnxluct Monitors and Local Dissolsed Oxygen Analyzers.
Addition Revised Condensate System figure to indicate 110w to Secondary Sampling System. See Description on pp. 10.4-132 and 134.
Change Request Number SA 96 .O Related SER 10.4. SSI$>. Section:
SER/SSER impact M i- 0209 3 (F10.4-14)
Figurc Addition of Secondary Corrosion Prodact Monitors and Local Dissolved Oxygen Analyicts.
Addition Revised llcater Drains ! r cms figure to indicate flow to Secondary Sampling System. See Description nor 10.4132 and 134.
Change Request Number S A '6 ,O Related SER 10.4. SSER + Se an:
SER/SSER Impact Ml-0210 -01 4 (Flo.4-5)
Figurc Revise Mi-0210-01 to delete the 8 inch lines that are souted to the Chlorination lluilding along with the difTusers. %e lines and diffusers are abandonded in place.
Revision See Justification of Change for 10.4-37, Change Request Number S A 64 .3 Related STR 10.4 SSER Sectio :
SER/SSER Impact N I
l
(
Attachment to TXX-96015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT Ah.ENDMENT 95 DETAILED DESCRIPTION Page 183 Prefix Page Group Descrintion Section.
(aumtllded)
Mi-211 4 (Fl0.4 3)
- l'igure Revises Figure to add valve to the seal water supply line to condenser vacuum breaker loop seal.
Revision A new supply valve will be added to the seal water supply line to the condenser vacuum breaker loop seal. The valve will be located to permit operator manipulation with minimum access problems to reduce the chance of personnel in, jury. This change does not change the design or function of the system.
Change Request Number S A 138 . O Related SER 10.4 SSER : Section:
SER/SSER Impact M t. 0212 3 (F10.4-15)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Figure to indicate Secondary Corrosion Product Monitor 04 and 01 flows to the Turbine Plant Cooling Water System and flow from the Turbine Plant Cooling Wa;ct System to Secondary Corrosion Product Monitor 01. See Description for pp. 10.4132 and 134.
Change Request Number S A 96 .O Related SER 10.4. SSER Section:
SEIUSSER Impact Mi- 0212 11 3 (F10.4 15)
Figure Revise the flow diagram to note that the existing unit specific Service Air compressor is abandc.aded in place.
Revision See Justification of Change for 9.3 2.
Change Request Number SA 83 .6 Related SER . 9.3.1 SSER' Section:
SEIUSSER Impact N
Attachment to TXX-98015 l
CPSES - UPDATED FINAL SAFE'IY ANALYSIS REPORT AMENDMENT - 95 DETAILED DJSCRIPTION Page 184 Prefix Page (as amendg1) Group Description Section.
M i- 0215 -D 2 (l'9.5 55)
Figure Corrects l'SAR figure 9.5-55 (M t.0215-D) by modifying the Diesel Generator Starting Air System configuration and controls to establish a safety class interface.
Correction Modify DO Starting Air system to establish the safety class interface between the ASME code Section 111, Class 3 DG air receivers and the NNS DG compressors. Replace (a) co.npressor unloading NNS solenoid operated valves (SOVs) with ASME Code section 111, Class 3/ Class IE SOVs interlocked to close upon loss of power and/or decreasing receiver pressure (b) associated transformers and fuses in the solenoid electric power supply (c) compressor unloading manual bypass valves (d) booster / delay valve located on the compressor e ith 3 time delay relay in the electircal circuit to eliminate breaker trips and other problerns leading to unreliable system operation experienced in the past. Add a Class IE pressure indication switch source connected to each DG air receiver via a common root valve with the pressure switch and interlocked with the solenoid to ensure a controlled isolation of the receiver in the event of a line break downstream of the SOVs and/or the compressor failure. Delete the scale trap filter which has been found to be a source ot' rust causing damage to the compressor. 'Ihe SOVs and the manual bypass valves will be located away from the compressor to climinate the vibration problems alTecting the valve functional reliability. Piping stress analysis will be performed for the as built configuration to ensure structural integrity of the affected portion of the system.
The safety class interface will be in accordance with ANSI N18.2 and FSAR Section 3.2. Replacement and relocation of the applicable components and the interhxks will result in functional reliability of the DG starting air system, and isolation of ASME Code Section til, Class 3 air receiver from the NNS air compressor under appropriate conditions to ensure at least one emergency DG start.
Change Request Number S A 34 .6 Related SER 9.5.6 SSER Section:
SER/SSER Impact N
Attachment to TXX-98015 l
CPSES - UPDA1 ED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 185 Prefix Page Oroup Descrintion Section.
(as amendsd]
M i- 0215 E 2 (I'9.5-55)
Figure Corrects FSAR Ogure 9.5-55 (M1-0215-E) by modifying the Diesel Generator Starting Air System configuration and controls to establish a safety class interface.
Correction Sec justifications for change request number SA-96-34.6. (Figure 9.5-55 (M1-0215 1D).
Change Request Number S A 34 .7 Related SER 9.5.6 SSER Section:
SER/SSER 1mpact N Mi- 0216 4 (I'9.3-1)
Figure Revise l'iow Diagram Ml-0216 to incorporate the upgrade or the Plant Air System.
Update See Justification of Change for page 9.3-4.
Chaage Request Number S A 69 4 Related SER 9.3.1 SSER 23 Section: 9.3.1 SER/SSER 1mpact N M i- 0216 .C 4 (F9.3 1)
Figure Revise the Flow Diagram P it-0216-C to incorporate the upgrade of the Plant Air System.
Update See Justification of Change for page 9.3-4.
Change Request Number S A 69 .5 Related SER 9.3.1 SSER 23 Section: 9.3.1 SER/SSER 1mpact N M1- 0216 - 01 4 (F9,3-3)
Figure Revise Flow Diagram M1-0216-01 to incorporate the upgrade of the Plant Air System.
Update Ece Justification of Change for page 9.3-4.
Change Request Number SA 69 .7 Related SER : 9.3.1 SSER 23 Section: 9.3.1 SER/SSER tmpact N
j Attachment to TXX-98015 i
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 186 Prefix Page Qme Descrmtion Section.
[as amended)
M1-0216 A 3 (F9.3-1)
Figure Revise the flow diagram to describe the new common Service Air compressor.
Revision See Justification of Chang; for 9.3-2.
Change Request Number SA 83 .4 Related SER 9.3.1 SSER . Section:
SER/SSER 1mpact N Mi- 0216 A 4 (F9.3 l)
Figure Add 3/8" instrument air tubing and valves. Replace water treatment system PVC Solenoid Chemica' isolation valves with Alloy 20 air actuated soler:oid ball valves.
Revision Alloy 20 ball valves are excellent for sulfuric acid service. These changes are considered trivial and this activity does not affect nuclear safetv nor the operation or functionality of tne water treatment chemical feed or instrument air systems.
Ch mge Request Number SA 4 ,I Related SER 9.2.3 SSER - Section:
SER/SSER 1mpact N M i- 0220 - 01 A 3 (F9.3-1)
Figure Revise the flow diagram to reflect abandonment and removal of Water Treatment System Equipment.
Revision See Justification of Change for 9.2-36,40,53,54.
Change Request Number SA 78 .2 Related SER SSER Section:
SER/SSER Impact N Mi- 0222 3 (F10.4 20)
Figure Additam of Secondary Corrosion Monitors and Local Dissolved Oxygen Analyzers.
Addition Revises Secondary Sampling System figure to indicate flow to Secondary Corrosion Product Monitor 04. Revises Secondary Sampling System figure to indicate the following: Stearn Generator lilowdown System (MI-0239) flow to Secondary Corrosion Product Monitor 02; feedwater System flow (MI-0203) to Secondary Corrosion Product Monitor 01 and Local Dissolved Oxygen Analyzer; Condensate Sysicm Pump A and B (MI-204) flow to Secondary Corrosion Product Monitor 03; and Condensate System Discharge
Attachment to TXX 98015
)
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Page 187 Prefix Page Onmp Description Section, (as amended) licader (MI 204) Dow to Local Dissolved Oxygen Analyzer.
Change Request Number SA 96 ,O Related SER 10.4. SSER Section:
SEIUSSER impact Mi- 0224 - Ol A 3 (F9.2-4A)
Figure Revise the flow diagram to rencet abandonment and removal of Water Treatment System Equipment.
Revision See Justi0 cation of Change for 9.2-36,40,53,54.
Change Request Number SA 78 .3 Related SER SSER Section:
SER/SSER 1mpact N M1- 0224 - OlF 4 (F9.2-4 A)
Figure Add 3/8" instrument air tubing and valves. Replace water treatment system PVC Solenoid Chemical isolation valves with Alloy 20 air actuated solenoid ball valves.
Revision See Justi0 cation of Change for Mi-0216-A.
Change Request Number SA 4 .2 Related SER 9.2.3 SSER Section:
SER/SSER 1mpact N M1-0224 - 01 D 3 (F9.2-4 A)
Figure Revise the flow diagram to renect abandonment and removal of Water Treatment System Equipment.
Revision See Justification of Change for 9.2-36,40,53,54.
Change Rec,uest Number SA 78 .4 Related SER SSER Section:
SER/SSER Impact N
Attachment to TXX-98015 l
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DL' TAILED DESCRIPTION Page 188 Prefix Page Group Description Section.
[BI.P.msnded)
M1- 0224 - 01 4 (F9.2-4 A)
Figure Revise Dow diagram to add the Water Produe' ion and Oil Lab Emergency shower and eye wash.
Revision See Justification of Change for Ml.0227.
Change Request Number SA 26 .2 Related SER , 9.2.4 SSER Section:
SER/SSER impact N M1- 0224 - OlO 4 (F9.2-4 A)
Figure Add 3/8" instrument air tubing and valves. Replace water treatment system PVC Solenoid Chemical isolation valves with Alloy 20 air actuated solenoid ball valves.
Revision See Justification of Change for Ml-0216-A.
Change Request Number S A 4 .3 Related SER 9.2.3 SSER . Section:
SER/SSER impact N M I- 0227 4 (F9.2-6)
Figure Revise flow diagram to delete the Water Production and Oil Lab Emergency shower and eye wash.
Revision Use of demineralized water will eliminate the need for super chlorination to disinfect the piping. These changes are considered trivial changes and do not alTect nuclear safety nor the operation or function of the Potable and Demineralized water system.
Change Request Number SA 26 .I Related SER 9.2 4 SSER Section:
SER/SSER impact N Mi- 0228 3 (F9.3-4 )
Figure Addition of the Analyzers and Detectors to continuosly monitor the pit of the Steam Generator Blowdown Samples . Add pit as a contincusly monitored parameter.
Correction See Justification of Change for 9.3-15,20.
Change Request Number SA 29 .3 Related SER 9.3.2 SSER Section:
SER/SSER Impact 1
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPOR ,
AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Peg,e 189 Oroup Description Section.
(as amended) a Ml- 0230 3 (F9.2-3)
cross-tic lines for the Spent Fuel Pool lleat Exchangers.
Revision To facilitate Unit 2 construction completion, the previous manual isolation valves were removed and replaced with spectacle flanges. Although the cross-tic capability was still available by rotating the spectacle part of the l
flange in place, it is a cumbersome and time consuming process. Restoring the
' cross-tic capability with manual valves allows the cross-tic to be put into service more readily.
Change Request Number SA 77 . 1
- Related SER : 9.2.2 SSER , Section:
SER/SSER Impact N j M1- 0230 A 4 (F9.2 3)
Figure Revise Flow Diagram M10230-A to incorporate the upgrade of the Plant Air System.
Update See Justification of Change for page 9.3-4.
Change Request Number SA 69 .6 3
Related SER : 9.2.2 SSER , 25 Section: 9.2.2 SER/SSER 1mpact N i Mi-0235 - 02 ? (F9.1 13)
= Figure Adds new Spent Fuel Pool (SFP) level devices (X-LY-4849A 1, X-LY-4849A 2, X-LY-4849B 1 and X-LY-48498-2)to provide 2-out of 2 logic for Spent Fuel Pool cooling pump protection on low-low pool level and continuous level indication in the control room.
Addition Seejustification for i A(D) 53.
Change Request Number SA 110 . 7 Related SER . 9.1.3 - SSER : 22 Section: 9.1.3 SER/SSER Impact N J
~- .- - , ,,---.,v. --.-,s. --s , -- , .-
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFE 1Y ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 190 Prefix Page Group Descrintion Section.
(as amended)
Mi-0236 -A 3 (F9.3-6)
Figure Revise figure to show drain hub installed in Door drain line to accomodate drain from flash tank.
Revision See summary of changes for Ml-0202.
Change Request Number SA 75 .3 Related SER : SSER : Section:
SER/SSER Impact N M1- 0239 3 (F10.4-10)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Steam Generator lilowdown Cleanup System figure to indicate now to Secondary Sampling System. See Description for pp. 10.4-132 and 134 Change Request Number S A e t - 96 .O Related SER : 10.4. SSER. Section:
SER/SSER Impact Mi- 0241 3 (F9.2-5)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Detaineralized and Reactor Makeup Water figure to indicate now to Secondary Corrosion Product Monitors 1-02 and 2-02. Four (4) Corrosion Product Monitors and two (2) Local Dissolved Oxygen Analyzers have been pennanently installed to provide for improved secondary side sampling capability. Corrosion Product Monitoring and Dissolved Oxygen control is essential for secondary side chemistry which is conducive to preserving secondary side components froni accelera ed aging and premature replacement.
Corrosion product monitor components requirc a sample temperature of around 100 degrees F. The Steam Generator Blowdown, Feedwater and lleater Drains samples will require cooling to meet the reduced sample temperature requirements.
Change Request Number SA 96 .O Related SER + 10.4 SSER Section:
SER/SSER Impact
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAlLED DESCRIPTION Page 191 Prefix Page Omug Descrintion Section.
Ias amended)
Mi- 0241 -01 2 (F9.2 5) l'igure The Unit I and common Reactor Water Makeup pump eninillow lines and recirculation lines are being increased from 1-inch to 2-inch.
1hc Dow - :triction orifices are being relocated from the discharge of the Reactor Water Makeup Pumps to the applicable supply lines.
Revision See change request number SA-96-55.2 on page 9.2 38 for additional information.
Change Request Number SA 55 .3 Related SER 9.2.3 SSER : Section:
SER/SSER impact N 4
M1- 0242 3 (F9.2 5)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Demir.eralized and Reactor Makeup Water figure to indica': flow to Secondary Corrosion Product Monitors 1-02 and 2-02. Four (4) Cor osion Product Monitors and two (2) Local Dissolved Oxygen Analyrcrs have been permanently installed to provide for improved secondary side sampling capability. Corrosion Product Monitoring and Dissolved Oxygen control is essential for secondary side chemistry which is conducive to preserving secondary side components from accelerated aging and premature replacement.
Corrosion product monitor components require a sample temperature of around 100 degrees F. The Steam Generator Blowdown. Feedwater and lleaser Drains samples will require cooling to meet the reduced sample temperature requirements.
Change Request Number S A 96 .O Related SER : SSER - Section:
SER/SSER Impact N
, MI- 0242 2 (F9.2 5)
Figure To reduce the effects of pressure transients initiated in another system, a surge suppressor is being installed near the-al relief valves that are excrpicncing inadvertent lifting.
Revision See change request number SA-96-55.2 on page 9.2-38 for additional information.
Change Request Number SA 55 .4 Related SER
- 9.2.3 SSER Section:
SER/SSER Impact N
l Attachment to TXX 98015 1
CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIITION Page 192 Prefix Page (as amendedi Group Descrintion Sedion.
Mi- 0244 - 01 3 (F10.4 7)
Figure Revise the figure to depict replacement of manual valve ICP-0001 on the discharge side of the Ilackwash Recovery Tank A with air operated valve 1-IIV-6457. '
Correction Addition of valve 1-ilV-6457 will enhance toe operation of the automated control system for the Condensate Polishing System.
Change Request Number SA 76 .3 Related -T:R 10.4 SSER Section:
SER/SsER 1mpact N M1- 0254 4 (F9.3-10)
Figure Add interface with CVCS mix bed demineralizer by-pass to the CVCS drawings.
Revision See justification for Section 9.3.4 on pages 9.3-33.36,40,47,49,61 and 78.)
Change Request Number SA 31 .2 Related SER . 9.3.4 SSER Section:
SER/SSER impact N Mi-0255 - 02 2 (F9.3 10)
Iigure Adds a flow restriction orifice in the supply line of the Reactor Water Makeup pump supply line.
Revision See change request number SA-96-55.2 on page 9.2-38 for additional information.
Change Request Number SA 55 .5 Related SER 9.2.3 SSER Section:
SER/SSER 1mpact N Mi-0258 4 (F9.3-10)
Figure Revise figure to reflect addition of piping cross-tic between the Recycle IIoldup Tank discharge and the Liquid Waste Processing System filter deminctlizer feed piping per plant minor modification.
Revision The cross-tie of the lloron Recycle System evaporator feed pt mp discharge piping with the Liquid Waste Processing System filter demineralizer feed piping allows processing of the Reevele lloldup Tank liquid waste inventory without the use of drain hoses. Ily eliminating the need for the drain hoses, personnel safety is enhanced and the possibility of contaminatiol is reduced.
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Page 193 Prefix Page Orge Description Section.
Lalamended)
The piping systems are compatible with regard to pressure and temperature triting, piping material specification, and Radioactive Waste M anagement System jurisdiction and requirements. 'the change increases Radwaste Operations ficxibility and does not adversely affect the performance or function of tne 1.iquid Waste Processing System or Doron Recycle System.
Change Request Number SA 58 . 1 Related SER 11.2 SSER Section:
SER/SSER Impact N M i- 0259 3 (F9.3-l l)
Figure Revise flow diagram Mi-0259 to reflect the normal position of valve XilR-0008 to be closed.
Revision See Justification of Change for 9.2-37.
Change Request Number SA 4 .4 Related SER SSER . Section:
SER/SSER Impact N M l- 0267 4 (Fi l .2-5)
Figure Revise figure to tellect addition of piping cross-tic between the Recycle lloidup Tank discharge and the Liquid Waste Processing System filter demineraliter feed piping per plant minor modification.
Revision This change reflects a phmt minor modification; see justification for Change Request Number SA-95-058.1 for Figure M1-0258 Change Request Number SA 58 .2 Related SER . I1.2 SSER Section:
SER/SSER impact N M i- 0269 - A &ll 3 (Fi l.3 1)
Figure Revise FSAR Figure Mi-0269, Sheets A & H (previouly FSAR Figure i 1.3 1, Sheet 2), " Gaseous Waste Processing System GWPS" A plant minor modification (MM 94-377) installed vendor recommended regulators and flow indicators in the pLmt nitrogen purge line to the Gas Analyzer Racks and replaced a pneumatic Manual / Auto (M/A) station with an electronic M/A station.
Revision This modification was installed to eliminate problems w th microprocessor lockup and the failure of the analyzers to control the recor biner oxygen supply and to satisfy channel checks. These changes invoh ' a non-safety related system and do not impact the functionality / functional capability of the
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT - 95 DETAILED DESCRIPTION Page 194 Prefix Page
[g m ended) Group Description Siqlips GWPS. This change does not impact plant safety systems or reponse to a system failure. All system interactiott' separation and design basis requirements continue to be satisfied.
Change Request Number SA 39 . I Related SER , SSER. Section:
SER/SSER impact N M1 0301 -A 2 (F9.4-6)
Figure Revisc 10 inch containment penetration from " Spare"to " Containment Leak Rate test Depressuritation" penetration.
Revision The containment penetrat'on is being changed for use during ILRT and for cable feed thru during normal plant outage activities.
Change Request Number S A 31 .O Related SER SSER , Section:
SER/SSER impact N M i- 0301 -A 2 (F9.4-6) l'igure Revise to include a blind flange on the outboard containment isolation valve foi containment penetrations MV-0001 and MV-0002.
Revision Provides for the installation of ASME code class blind flanges outside containment to seat ofTthe penetration to support LLRT as an acceptable substitute for the outside containment valve.
Change Request Number SA 74 . 1 Related SER SSER Section:
SER/SSER 1mpact N M i- 0304 4 Sheet A Figure Change titles for Room 142 from " Locker Room" to "Womens foilet Room" and Room 141 from " Toilet" to " Men's Toilet".
Addition Sec justification for page 9.4.l.
Change Request Number S A 41 .3 Related SER , 9.4.1 SSER Section:
SER/SSER Impact N
. -- . _. = . . .. .
Attachm-nt to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Page 195
[gumended) Omug DescriptiqIl Sgglien; M1-0.s11 3 Figure Adds UPS and Distribution Rooms Fan Coil Units to the Safety Chilled Water Sys. tem.
Correction Sec justification for FSAR Section 9.4C (Page 9.4C-12).
Change Reqve ,1 Number SA 150. 2 Related SER : 9.4 A SSER : 22 Section: 9.4.6 SER/SSER 1mpact N M i- 0313 3 (F9.4 15) Sheet 01 Figure Adds Fan Coil Units for the UPS and Distribution Rooms in UPS Air Conditioning *,ystem flow diagram.
Correction Sec justification for FS AR Section 9.4C (Page 9.4C-12).
Change Request Number SA 150 . 3 Related SER : 9.4 SSER 22 Section: 9.4 SER/SSER impact N M2- 0202 - 03 4 (F10.3 1)
Figure Restores level indication to the Unit 2 Main Steam drip pot 2-MS-27, located in the steam supply piping to the TDAFW Pump.
Revision This modification provides operators a mean n x rfsin if excess condensation exists in the steam supply to ti e Driven Auxiliary Feedwater Pumps or if excess condensation as .. ates in the exhaust drain system. A temperature compensated thermal dispersion type level sensor capable of reliable operation in the design service tonditions is being added to both the supply and exhaust condensate drainage system. A common alarm will annunciate at the Main Coritrol Board when condensate is detected at the high level sensing point of either or both instruments. This alarm will be indicative of potential condensation drain blockage. Local independent indicating lights will enable operators to determine which sensor has tripped the local relay. Corrective actions such as manual operation of bypass valves can be taken. The source of the liquid formation can be determined and adequate steps taken such as inspecting or cleaning trap strainers to limit condensate formation.
Change Request Number SA 89 ,,
Related SER : 10.3.2 SSER , Section:
SER/SSER Impact N
l Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Page 196 Prefix Page (as amended) fnpyy Descrintion Section.
M2- 0202 I (F10.3 1)
Figure 2-IIV 24521 and 2-IIV 2452 2. the steam admission valves to the turbine driven auxiliary feedwater pump, are being swapped with respect tn which valve is associated with each steam line for train considerations.
Revision This change is part of the corrective acthn prescribed to the condition reported in LER l-97-001-00. The modificat' s was required to restore the design basis for operation of CPSES. These coanges have been implernented for Unit 2 only at this time.
Change Reqacst Number SA 27 . I Related SER SSER - Section:
SER/SSER Impact N M2- 0702 4 (F 10.3-l'.
Figure The " tee" connection for the two steam supply lines to the TDAFW pump turbine is relocated from the pump room to the main steam and feedwater penetration area to reduce the volume of pipe between the steam admission valves and the turbine. This requires the check valves and manual block valves for each 4" line to be relocated accordingly upstream of the connection.
One of the existing supply lines is retained as the common header and
" knockout pots" are instelled M remove condensation generated by cold start transients. The other supply line . : converted to a drain / vent line for the knockout pots and is routed to a new absh tank. The existing high and low pressure drains are routed to the Dash tart and the existing steam traps are removed. The tank is vented to atmosphert ud drains to the floor drain system. The governor valve stem leakofiline is rotated to improve draining of the valve stem.
Revision The nuxis will reduce the volume of condensation generated and will remove the remaining water before it passes through the turbine resulting in smoother starting tranvients and a lesser demand on the governor to prevent overspeed trips. The flash tank will ensure that the steam from the drains and knockout pots does not create a harsh environment for the Class IE equipment in the area. The mods will be in accordance with applicable codes and standards.
The overall efTect will be improved reliability of the TDAFW pump.
Change Request Number SA 20 . I Related SER SSER ' Section:
SER/SSER Impact N
. . - . - - . . . ~ - .. . _- - . - . . . -- , - - . . . - . -
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPT!ON Prefix Page Page 197 (as amendedi Group DrigIjp1].nti Eg.ction:
4 M2- 0202 03 1 (F10.4-9)
Figure- The " tee" connection for the two steam supply lines to the TDAFW pump turbine is relocated from Ge pump room to the main steam and feedwater penetration area to reduce the volume of pipe between the steam admission valves and the turbine. This requires the check valves and manual block valves for each 4" line to be relocated accordingly upstream of the connection.
One of the existing supply lines is retained as the common header and
. _ knockout pots" are installed to remove condensation generated by cold start transients. The other supply line is converted to a drain / vent line for the -
knockout pots and is routed to a new flash tank. The existing high and low pressure drains are routed to the flash tank and the existing steam traps are I removed. The tank is vented to atmosphere and drains to the floor drain system. 'lhe governor valve stem leakoffline is rotated to improve draining
- of the valve stem.
1 Revision See Justification of change for M2-0202.
Change Request Number SA 20 . 2 Related SER : SSER : Section:
l SER/SSER Impact N M2- 0203 3 (Flo.4-9)
! Figure Addition of Sceondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition RevisedSteam Generator Feedwater System figure to indicate flow to Secondary Sampling System. See Description on pp. 10.4-132 and 134.
Change Request Number SA 96 , O Related SER : SSER : Section:
SER/SSER 1mpact N M2 0204 -03 3 (F10.4-14)
Figure Revise the figure to show the lleater Drain Pump discharge downstream isolation valve replaced with a metal seated zero-leakage butterfly valve.
Revision -
See Justification of Ch.tnge for M2 0207.
Change Request Number SA 51 . 5 Related SER - SSER : Section:
SER/SSER Impact N 4
,, -, e ,- r ---y- . , ,
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Prefiz Page Page 198 Group Description Section.
(as amendsd]
M2- 0204 02 4 (F10.4-8)
Figure Change the sontrol logic for valve 2 FV-2239 (Condensate Pump Recirculation Flow Control Valve) to " fail closed" in the event of an electrical power failure 'n the control circuit. The normal valve function, to open in order to maintain adequate flow and protect the Condensate Pumps, remains unchanged. Also, loss of air failure will continue to result in a " failed oper '
valve position.
Revision
'!his change to the control circuit will result in the valve remaining in the normally closed position (normal power /high flow operations) or repositioning to a closed position (Iow power / low flow operation) in the event of a fuse failure. Operators will take other actions in the event oflow flow coincident with a fuse failure to protect the Condensate Pumps, which have no safety function and are low energy pumps with sulTicient time available for the operator to establish adequate recirculation flow. 'Ihis modification results in more stable plant operaations and continues to ensure the Condensate Pumps are protected from low . low conditions. A positive eiTect will be realized for the accident analysis as the unit will be less susceptible to a loss of feedwater transient that can lead to a reactor trip.
Change Request Number SA 24 . I Related SER ,10.4.7 SSER , Section:
SER/SSER Impact N M2- 0204 3 (F10.4-8)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Condensate System figure to indicate flow to Secondary Sampling System. See Description on pp.10.4-132 and 134.
Change Request Number SA 96 ,o Relat~1 SER + SSER Section:
SER/SSER 1mpact N M2- 0204 02 4 (F10.4-8)
Fis,ure Deletes references for installed conductivity elements.
Revision See description for FSAR pp.10.4-6,7 and 9.
Change Request Number SA 106 . 4 Related SER ,10.4 SSER. Section:
SER/SSER Impact N 4
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Page 199 Prefix Page Groun L)nstiption Section.
(numtaded)
M2- 0204 02 4 (F10.4 8) -
ligure Add a sample point from the Auxiliary Condenser for chemistry.
Addition See Justification of Change for Mi 0204 02.
Change Request Number SA 13 .2 Related SF.R : SSER Section:
SER/SSER Impact N M2- 0206 01 3 (Flo.4-il)
I igurc Add drain valve to the Auxiliary Feedwater Pump Turbine tube oil equalizing line. *lhe line is located beneath the turbine governor valve and the valve will aid maintenance personnel in draining oil and in ensuring moisture removal from the oil.1he pump seal leakolTdrain lines are being routed to a closer drain hub and connected with a new drain line from the pump skid. The flow restrictor in the high point leakolTline for service water in-leakage detection was rek>cated to the end of the pipe, and no longer goes to a floor drain.
Revision The oil drain valve will aid maintenance when removing oil from the turbine and will enable maintenance personnel to ensure removal of any moisture from the oil system, since the valve is at the low point where any moisture would collect. Rerouting the pump scal leakofTlines will eliminate several feet of piping and associated supports in a highly congested aren. 'the addition of the d drain line from the pump skid will climinate c!can-up of spilled water aller pump runs.
Change Request Number S A 20 .3 Related SER - SSER Section:
SER/SSER impact N M2- 0207 I (F10.4 14) l'igure Revise the figure to show tl.a lleater Drain Pump recirculation lines are extended inside the lleater Drain Tanks to below the water level, the existing pump discharge check valves are replaced with nonle check valves, the pump discharge isolation valves are replaced with metal seated zero-leakage butterfly valves and new suction isolation valves of the same style are added.
The pumps discharge control valve is resized and new metal scated zero-leakage butterfly isolation valves are added. The alternate drain line to the condenser is rerouted, the control valve is resiicd, and the isolation valves are replaced. Warm-up lines are added to keep the alternate drain lines for the llcater Drain Tank, Feedwater lleaters 2-1 A,2 111,2-2A, and 2-21) close to system operating temperature. New nonle check valves are added to the drain lines of Feedwater IIcaters 2 A and 2II.
Revision
Attachment to TXX-98ttl5 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMF.NDMIINT - 95 DI! Tall.l:D DlISCRIPTION Page 200 Prrfix Page (as amends.d) Group 'In niplinn Section.
us. e the initial operation of CPSliS IJnit 2, the lleater Drains System has evperienced a number of water hammer events which have resulted in ins:dation and pipe hanger damage. This modification will reduce these water hamener events and improve the ability to isolate components within the syster.1. I xtending the lleater Drain Pump recirculation lines to below the water level in the e dater Drain Tanks will climinate severe water hammer events caused by the collapse of volds in the recirulation piping during pump start. The use of noule check vstves in the pump discharge line will damper.
the water hemmer effects following a single lleater Drain Pump trip and ensure closu:e prior to flow reversal through the check valve. The new warm-up lines will reduce the occurrence of low pressure discharge water hammer events caused by a low temperaturc/high temperature interface passing through w restriction such as a valve. The new nonic check valves in the drain lines ofI cedwater lleaters 2A and 211 will prevent reverse flow from the lleater Drain Tanks to the alternate drain line when the heater alternate drain valve opens which has been observed to result in significant water hammer.
The new metal seated reio-leakage isolation valves will improve component isolation and maintenance, Resizing the pump discharge control and the llenter Drain Tanks alternate drain valves will improve water level control in the heater drain tanks.
Change Request Number SA 51 . I Related SI R : SSER Section:
SI!R/SSER Impe.t N M2- 0207 -A 4 (F10.4 14)
Figure Wann-up lines are added to keep the alternate drain lines for Feedwater l'. caters 2-4 A and 2-411 close to syste:9 operating temperature.
Hevision Fee Justification of Change for M2-0207 Change Request Number SA 51 .2 Related SliR SSIR Section:
StilVSSliR Impact N
,-4 * .. -- _. - _ e - - .
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT i
AMENDMENT 95 DETAILED DESCRIPTION Prefix 1%ge Page 201 (as amended) Group Descrintion section.
M2- 0209 3 (F10.4 14)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised lleater Draird Systems figure to indicate flow to Secondary Sampling System. See Description for 10.4132 and 134.
Change Request Number SA 96 .O Related SER
- SSER Section:
' SER/SSER Impact N M2- 0209 4 (F10.4-14)
Figure Warm-up lines are added to keep the alternate drain lines for the MSR Separator 2-11 Drain Tank, MSR Shell 2-B Drain Tank, and MSR Reheater 2-11 Drain Tanks close to system operating temperature.
Revision See Justification of Change for M2-0207.
Change Request Number SA 51 .3 Related SER
- SSER Section:
SER/SSER 1mpact N M2- 0209 -A I (F10.4-14)
Figure Warm-up lines are added to keep the alternate drain lines for the MSR Separator 2 A Drain Tank, MSR Shell 2-A Drain Tank, and MSR Reheater 2-A Drain Tanks close to system operating temperature.
Revision See Justification of Change for M2-0207.
Change Request Number SA 51 4 Related SER : SSER Section:
SER/SSER 1mpact N M2- 0210 4 (Flo.4-5)
Figure Revise M2 0210 to delete the 8 inch lines that are routed to the Chlorination fluilding along with the diffusers. The lines and dilTusers are abandonded in place.
Revision See Justification of Change for 10.4 37.
Change Request Number SA 64 .4 Related SER 10.4 SSER* Section:
SER/SSER Impact N
.. - .. - ,- .... .-.- . - -.- .- _ . ~ - . - . ..- . ~_. - ..- . .. - - ... - .._. --. ~.-
,' Attachment to TXX 98015 -
i '- l 1
CPSES - UPDATED FINAL SAFETY ANALYSIS REFORT AMENDMENT 95 l DETAI!,ED DESCRIPTION ,
Page 202
- Prefix Page f as amended) Group Descrintion Section.
l M2- 0212 3 (F10.4 15)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved i
Oxygen Analyzers.
Addition 3 Revised figure to indicate Secondary Corrosion Product Monitor 04 and 01 Hows to the Turbine Plant Cooling Water System and now from the Turbine Plant Cooling Water System to Secondary Corrosica Product Monitor 01. ' See Description for pp. 10.4132 and 134.~ ,
Change Request Number SA % . 0 Related SER : SSER : Section:
SER/SSER Impact N M2- 0212 - - 11 3 (F10.4-15)
Figure Revise the flow diar, ram to note that the existing unit specific Sen' ice Air compressor is abandonded in place.
Revision See Justification of Change for 9.3 2.
Change Request Number SA 83 . 7 Related'SER : 9.3.1 SSER : Section:
I SER/SSER Impact N
. M2- 0215 - D 2 (F9.5 55)
Figuri. Corrects FSAR figure 9.5-55 (M2-0215 D) by modifying the Diesel
' Generator Sta..ing Air System con 0guration and controls to establish a safety class interface.
Correction See justi0 cations for change request number S A-96-34.6. (Figure 9.5-55 h (M i-0215-I D).
Change Request Number SA 34 , 8
- - Related SER
- 9.5.6 SSER : Section:
SER/SSER Impact N I:
t n
4
Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT 95 DETAILED DESCRIPTION Prefix Page Page 203 Gmyp Descrintion Erstingn (stamended)
M2-0215 -E 2 (l'9.5-55)
Figure Corrects TSAR figure 9.5-55 (M2-0215-E) by modifying the Diesel Generator Str.rting Air System configuration and controls to establish a safety class interface.
Correction See justifications for change request number SA-96-34.6. (Figure 9.5-55 (Ml-0215-1D).
Change Request Number SA 34 .9 Related SER t 9.5.6 SSER , Section:
SER/SSER Impact N M2- 0216 A 3 (F9.3-1)
Figure Revise the flow diagram to note that the existing unit specific Service Air compressor is abandonded in place.
Revision See Justifiestion of Change for 9.3-2.
Change Request Number SA 83 . 5 Related SER 9.3.1 SSER , Section:
SER/SSER impact N M2- 0222 3 (F10.4-20)
Figure Addition of Secondary Corrosion Monitors and Local Dissolved Oxygen Analyrers.
Addition Revises Secondary Sampling System figure to indicate flow to Secondary Corrosion Product Monitor 04 Revises Secondary Sampling System figure to indicate the following: Steam Generator illowdown System (M2-0239) flow to Secondary Corrosion Product Monitor 02; Feedwater System flow (M2-0203) to Secondary Corrosion Product Monita. 01 and Local Dissolved Oxygen Analyzer; Condensate System Pump A and f3 (M2-204) flow to Secondary Corrosion Product Monitor 03; and Condensate System Discharge lleader (M2-204) flow to Local Dissolved Oxygen Analyzer.
Change Request Number S A 96 .O Related SER SSER Section:
SER/SSER Impact N
Attachment to TXX 98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT- 95 DETAILED DESCRIPTION Prefix Page Page 204 f as amendssD Qwyn Description Section.
M2- 0236 -A 2 (F9.3-6)
Figure A drain hub is being installed in a floor drain line to accommodate the drain from the flash tank.
Revision See Justification of change for M2-0206-01, Change Request Number SA 20 .4 Related SER SSER : Section:
SER/SSER Impact N M2- 0239 3 (F10.4 10) l'igure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Steam Generator lilowdown Cl;canup System figure to indicate flow to Secondary Sampling System. See Description on pp.10.4-132 and 134 Charoe Request Number SA 96 0 Related SER , SSER - Section:
SER/SSER Impact N M2- 0241 3 (F9.2 5)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addition Revised Demineralized and Reactor Makeup Water figure to indicate flow to Secondary Corrosion Product Monitors 1-02 and 2-02. Four (4) Corrosion Product Monitors and two (2) Local Dissolved Oxygen Analyzers have been permanently installed to provide for improved secondary side sampling capability. Corrosion Product Monitoring and Dissolved Oxygen control is 4
essential for secondary side chemistry which is conducive to preserving secondary side components from accelerated aging and premature replacement.
Corrosion product monitor components require a sample temperature of around 100 degrees F. The Steam Generator Illowdown, Feedwater and lleater Drains samples will require cooling tu meet the reduced sample temperature requirements.
Change Riquest Number SA 96 .O Related SER - SSER. Section:
SER/SSER Impact N
Attachrnent to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT AMENDMENT. 95 DETAILED DESCRIPTION Prefix Page Page 205 (as amended) Group Descrintion Section.
M2- 241 2 (F9.2-5)
Figure The Unit 2 Reactor Water Makeup pump miniflow line and recirculation line is being increased from I inch to 2 inch.
The flow restriction orifice is being relocated from the discharge of the Reactor Water Makeup Pump to the applicable supply lines.
Revision See change request number SA 96-56.2 on page 9.2-38 for additional information.
Change Request Number SA 56 ,3 Related SER , 9.2.3 SSER : Section:
SER/SSER 1mpact N M2- 0242 3 (F9.2-5)
Figure Addition of Secondary Corrosion Product Monitors and Local Dissolved Oxygen Analyzers.
Addnion Revised Demineralized and Reactor Makeup Water figure to indicate flow to Secondary Corrosion Product Monitors 1-02 and 2-02. Four (4) Corrosion Product Monitors and two (2) Local Dissolved Oxygen Analyzers have been permanently installed to provide for improved secondary side sampling capability. Corrosion Product Monitoring and Dissolved Oxygen control is essential for secondary side chemistry which is conducive to preserving secondary side components from accelerated aging and premature replacement.
Corrosion product monitor components require a sample temperature of around 100 degrees F. De Steam Generator 11 lowdown, Feedwater and IIcater Drains samples will require cooling to meet the reduced sample temperature requirements.
Change Request Number S A 96 ,0 Related SER . SSER Section:
SER/SSER impact N M2- 0301 -A 2 (9.4-6)
Figure- Revise 10 inch containment penetration from " Spare"to " Containment Leak Rate test Depressurization" penetration.
Revision The containment penetration is being changed for use during ILRT and for cable feed thru during normal plant outage activities.
Change Request Number SA 31 .O Related SER SSER Section:
SER/S3ER Impact N
_ . . - - . _ _ . ._.-__ _..m._... . - - _ . . _ _ . _ _ _ _ _ . _ . _ . .- - . _ . _. _ .._ ..
I 1 Attachment to TXX-98015 CPSES - UPDATED FINAL SAFETY ANALYSIS REPORT .
AMENDMENT- 95 ,
DETAll.ED DESCRIPTION Prefix Page Page 206 8- f as amended) fknya Descripl10D Section.
M2- 0301 -A 2 (F9.4-6) '
~Figure . Revise to include a blind flange on the outboard containment isolation valve
]
for containment penetratiom MV 0001 and MV 0002.
Revision Provides for the installation of ASME code class blind flanges outside i ' containment to seal off the penetration to support 1.LRT as an acceptable substitute for the outside containment valve.
Chango Request Number SA - 96 ~- 74 ,0 Related SER : SSER : Section: ,,
SER/SSER impact N 'i i
M2- 304 4 (F9.4 1)
Figure Add Digital Control Room Air-conditioning Unit and Roof Ventilators for the Main Feed Pumps area.
- Correction See description for Page 9.4 26.
Change Request Number SA -% -3 ,2 Related SER : 9.4 SSER : Section:
SER/SSER Impact N M2- 0311 3 Figure Adds UPS and Distribution Rooms Fan Coil Units to the Safety Chilled Water System.
Correction Secjustification for FSAR Section 9.4C (Page 9.4C-12).
Change Request Number SA 150 . 4
'~
Related SER : 9.4.6 SSER : 22 Section: 9.4.6 SER/SSER Impact N .
W 4
r'
' I nummmmmmme
==
Log # TXX-88467 C. - = File #~10010 m C C Ref 10CFR2.102(a) 1UELECTRIC wn. c.co a t,<< < n > , era,+
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446 EVALUATION OF CHANGES TO FINAL SAFETY ANALYSIS REPORT REF: Letter from Stewart D. Ebneter (NRC) to William G. Counsil (TV Electric) dated May 17, 1988 Gentlemen:
In the referenced letter, the NRC Staff-informed TV Electric that it was preparing to resume active review of the amendments to the Comanche Peak Steam x
( Electric Station Final Safety Analysis Report (FSAR). To assist the NRC Staff in planning and scheduling its review, the Staff requested that TV Electric identify portions of the FSAR which were previously evaluated and found acceptable in the Staff's Safety Evaluation Report (SER), or supplements thereto (SSERs), and for which the licensing basis was changed by FSAR amendments after Amendment 54. The response should identify and summarile the nature of the FSAR changes since SSER No. 12 was issued. In addition, the Staff requested that TV Electric evaluate each FSAR change with respect to the overall safety of the facility and broadly categorize each change based on the safety significance determined by the evaluation, in _ response to the NRC Staff's request TU Electric _has undertaken a comprehensive update and review of the FSAR and screening of the FSAR changes.
As a result of this effort, TU Electric has prepared a detailed listing and description of every change to the FSAR that causes that document to differ from the version reviewed and accepted by the NRC Staff through SSER No. 12.
Further, all changes have been placed in one of four groups based upon their relative significcnce.
To briafly describe the process, TV Electric has identified every change to the FSAR text made .ince Amendment 54 and characterized each as one of six types:
o Revision: Provides changes to the design criteria, tne design basis, or to basic operational commitments.
%Wo@ovoir9 4* % ,
40 North Chw Street LR 81 ; Danes. Tens 73201
fxx 88467 June ', 1988 "
Page / of 4 o Addition: Adds a description of an Aspect of the CPSES design that was not previously described.
o Update: Provides new or expanded descriptions in areas which were designated "t.ater" in th0 past or which were expect *d to change with time ge.g. resumes),
o Correction: Provides changes to the technical description to match the as-built plant but does not change dedgn criteria or bases. Includes changes made to conform a section of the F5AR N a previous change in another section of the FSAR, Clarification: Provides a clearer description in an area where the pr6vious description could cause confusion or misinterpretation. No change in design or design criteria is intended, o Editorial: Makes corrections because of previous editorial errors or to conform the FSAR (e.g., index pages
( or cross-references) to reflect other changes.
(ach change was then evaluated for relative 1,ignificance. The evaluation aas made by utilizing based upon screening the concepts criteria embodied in 10specifically C.F.R 50.59 developed and 50.92(c by)TV
. It isElectric important to note that neither of these two regulations applies by their terms to the FSAR change review conducted by TV Electric. Nevertheless they provided useful guidance in establishing screening criteria for tne relative significance evaluation requested by the NRC Staff. The criteria were also intended to assure that all TV Electric reviewers from all the disciplines involved in the process applied a uniform screen. A description of the screening criteria is provided as Attachment 1 to this letter.
It should be emphasized that, prior to submittal of each FSAR change, TU Electric had reviewed the technical merits of such change and had concluded that all aspects of the change satisfied applicable NRC requirements. None of the changes has " safety significance" in the sense that it would create a potentially unsafe situation, i.e., a facility not in compliance with MC requirements. The term " relative significance" as used in this revi* denotes only that the FSAR changes -- all of which are acceptable from a safety standpoint -- have been classified into groups, in increasing order of possible importance of the change to the NRC Staf f. The classification, which involved a number of subjective cnnsiderations, is intended only for purposes of aiding the Staf f in planning and scheduling its review.
(
)
i
( in.88467 >
! June 1, 1988 "
i Page 3 of 4 As can be seen from the criteria, the screening process resulted in each change being classified, in TV Electric's opinion, in one of the following four groups:
Group 4: These changes are not substantive and do not affect the Ilcensing basis previously evaluated and found acceptable by the NRC Staff.
Group 3: These changes are either clearly conservative with raspect 4
to the previous commitment or clearly f all outside the scope or intent of the NRC Staff's review under the
- Standard Review plant (SRP) (NUREG-08001 Thus they do
- not affect the licensing basis previously evaluated and -
! found acceptable by the NRC Staff.
- Group 2: These changes substantively modify descriptions and analyses in the FSAR but, in view of the screening criteria applied, are less likely to require detailed NRC Staff review than the changes in Group 1. -
(( Group 1: These changes substantively modify descriptions and analyses in the FSAR, and for the NRC Staff's planning and scheduling purposes, are likely to require detailed NRC Staff review. These have been fully addressed by TV i Electric to demonstrate compliance with applicable NRC requirements.
The results of this effort are provided in Attachment 2. In preparing the i data, we have identified all changes to the CPSES FSAR from Amendment 55 through Amendment 68 inclusive, and sorted the changes by applicable SER section. The cha1ges within each SER section are listed in accordance with TV Electric's " significance" group . Finally, at the end of each Chapter, two tables are provided to facilitate the Staff's review. The first table indicates the TV Electric evaluation of the relative signif' ance of the changes as they affect specific SER sections. The second table lists repetitive entries which require only a single review.
Descriptions.for Amendment 69 and 70 were provided in letters dated March 18, 1988 (ixx-88248) and April 22, 1988 (TXX-88359), respectively. These descriptions did not include the significance evaluation (i.e., the group classification). Revised descriptions which include the group classtfications for Amendment 69 and 70 will be submitted by June 20, 1988. A description for FSAR Amendment 71, including the results of the significance evaluation, was suomitted on May 27,1988(TXX-88445).
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TxX-88467 C June 1, 1988 Page 4 of 4 The referenced le ter indicates that the NRC intends to review these FSAR amendments against the licensing criteria in the current version (May 1988) of the Standard Review Plan (SRP), NUREG-0800. As noted in your letter, the CPSES OL application was tendered prior to the issuance of the SRP. Per 10 CFR 50.34(9), the SRP is not applicable to the CPSES OL application.
However, we will be pleased to continue to cooperate in the NRC Staff's review in accoidance with all pertinen* regulations and procedures.
Please let us know if we can provide any further information to facilitate the Staff's planning and scheduling of its review.
Very truly yours, W. G. Counsil
/' M4 By:%./0.( a1ker
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Mana r, Nuclear Licensing BSD/amb attachments c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)
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