AECM-87-0019, Forwards Summary Rept of Safety Evaluations Conducted as Result of Updated FSAR Change Notice Review Program,Per Util 860410 Response to Violation 50-416/86-02-01

Forwards Summary Rept of Safety Evaluations Conducted as Result of Updated FSAR Change Notice Review Program,Per Util 860410 Response to Violation 50-416/86-02-01

ML20211F253
Person / Time
Site:	Grand Gulf
Issue date:	02/18/1987
From:	Kingsley O SYSTEM ENERGY RESOURCES, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AECM-87-0019, AECM-87-19, NUDOCS 8702250022
Download: ML20211F253 (178)

Text

EVETEM ENERGY REEDURCEE,INC.

O_.vtp D KfGLEY,JR vcenescen, February 18, 1987 ewea cwo ons U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Report of Safety Evaluations as a Result of the UFSAR Change Notice Review Program AECM-87/0019

References:

1) AECM-85/0307, dated December 1, 1985

2) AECM-86/0089, dated April 10, 1986

3) AECM-86/0362, dated November 26, 1986

4) AECM-86/0382, dated November 26, 1986 In accordance with the MP&L (SERI) response to NRC Violation 50-416/86-02-01 (reference 2), SERI is submitting a summary report of those safety evaluations conducted as a result of the UFSAR Change Notice Review (UCNR) program for changes made to the initial submittal of the GGNS UFSAR dated December 1, 1985 (reference 1).

The UCNR program resulted in 233 safety evaluations that were conducted and approved through GGNS PSRC. The summaries of these safety evaluations are contained in either this report or the previous 10CFR50.59 safety evaluation report submitted to the NRC on November 26, 1986 (reference 3). Attachment 1 contains a summary of the safety evaluation description and result of the UCNR safety evaluation which are being reported in this submittal. In response to Violation 86-02-01, these summaries also contain a notification of whether or not a " Facility Description Change" is associated with the safety evaluation.

Per MP&L (SERI) UCNR procedure a Facility Description Change is "an apparent change to the FSAR description of the plant design (or to FSAR statements of conformance to standards, codes or analyses pertaining to plant design) which was not otherwise supported by a previous 50.59 evaluation or other exclusion criteria established by this procedure."

As a matter of completeness, attachment 2 contains a listing of UCNR safety evaluations previously reported in reference 3. This listing provides the GGNS safety evaluation number, the identification number (SRASN No), and a dotermination of Facility Description Change.

C1CRMo0RL 870N8' e ,

EijiI hDOCK 05000416 a UDR n l mn ~ aw ww l swww n , , .~ ~ , n - 4, []

J12AECM87012101 - 1 Ig

AECM-87/0019 Page 2 As a result of the UCNR program, SERI also identified certain safety evaluations conducted which were not previously determined to be reportable for UFSAR Revision 0 changes. These safety evaluations are contained in Attachment 3.

As a result of the UCNR safety evaluations conducted, no unreviewed safety questions were identified, and no Technical Specification changes were directly required. However, as indicated in our letter dated November 26, 1986 (reference 4), a proposed Technical Specification change to the Unit I reactor pressure vessel's pressure-temperature operating map was identified as an indirect result of the UCNR review process. The proposed change was submitted for NRC review and approval in AECM-86/0351.

Based on the UCNR program and the corrective actions for compliance to

, Violation 86-02-01, SERI has established an overall GGNS Nuclear Production Department requirement for conducting safety evaluations on UFSAR changes.

Future safety evaluations for these changes will be incorporated in the routine summary reports submitted in accordance with 10CFR50.59(b).

Yours t ly, ODK:rg .

Attachments ,

cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Dr. J. Nelson Grace, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 J

f J12AECM87012101 - 2

L i

ATTACHMENT 1 SAFETY EVALUATIONS CONDUCTED FOR THE UFSAR (REV. 0) CHANGE NOTICE REVIEW PROGRAM l

l t

k J19ATTC86123001 - 172

Attachment to AECM-87/0019

SRASN: NPE-86-056 DOC N0: CN-3227-CUCNR0116 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Tables 8.3-6 and 8.3-7 were revised to_ reflect the load requirements of the uninterruptable power

' supplies, _ and to reflect new values for the load requirements resulting'from revised calculations. Also, loads required for the RCIC air compressor and DG fuel oil pump were deleted from

.the tables.

REASON FOR CHANGE: To reflect the current 125 VDC plant requirements.

SAFETY ~ EVALUATION: Although system loads were modified, the use of Class 1E equipment and isolation devices ensures that accident possibilities and malfunction consequences remain bounded by existing analyses. No unreviewed safety question or Technical Specification change was identified for_this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 1

Attachment to AECM-87/0019 SRASN: NPE-86-057 DOC N0: CN-3419-CUCNR0104 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 10.4.5.3 was revised by incorporating a discussion of an evaluation of the postulated failure of both the Unit I and Unit 2 circulating water systems.

The change addresses the location of safety related equipment in tne affected areas and the required action to be taken prior to filling the Unit 2 circulating water system.

REASON FOR CHANGE: To update the FSAR and to provide consistency with the Circulating Water Flooding Evaluation.

SAFETY EVALUATION: This change to the FSAR does not increase the probability of an accident; it does not increase the consequences of an accident; and it does not create the possibility of a new accident different from those previously evaluated. No Technical Specification change or unreviewed safety question was created by this change.

FACILITY DESCRIPTION CHANGE: Yes i

i

! J19ATTC86123001 - 2 1

Attachment to AECM-87/0019 SRASN: NPE-86-058 DOC N0: CN-3283-CUCNR0059 SYSTEM: N/A DESCRIPTION OF CHANGE: This change incorporates into Table 3.2-4 of the UFSAR the use of the 1977 Edition through Winter 1979 Addenda of ASME Section III, Subsection NC and ND, Paragraphs NC/ND-3647 and NC/ND-3658 as required by NC/ND-3671-1 for the analysis of Class 2 and Class 3 flanged joints in piping systems.

REASON FOR CHANGE: To allow the use of analytical methods not available in earlier editions of the ASME Section III Code.

SAFETY EVALUATION: The design criteria for piping analysis are not addressed in Technical Specifications. This change uses analytical methods for Class 2 and Class 3 flanged joints which were not available in previous ASME Code Editions. The new Code Edition has been approved for use by the NRC. The structural integrity of any system or of flanrad joints and other components is not affected. There is no functional or operational effect on any plant system. No Tech. Spec. change or unreviewed safety question was created by this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 3

Attachment to AECM-87/0019 SRASN: NPE-86-059 DOC NO: CN-3229-CUCNR0041 SYSTEM: N/A DESCRIPTION 0F CHANGE: This change revised the FSAR as follows:

In subsection 6.2.3.2, delete the "4 inch condensate and refueling water supply" line from the list of secondary penetrations having a single, fail-closed air-operated isolation valve; and in Table 7.6-12 indicate that the pilot valves for A0V E12-F203 are powered by separate ESF systems. This reflects no change or modification to the plant.

REASON FOR CHANGE: To correct errors in the FSAR, and to reflect in the UFSAR a condition actually existing in the plant.

SAFETY EVALUATION: The line deleted from Section 6.2.3.2 is correctly described in Table 6.2-42. Design documents indicate pilot valves are currently powered by separate ESF systems.

There is no effect on Technical Specifications. The changes correct errors and do not reflect modifications or design changes to the plant. Consequently there is no increase in the pro'aability or consequence of an accident or of a malfunction of equipment important to safety, nor is the possibility of a new accident or malfunction created.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 4

Attachment to AECM-87/0019 SRASN: NPE-86-060 DOC N0: -CNs 3262,3264,3331-CUCNR0049 SYSTEM: N/A '

DESCRIPTION OF CHANGE: Incorporate Code Cases N-71-8, N-71-9, N-71-10, N-249-1, N-249-2, and N-247 into Tables 3.9-28 and 5.21. Add Note (2) to Table 3.9-28 to incorporate information pertaining to the use of Code Case N-242.

REASON FOR CHANGE: All Code Cases utilized at the facility are required to be listed in Tables 3.9-28 and 5.2-1.

SAFETY EVALUATION: Design criteria as related to the use of Code Cases are not addressed in Technical Specifications. The Code Cases addressed by this change have been approved by the ASME and comply with ASME Section III requirements. The NRC has approved the use of these Code Cases. The use of these Code Cases introduces no new failure mode and does not affect the margin of safety. Nor is there any increase in the probability or consequences of an accident, or of a malfunction of equipment important to safety.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 5

Attachm:nt to AECM-87/0019 SRASN: NPE-86-061 DOC N0: CN-3449-CUCNR0048 SYSTEM: E12 DESCRIPTION OF CHANGE: This change deleted a reference to " core

. spray" in a discussion of RHR Steam condensing in Section 5.4.7.1.1.5; and deletes a reference to " low resistance" in the discussion of RHR minimum flow in Section 5.4.7.1.2.

REASON FOR CHANGE: The reference to " core spray" in Section 5.4.7.1.1.5 is incorrect because the RHR system does not have a core spray mode. - The deletion of " low resistance" provides clarification that the orificed line may not always provide low resistance.

SAFETY EVALUATION: These changes reflect actual design conditions and reflect no changes to existing plant or system configuration. They correct errors in the FSAR as well as provide minor clarification to it. No unreviewed safety question is created, nor is there any impact on Technical Specifications.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 6

Attachment to AECM-87/0019 SRASN: NPE-86-062 DOC N0: CN-3338,3485-CUCNR0033 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 5.4.6.2.1.1 and 5.4.6.2.2.2.a .were revised to reflect: (1) the correct RCIC suction source, (2) RCIC suction in the steam condensing mode of operation, (3) that condensate is drained from the RCIC turbine exhaust line during standby conditions only, and (4) RCIC rump flow is 825 GPM. A new section, 5.4.6.2.2.2.1, was added to the FSAR stating that the RCIC instrumentation trip settings and setpoints are provided in the plant Technical Specifications.

REASON FOR CHANGE: To provide clarification and correct minor errors in the UFSAR.

SAFETY EVALUATION: There was no change to equipment or system operation contrary to the GGNS Technical Specifications. This change did not involve a Technical Specification change or an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes 1

r l

J19ATTC86123001 - 7 L

Attachment to AECM-87/0019 SRASN: NPE-86-063 DOC NO: CN-3437-CUCNR0022 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table A-10 of Appendix 6A was revised to reflect corrections to several of the values listed specifically for Grand Gulf including suppression pool depth and volume, drawdown makeup volume (upper pool dump volume) and vent volume.

REASON FOR CHANGE: To correct minor errors and to provide consistency with the Technical Specifications and other design documents.

SAFETY EVALUATION: This change did not affect previously analyzed accidents or equipment performance. No unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 8

Attachment to AECM-87/0019 SRASN: NPE-86-064 DOC N0: CN-3145,3165-CUCNR0007 SYSTEM: E22 DESCRIPTION OF CHANGE: FSAR Figure 6.2-77 was revised by the correction of valve numbers, and by the deletion of a portion of a SLC System Line that was never installed. Figure 6.3-1 was revised by the deletion of a limit switch on Valve E22-F240.

REASON FOR CHANGE: To reflect the correct as built design and to provide consistency with other design documents.

SAFETY EVALUATION: This change to the text of the FSAR did not involve any physical changes to .the facility or operation of the plant. The Technical Specifications are not affected by this change and there is no adverse effect on the operability of the plant. No unreviewed safety question was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes t f 9

f f

4 J19ATTC86123001 - 9

. _ . _ _ ._ _ _ _ - ._ --_ ___--_. _ . ~ - _ - - - - - - _ _ _ _ _ . _ - _ _ _ _ . . - ..

Attachment to AECM-87/0019 SRASN: NPE-86-065 DOC N0: CN-3164,3195-CUCNR0001 SYSTEM: VAR.

t DESCRIPTION OF CHANGE: FSAR Figures 5.4-16 & 17 and 6.3-1 & -4 were revised by the deletion of pump suction strainers in the RHR, LPCS and HPCS systems, i

REASON FOR CHANGE: To reflect the current plant configuration and to meet the original design requirement which was to replace the startup strainers with ring spacers.

SAFETY EVALUATION: This change to the FSAR did not affect the oparability of any system and reflects compliance with the criginal design. No unreviewed safety question or Technical Specification change was identified for this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes i

(

+

i r

J19ATTC86123001 - 10

Attachment to AECM-87/0019 SRASN: NPE-86-066 DOC N0: CN-3354-CUCNR0119 SYSTEM: VAR.

DESCRIPTION OF CHANGE: These changes consist of corrections and clarifications to the FSAR, and also include changes to reflect completed work and analyses concerning the failure mode analysis for pipe breaks and cracks.

REASON FOR CHANGE: To update the UFSAR Appendix 3C to reflect current stress analysis and corrections determined by the results of the final examinations.

SAFETY EVALUATION: These changes are not addressed in Technical Specifications. The evaluations for the changes were performed using existing criteria presented in the UFSAR. The analyses for these changes are based on existing plant configuration and show that the effects of postulated pipe breaks will not damage function or necessary component operability. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 11

L-Attachment-to AECM-87/0019' SRASN: NPE-86-067 DOC N0: -CN-3399-CUCNR0043 SYSTEM: N/A

-DESCRIPTION OF CHANGE: Revise UFSAR Sections 9.5.2.1.1 and 9.5.2.2.3 to reflect the fact that during normal plant operation communication with offsite agencies is accomplished via a recently installed microwave radio link and not a transmission carrier current link as stated in the FSAR. The microwayo link is an improved, more dependable communications link.

REASON FOR CHANGE: To update the UFSAR to reflect current plant configuration.

SAFETY EVALUATION: This change has no effect on Technical Specifications. It is only an FSAR change to communications systems and has no effect on any plant equipment or the plant itself. The microwave link is more reliable than the earlier transmission carrier current link. This change has no effect on the probability or consequences of an accident or of the malfunction of equipment important to safety. The margin of safety is not reduced. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes l J19ATTC86123001 - 12

Attachment to AECM-87/0019 SRASN: NPE-86-068 DOC N0: CN-3434-CUCNR0151 SYSTEM: B21 DESCRIPTION OF CHANGE: This change revised the description of indications for reactor shutdown: 1) to state that the control rod status lamps are powered by the Uninterruptible Power Supply (UPS), rather than the AC instrument bus, and 2) to state that the Reactor Protection System (RPS) Motor Generator (MG) sets must be switched to alternate and reset following a loss of offsite power.

REASON FOR CHANGE: To reflect current plant design.

SAFETY EVALUATION: Control Rod Status Lamp power supplies are not addressed by Technical Specifications, and this change has no effect on Technical Specifications. Accident probabilities remain bounded by the AC instrument bus, because the indicators with the UPS will not be lost while they would have been lost with the loss of the AC instrument bus. No equipment or systems important to safety are affected by this change. Technical Specification safety margins are unaffected. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes

\

d l

[

Y

)

J19ATTC86123001 - 13 ?, /

i

Attachment to AECM-87/0019 SRASN: NPE-86-069 DOC N0: CN-3393-CUCNR0153' SYSTEM: VAR.

DESCRIPTION OF CHANGE: This change revised FSAR Section 8.3.1.1.4.lf(5) to include Control Room annunciation of " Diesel Generator Engine Bearing Temperature High", and " Diesel in Maintenance Mode".

REASON FOR CHANGE: To enhance safety by providing additional information on the status of the Emergency Diesel Generators in the Control Room.

SAFETY EVALUATION: These are additional annunciator points and have no effect on plart systems, equipment, or the Technical Specifications, because sufficient isolation of the annunciators from plant equipment exists to ensure that annunciator malfunction cannot affect anything else. Should another type of accident occur, the additional operator information provided by this change will aid to minimize the consequences. There is no impact on the margin of safety. Therefore no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 14 1

Attachment to AECM-87/0019 SRASN: NPE-86-070 DOC N0: CN-3235-CUCNR0114 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 9.3.2.2.4 was revised by the addition of a new paragraph stating that the power supply to the Post Accident Sampling System is from a Class IE Motor Control Center. This MCC is tripped upon receipt of an accident signal, but can be reset locally.

REASON FOR CHANGE: To provide a current and correct description of the as built system.

SAFETY EVALUATION: The change to the FSAR did not alter the Technical Specifications; did not affect any previously analyzed accident; and did not affect equipment performance. No unreviewed safety question was identified for this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 15

e Attachment to AECM-87/0019 SRASN: NPE-86-071 DOC N0: CN-3138-CUCNR0113 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Figure 8.3-7 was revised to show that the power feed for the NSSS computer cassette, typer, and programmer CRT are located on disconnect switches rated at 30 amps and fused at 14 amps.

REASON FOR CHANGE: To provide a current and correct description of the power distribution panels on the figure.

. SAFETY EVALUATION: Use of the more appropriate disconnects and fuses provide increased reliability of the power supply. Loss of the subject loads will not affect accident consequences. The consequencesLof previously evaluated malfunctions is not altered by this change. No unreviewed safety question or Technical Specification change was identified for this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 16

Attachment to AECM-87/0019 SRASN: NPE-86-072 DOC NO: CN-3391-CUCNR0103 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 2.2-4 " Chemicals Stored Onsite", was deleted ir. f ts entirety and Section 2.2.2.2 was changed by deleting th,e reference to'the table.

REASON FOR CHANGE: .The table is not required by the Standard Review Plan nor the Standard Format; and, the difficulty of maintaining the table which was not limited to hazardous chemicals justified its deletion.

SAFETY EVALUATION: This change to the FSAR does not affect any plant equipment, nor accident analyses. No safety concern was identified and there were no unreviewed safety questions or Technical Specification changes associated with this change.

Hazardous chemicals are addressed separately so the deletion of this table does not pose the threat of neglecting needed hazardous chemical analyses.

FACILITY DESCRIPTION CHANGE: Yes l

J19ATTC86123001 - 17 l

Attachment to AECM-87/0019 SRASN: NPE-86-073 00C N0: CN-3391-CUCNR0102 SYSTEM: N/A DESCRIPTION OF CHANGE: This change deletes reference to anhydrous ammonia storage tanks which have been removed (offsite) and added potentially hazardous materials stored on site which have been analyzed for consequences during an accident. Surveys were conducted to verify accuracy of references to industries in area (Section 2.2.2.6). Hazardous materials added are acetone and sulfuric acid which are stored in the yard.

REASON FOR CHANGE: To bring the UFSAR up to date with current plant hazardous chemical storage practices.

SAFETY EVALUATION: There is no impact on Technical Specifications, or on accident analysis or on plant equipment.

No accidents of a different type from any previously evaluated were identified. Therefore, no unreviewed safety questions or Technical Specification change was identified by this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 18

Attachment to AECM-87/0019 SRASN: NPE-86-074 DOC N0: CN-3479-CUCNR0028 SYSTEM: VAR.

DESCRIPTION OF CHANGE: Remove sentence addressing concrete shield wall thickness from FSAR Subsection 12.3.1.1.2. This FSAR Subsection addresses common facility and layout designs for ALARA concerns.

REASON FOR CHANGE: This change deletes a sentence which is unnecessary because the radiation zones, which are based on shield wall thicknesses, are referenced in this subsection and in Figures 12.3-21 through 12.3-27.

SAFETY EVALUATION: Technical Specifications do not address concrete shield wall thickness.' No changes have been made in the plant, in plant design, or in the basis for ALARA. There is no impact on equipment operability. No Technical Specification change or unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: No

'l J19ATTC86123001 - 19

Attachment to AECM-87/0019 i

SRASN: NPE-86-075 DOC N0: CN-3144-CUCNR0112 SYSTEM: PS2,P53 DESCRIPTION OF CHANGE: This change revises FSAR Figures 9.3-1 and 9.3-3 to show valve positioner symbols on valves PS2-FCV-F507A, F5078, F508A, F5088; P53-FCV-F511 and F520.

REASON FOR CHANGE: These drawing changes are for the purpose of making the FSAR consistent with as-built plant configuration.

SAFETY EVALUATION: These changes are drawing changes to bring UFSAR Figures to the Original design. There is no change in hardware or in any plant system. There is no effect on Technical Specifications. No new failure mode is created, nor is there any reduction in the margin of safety. Therefore, no unreviewed safety question is created.

FACILITY DESCRIPTION CHANGE: Yes i

+

J19ATTC86123001 - 20

Attachment to AECM-87/0019 SRASN: NPE-86-076 DOC N0: CN-3319-CUCNR0081 SYSTEM: E61 DESCRIPTION OF CHANGE: This change revises Table 7.5-1, sheet 3 of 5, to show the addition of hydrogen igniters which are part of the Combustible Gas Control System. This change is in agreement with Technical Specifications Table 3.6.7.2-1.

REASON FOR CHANGE: This change makes the UFSAR Table consistent with other UFSAR material including Figure 7.5-3 and reflects the current plant configuration.

SAFETY EVALUATION: This change is consistent with the Technical Specifications. It simply corrects the FSAR description. It does not degrade the Combustible Gas Control System or prevent action described in FSAR Chapter 15 " Sequence of Events" Tables for accidents analyzed. The change reflects current plant configuration. The margin of safety is actually improved since the system will ensure combustion of hydrogen as described in the Bases to the Technical Specifications.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 21

Attachment to AECM-87/0019 SRASN: NPE-86-077 DOC N0: CN-3199-CUCNR0142 SYSTEM: N/A DESCRIPTION OF CHANGE: This change revises FSAR Figure 9.5-5 to (1) show valve F467 as " locked open"; (2) assign MPL numbers to valves FB34 and FB35; and (3) show the C0 2 line to the electromanual pilot control operator (EMPC) on valve F373 and sensing line. This modifies the drawings to reflect final designed component arrangement.

REASON FOR CHANGE: To reflect correct as built configuration in the UFSAR.

SAFETY EVALUATION: Technical Specifications are not affected by this change. This change reflects system design and as-built conditions, and it picks up a previously undepicted CO 2 supply / control line. The " lock open" capability of valve F467 provides assurance that F373 will have adequate gas to actuate.

No unreviewed safety question was created by this change.

FACILITY DESCRIPTION CHANGE: Yes 1

J19ATTC86123001 - 22

Attachment to AECM-87/0019.

't SRASN: NPE-86-078 DOC NO: CN-3322-CUCNR0120 SYSTEM: VAR.

DESCRIPTION OF CHANGE: This change provided clarification of the actual criteria used in the determination and dynamic effects of pipe breaks. .This change revised Sections 3.6A.1, 3.6A.2 and associated tables.

, REASON FOR CHANGE: To update the described sections to reflect current stress analysis and make corrections determined by the results of the final postualted pipe break evaluations. ,

1 SAFETY EVALUATION: The criteria involved in this change notice are not addressed in Technical Specifications. This change'does not change the physical plant configuration. The evaluation and analysis were performed using the existing criteria presented in the FSAR and still show that the effects of pipe breaks will not damage essential items to an extent that would impair their design function or necessary component operability. There is no unreviewed safety question created by this change.

FACILITY DESCRIPTION CHANGE: Yes 4

l JI9ATTC86123001 - 23

-- .__ __, ._ - . _ - _ . . _ _ _ ..-_.._______a_._. _ _ - _ - _ . _

Attachment to AECM-87/0019 SRASN: NPE-86-079 DOC N0: CN-3473-CUCNR0084 SYSTEM: N/A DESCRIPTION 0F CHANGE:

In UFSAR Section 5.3.1.5.1, this change deleted subparagraph 1) which makes reference to the General Electric Licensing Topical Report NE00-21778-A and the exception to 10CFR50 Appendix G (prior _to May 1983). References to NED0-21778-A were also deleted in Paragraph E and Section 5.3.2.1.

REASON FOR CHANGE: In May, 1983, 10CFR50 Appendix G was revised to incorporate the proposed modification as presented in NED0-21778-A. Therefore, the FSAR will be in compliance with 10CFR Appendix G and the references should be deleted.

SAFETY EVALUATION: This change does not change the pressure RPV temperature curves or any other .10CFR50 Appendix G requirement mentioned in the current Technical Specifications. The needed Technical Specification changes associated with this change to Appendix G were made in 1984 as a part of the GGNS Technical Specification Review Program. Because no hardware change was made, this change will not. increase the probability or consequences of an accident or malfunction of equipment important to safety. No possibility of a new accident or malfunction is created. .There is no effect on the margin of safety.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 24

Attachment to AECM-87/0019 SRASN: NPE-86-080 DOC N0: CN-3414-CUCNR0149 SYSTEM: E61 DESCRIPTION OF CHANGE: This change reduces the time before the hydrogen recombiners would be required from 6.02 days to 5.8 days. The recombiners are manually initiated from the Control Room whenever the hydrogen gas concentration reaches 3.5% by volume. Following an accident, this prevents hydrogen gas concentration from exceeding 4% by volume.

REASON FOR CHANGE: As per Design Change Package 82/574, the flow rate of the drywell purge compressors was reduced to 1000 CFM.

Due to this decrease, the time before the hydrogen recombiners would be required to be initiated was reduced.

SAFETY EVALUATION: The calculated time at which recombiners will be required is not addressed in Technical Specifications. The reduced hydrogen recombiner time has no effect on any accident analysis. The recombiners are qualified to operate following a design basis accident. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 25

Attachment to AECM-87/0019

~SRA'a: NPE-86-081 ~DOC N0: CN-3191-CUCNR0078 SYSTEM: N/A DESCRIPTION 0F CHANGE: FSAR Table 9.3-3 was revised to show that the post-accident sample connection is from reactor recirculation loop A instead of loop B.

REASON FOR CHANGE: To provide consistency with design drawings.

SAFETY EVALUATION: This change affects FSAR Table 9.3-3 only.

There is no change to the design, operation, or physical configuration of the plant. The change does not affect any accident previously analyzed and does not impact equipment performance. No unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 26

Attachment to AECM-87/0019 SRASN: NPE-86-082 DOC N0: CN-3189-CUCNR0068 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 9.2.2.2 was revised by changing the maximum operating conditions for the Component Cooling Water (CCW) System fran 110 psig/185 degrees F to 120 psig/180 degrees F. Table 9.2-7 was also revised by changing the CCW pumps TDH from 119 ft. to 150 ft.

REASON FOR CHANGE: To correct the FSAR and reflect as-built conditions.

SAFETY EVALUATION: This change to the FSAR does not alter the system design, plant configuration, or plant operation. No physical change to the plant was made. There was no effect on accident analyses nor equipment performance, and no unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 27

Attachment to AECM-87/0019

.SRASN: NPE-86-083 ~ DOC N0: CN-3261-CUCNR0067 SYSTEM: N/A DESCRIPTION 0F~ CHANGE: FSAR Sections 9.5.9.1.2, 9.5.9.2.1, and 9.5.9.5 were-revised to describe a reboiler-subsystem added to the Auxiliary Steam System. Figure 9.5-20a was added to provide a P&ID of the reboiler subsystem..

REASON FOR CHANGE: To reflect the as-built condition of the facility and the addition of the reboiler.-

SAFETY EVALUATION: The Auxiliary Steam. System s'erves no safety

' function and is installed in the Unit I turbine building.

Failure of the system will not compromise any safety-related system or component. The change to the FSAR did not result in the identification of a Technical Specification change or an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 28

Attachment to.AECM-87/0019

-SRASN: NPE-86-084 DOC N0: CN-3232-CUCNR0026 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Tables 3.8-17, 3.8-18, and 3.8-19 were revised to include the term 1.25C in the governing equation-1 loading combinations.

REASON FOR CHANGE: To reflect the load combination committed to .

in FSAR subsection 3.8.3.3.2.3.1.c.

SAFETY EVALUATION: The change to the FSAR does not affect the physical design of the plant. No Technical Specification change was identified and there was r.o unreviewed safety question-related to the change.

FACILITY DESCRIPTION CHANGE: Yes 1

J 4

J19ATTC86123001 - 29

Attachment to AECM-87/0019 SRASN: NPE-86-085 DOC N0: CN-3401-CUCNR0025 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 3.7.4.2.2 was revised to reflect which Peak Recording Accelerographs (PRA) are in place and those that will.be installed at a later date.

REASON FOR CHANGE: To provide an correct description of the PRAs that are installed.

SAFETY EVALUATION- This change to the FSAR did not affect the physical design of the plant. The PRAs are passive instruments and have no potential to increase the probability of an accident occurrence. No unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: No d

i t

t 6

f i J19ATTC86123001 - 30

Attachment to AECM-87/0019 SRASN: NPE-86-086 DOC N0: CN-3478-CUCNR0012 SYSTEM: N/A DESCRIPTION OF CHANGE: .This change revised Section 2.5.4.13.1 Table 2.5-10, and Figures 2.5-75a through 2.5-75h to provide the criteria for long term monitoring intervals of the building settlement - markers.

REASON FOR CHANGE: To provide criteria by which a program could be established for long term monitoring of the settlement markers.

SAFETY EVALUATION: Provision of the monitoring intervals after completion of construction on Unit I will ensure that cumulative building settlements are noted and evaluated. These intervals will help determine if excessive settlement is likely to occur and prevent settlement impact upon any GGNS design. Therefore, no Technical Specification change or unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: -No i

l l

f t J19ATTC86123001 - 31

Attachment to AECM-87/0019

~

SRASN: .NPE-86-087 . DOC N0: CN-3277-CUCNR0011 SYSTEM: VAR.

DESCRIPTION OF CHANGE: FSAR Table 6.2-44 was revised to reflect correct post-accident positions of several valves; i.e., the position reflected was changed from " closed" to " closed or open". For one valve the position reflected was changed from

'"open or closed" to'" closed".

REASON FOR CHANGE: To provide clarification, correct minor errors, and to provide consistency with other FSAR sections describing the post-accident functions.

SAFETY EVALUATION: No modifications were made to plant equipment or operation. The change reflects actual design conditions. No Technical Specification change or unreviewed safety question was identified for this charge.

FACILITY DESCRIPTION CHANGE: Yes l

J19ATTC86123001 - 32

Attachment to AECM-87/0019

' SRASN: NPE-86-088 DOC N0: CN3239-CUCNR0008. SYSTEM: E51 DESCRIPTION OF CHANGE: FSAR Figure 5.4-11 was revised to show RCIC drain valve E51-F004 as normally open and fail closed, and valve E51-F005 as normally closed and fail closed.

REASON FOR CHANGE: To provide consistency with existing design documents.

SAFETY EVALUATION: This change to the FSAR did not involve a change to the facility nor did it involve a change in the operation of the facility. The change did not involve an unreviewed safety question or Technical Specification _ change.

FACILITY DESCRIPTION CHANGE: Yes d

I J19ATTC86123001 - 33

. -. - _ = . .- . . , - , - -

Attachment to AECM-87/0019 SRASN: NPE-86-089 000 N0: CN-3349-CUCNR0141 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 3.11.4.5, 9.4.5.2.3, and 9.4.5.5.2 were revised to reflect that the two fans in Standby Service Water (SSW) Pumphouse A are supplied power from divisions I and II of Unit I instead of division I of Units 1 and 2.

REASON FOR CHANGE: To clarify the description of the Standby Service Water Pumphouse A ventilation system and to provide consistency with the information contained in Figure 9.4-9a.

SAFETY EVALUATION: This change to the FSAR reflects a change which only provides a redundant cooling system to the SSW pumphouse A which in turn increases the reliability of the HPCS system. The physical change did not alter the original ventilation system design capability of having two operable fans. There was no Technical Specification change or unreviewed safety question identified for this change.

FACILITY DESCRIPTION CHANGE: Yes 9

J19ATTC86123001 - 34

Attachment to AECM-87/0019 SRASN: NPE-86-090 DOC N0: CN-3339-CUCNR0062 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 15.4-1 was changed by revising the descriptions in the sequence of events and by reducing the elapsed time for the sequence of events from 60 seconds to 25 seconds.

REASON FOR CHANGE: To provide a more accurate description of the sequence of events during a rod withdrawal error.

SAFETY EVALUATION: This change does not affect the physical design of the plant, nor is there a change to the functional requirements of the existing design. The change only involves a description in the FSAR and does not involve an unreviewed safety question or Technical Specification change.

' FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 35

Attachment to AECM-87/0019

'SRASN: NPE-86-091 DOC N0: CN-3241-CUCNR0034 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 5.2.2.2.1 was changed to reflect that the REDY code was used to evaluate transients.

Section 15 was changed to reflect the purpose of the low-low set function of the Safety Relief Valves.

REASON FOR CHANGE: To provide clarification as to which computer code was used in.this application.

SAFETY EVALUATION: This change to the FSAR only provides clarification and does not create the possibility of an accident, and it has no impact on equipment performance. No Technical Specification change was identified for this char.ge, and there was no unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 36

~

Attachment to AECM-87/0019

~

SRASN: NPE-86-092 DOC N0: CN-3381,3433,3449-CUCNR0029- SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 5.4.7.2.2,'6.3.2.2.1, 6.3.2.2.3, and Appendix 6E were changed to reflect the addition of the NPSH calculations for the ECCS pumps in operational conditions 4 and 5. Section 6.3.2.2.4 was also revised by changing the description of.the flowpath for LPCI injection, and i .Section 6.3.2.2.1 was revised to correct the reference point for the HPCS pump NPSH.

REASON FOR CHANGE: To respond to an NRC request that the NPSH calculations be added to the FSAR and to provide clarification that the LPCI injection point is near the top of the core, as well as to correct the reference point for HPCS pump NPSH.

SAFETY EVALUAT:0N: This change to the FSAR simply adds information and clarifies a description. The change does not affect the Technical Specifications, and does not modify any equipment-or system function. No unreviewed safety question was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J

r l

L J19ATTC86123001 - 37

Attachment to AECM-87/0019 SRASN: NPE-86-093 DOC N0: CN-3272-CUCNR0140 SYSTEM: Z17 DESCRIPTION OF CHANGE: This change was to reflect in Section 9.4.10 Tables 1.10-1, 9.4-13, and Figures 9.4-16a and 9.4-16b the incorporation of two self-contained air conditioning (A/C) units into the computer room cooling system which is a part of the Control Building HVAC system.

REASON FOR CHANGE: These A/C units provide the: additional cooling necessary to meet the design requirements of the computer room.

SAFETY EVALUATION: The change was made to a non-safety related system which performs no safety-related function whose failure would not prevent safe reactor shutdown, and is connected to a non-safety related power supply. The addition of the two self-contained A/C units into the Control Building HVAC system has been evaluated for such hazards as flooding, water jet impingement, generation of new missiles and seismic II/I concerns. Potential flooding occurring in the computer room and flowing beneath the doors to the adjacent rooms was reviewed and determined that it would not affect any safety related equipment. No unreviewed safety question or Technical Specification change resulted from this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 38

Attachment to AECM-87/0019 SRASN: NPE-86-094 DOC N0: CN-3206-CUCNR0144 SYSTEM: P64 DESCRIPTION OF CHANGE: This change removes " position indication" and " lock open" symbols from valve NSP64F479 shown on Figure 9.5-8. This valve provides isolation capability of deluge water spray systems and a hose station at the Radial Well Switchgear House.

REASON FOR CHANGE: This change was necessary to make the Figure consistent with plant as-built conditions.

SAFETY EVALUATION: This change only incorporated the plant as-built configuration of the system onto the figure shown in the FSAR. During plant construction, the indicating post was removed to prevent impairment of the valve operator due to occasional flood water and floating debris. The only adverse affect that removal of the " lock-open" capability and post indicator on NSP64F479 would be the inadvertent closing of.this valve. If the valve remained closed and a fire broke out in the Radial Well Switchgear House, deluge water would not be readily available to subdue the fire. However, none of the components being protected by this fire water supply are safety-related or provide primary make up to reactor coolant and no radioactive systems are involved.

This change does not reduce the margin of safety or increase the consequences of an accident evaluated in the FSAR. Therefore, this change does not create an unreviewed safety question and does not change the Technical Specifications.

FACILITY DESCRIPTION CHANGE: Yes l

f-I i

l i

l J19ATTC86123001 - 39

Attachment to AECM-87/0019 SRASN: NPE-86-095 DOC NO: CN-3445-CUCNR0090 SYSTEM: N/A DESCRIPTION 0F CHANGE: FSAR Section 3.2.4.1.1 was revised by deleting " core support structure" from the definition of Safety Class 1 components and correctly specifying it as Safety Class 2.

The core support structure was correctly specified as safety class 2 in~FSAR T.*ble 3.2-1, so the change corrects an error.

REASON FOR CHANGE: To provide consistency with Table 3.2-1 which correctly specifies the core support structure as being Safety Class 2.

SAFETY EVALUATION: This change resolves an FSAR inconsistency and does not alter the design bases, configuration or operation of the fetility. No unreviewed safety question or Technical Specific 6 tion change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes s

\

i

,s*<

s J19ATTC86123001 - 40

e b Attachment to AECM-87/0019

. .r .

', SRASN: .NP$ 096 DOC N0: CN-3210-CUCNR0055 " SYSTEM: G33

/ ).

• c*y - .' ~

DESUtIPTION OF CHANGE: FSAR Table 3.9-3C was changed to correctly show valves G33-F051 and G33-F052A & B as simple check-

, valves.v Tbg table had listed the valves as motor operated check valves.-

• n./

, j. REASON-FOR CHANGE: . To provide consistency,with design documents.

' SAFETY EVALUATION: This change!does not iter the design or configuration of the system and there wasi.no phy'sical change to the plant. This change introduced'no unreviewed safety question or. Technical Specification change. '

FACILITY DESCRIPTION CHANGE: Yes

's 3

)

(

[

l 1

?

<?

/

l.

')

L g i

J19ATTC86123001 --41

.- - . . ~ ~ _ . .

m Attachment to AECM-87/0019 m

SRASN: NPE-86-097 DOC NO: CN-3319-CUCNR0150 SYSTEM: E61 4

DESCRIPTION OF CHANGE: FSAR Section 7.5.'1.7.8.2 was revised'by adding a statement'that operating lights indicate when~the -

hydrogen' igniter circuits are energized. Tables 8.3-1 and 8.3-2 were revised by deleting the listing of the power requirements for the Hydrogen Igniters, since the loads were previously reflected by the Power Panel transformer loading.

REASON FOR CHANGE: To update the FSAR so that it corresponds to the current design of the plant.

, SAFETY EVALUATION: This change to the FSAR did not affect previously analyzed accidents or equipment important to safety.

No Technical Specification change was identified for the change, and there was no unreviewed safety question identified.

FACILITY DESCRIPTION CHANGE: Yes 9

4 I

d 4

l

\

J19ATTC86123001 - 42

Attachment to AECM-87/0019 SRASN: NPE-86-098 DOC NO: CN-3214-CUCNR0134 SYSTEM: Z77 DESCRIPTION OF CHANGE: This change was to incorporate FSAR Figures 9.4-8a and 9.4-86 which reflect the modifications made to the Safeguard Switchgear and Battery Room Ventilation System to correct a low flow problem. The system was changed from two 100%

supply fans and two 100% exhaust fans to four 50% supply fans and four 50% exhaust fans.

l REASON FOR CHANGE: The text change for this modification was previously incorporated into the FSAR prior to the issuance of the operating license. This change incorporated the as-built figures into the FSAR.

SAFETY EVALUATION: The change does not add, delete, or modify any equipment nor does it alter any portion of the equipment physically or functionally from what was already described in the text of the FSAR. This change only incorporated as-built figures into the FSAR. No unreviewed safety question or Technical Specification change was identified as a result of this change.

FACILITY DESCRIPTION CHANGE: Yes L

l J19ATTC86123001 - 43

Attachment to AECM-87/0019 SRASN: -NPE-86-099 DOC N0: CN-3222-CUCNR0087 SYSTEM: 833 DESCRIPTION OF CHANGE: This change revised FSAR Section 5.2.3.5 to identify plans to implement Induction Heating Stress Improvement (IHSI) and improved ultrasonic examination procedures on recirculation piping welds. Table 5.2-4 was also corrected to show proper identification of reactor pressure vessel recirculation safe end material.

^

REASON FOR CHANGE: The change was done to include within the FSAR the method for minimizing and detecting leaks and cracks in recirculation piping at GGNS. The other change was the addition of information to correctly identify safe end material.

SAFETY EVALUATION: The changes identify improved materials, inspection procedures, and IGSCC mitigation techniques which does not change the intended function or integrity of the recirculation -

piping. This change does not involve an unreviewed safety question nor were any Technical Specification changes identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 44

Attachment.to AECM-87/0019

'SRASN: NPE-86-100 DOC NO: CN-3422-CUCNR0094 SYSTEM: 'N/A-DESCRIPTION OF CHANGE: .FSAR Section 11.4.1.1 was revised by the deletion of diatomaceous earth filtering media-as one of the specified wastes.for-processing by the solid radwaste system.-

REASON FOR CHANGE: To provide a correct description since the plant will be using other acceptable filtering media.

SAFETY EVALUATION: This change does not alter the design, configuration, or operation of the solid radwaste system. There was no effect on previously analyzed accidents or equipment performance. No Technical Specification change was-identified and there was no unreviewed safety question for this. change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 45

Attachment to AECM-87/0019 SRASN: NPE-86-101 DOC N0: CN-3351-CUCNR0138 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Figure 6.2-81 was changed to indicate that the seal water supply bypass valve for the containment purge compressor is normally closed.

REASON FOR CHANGE: To provide clarification and reflect the original system design.

SAFETY EVALUATION: This change to the FSAR did not result in the addition, deletion, or modification of equipment, nor was any portion of the system physically or functionally altered in any way. There was no unreviewed safety question or Technical Specifict. tion change identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 46

Attachment to-AECM-87/0019l SRASN: NPE-86-102 DOC N0: CN-3220-CUCNR0136 SYSTEM: .N/A w DESCRIPTION OF CHANGE: FSAR Figure 9.4-9b was ch'anged by adding room numbers and by providing correct temperature element numbers in the table depicted in the figure. N100 was changed to N101 in-three places in the section of the figure which depicts the typical centrifugal-type ESF Electrical Switchgear room cooler.

REASON FOR CHANGE: To update the FSAR to agree with.the latest revision of the P&ID which reflects "as-built" conditions.

SAFETY EVALUATION: No equipment was added, deleted, or modified nor was any portion of the system physically or functionally altered in any way. No Technical Specification change was identified and there was no unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 47

~

-Attachment to'AECM-87/0019-SRASN: 'NPE-86-103 ' DOC N0: CN-3482-CUCNR0137~ SYSTEM: .N/A DESCRIPTION OF CHANGE: FSAR Figures 9.5-6 and 9.4-16b were changed by the deletion of control signals from the Carbon-

' Dioxide. Suppression. System to valves Z17-F004 & F005, REASON FOR CHANGE: To provide consistency with the description for the control . building purge subsystem contained in FSAR Section 9.4-10.

SAFETY EVALUATION: - This change only provides clarification. No physical change was made to. the system, its function, or its components. There was no effect on previously analyzed accidents or equipment' performance, and no unresolved safety question or Technical Specification change was' identified.-

FACILITY DESCRIPTION' CHANGE: Yes.

N J19ATTC86123001 - 48

Attachment to AECM-87/0019 SRASN: NPE-86-104 DOC NO: CN-3411-CUCNR0069 SYSTEM: N62 DESCRIPTION OF CHANGE: FSAR Section 10.4.2.2 was revised by changing the phrase " steam-pressure reducing station" to

" steam-pressure reducing valve".

REASON FOR CHANGE: To provide clarification and more precisely define the pressure reduction provisions for main steam utilized by the steam jet air ejectors in the Condenser Air Removal System.

SAFETY EVALUATION: The change is to the description in the_FSAR for clarification only and does not alter the design, configuration, or operation of the plant. There were no Technical Specification changes associated with the change and there were no unreviewed safety questions.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 49

' Attachment to AECM-87/0019 SRASN: NPE-86-105 DOC N0: CN-3314-CUCNR0079: SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 6.2.3.3 was revised to.

change the calculated secondary containment inleakage, at the design negative pressure, from 1300 cfm to 2300 cfm.

REASON FOR CHANGE: To correct an apparent typographical error.

SAFETY EVALUATION: The correct inleakage value was used to establish the SGTS flow requirements; thus, the error did not adversely impact the design, configuration, or operation of the Standby Gas Treatment System. No.unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes

'J19ATTC86123001 - 50

Attachment to AECM-87/0019 SRASN: NPE-86-106 DOC N0: CN-3353-CUCNR0003 SYSTEM: N/A DESCRIPTION OF CHANGE: This change provided revised FSAR hydrodynamic loads to incorporate new quencher air bubble pressure and water clearing data.

REASON FOR CHANGE: Changes were made to reflect the latest methodology and load combinations for determining the hydrodynamic loads on the main steam relief valve quenchers.

SAFETY EVALUATION: This FSAR change reflected the results of the most currently approved methodology for determining hydrodynamic loads on the main steam relief valve quenchers. Since the revised hydrodynamic loads were within the quencher design allowables, no Technical Specification changes or unreviewed safety questions were identified as a result of this change.

FACILITY DESCRIPTION CHANGE: Yes l '

V f

J19ATTC86123001 - 51

Attachment to AECM-87/0019 SRASN: NPE-86-107 DOC NO: CN-3034-CUCNR0004 SYSTEM: N/A DESCRIPTION OF CHANGE: This change revised FSAR Sections 3.8.1.2.2.1 and 3.8.3.2.2.1 concerning exceptions taken to AWS D1.1 Structural Welding Code regarding base materials, welding processes, design of welded connections, procedure and personnel qualifications and visual inspection of welds.

REASON FOR CHANGE: A revision was necessary to accurately describe within the FSAR the GGNS welding program's compliance with AWS D1.1 1L972.

SAFETY EVALUATION: The exceptions taken to AWS DI.1 - 1972 reflect technically acceptable alternatives to D1.1 installation requirements which cannot be technically or economically applied to all applications that occur in the construction of a nuclear power plant. By accepting these alternate requirements, there has been no loss of quality or design capacity in the erected structural and miscellaneous steel, rather the alternative requirements provided the controls necessary to assure the quality of the installations. This change did not involve an unreviewed safety question or Technical Specification change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 52

Attachment to AECM-87/0019 SRASN: NPE-86-108 DOC N0: CN-3130-CUCNR0005 SYSTEM: N/A DESCRIPTIG;i 0F CHANGE: This change revised FSAR Section 3.8.4.2 to specify allowable undercut of welds for materials less than 3/16 inches thick and added a reference to AWS D1.3 which applies to the walding of light gauge or sheet steel.

REASON FOR CHANGE: Added the reference to AWS D1.3 because the requirements in that standard provided for additional structural integrity of the welding covered by AWS D1.3. The weld undercut change was made to reflect the requirements used in the construction of GGNS and to conform with industry welding standards.

SAFETY EVALUATION: The inclusion of specific weld undercut requirements did not increase the probability of an accident, rather those requirements ensured that welds had a measurable and inspectable level of quality as intended by standard industry welding practice. The addition of AWS D1.3 which provided criteria specifically for welding of sheet metal increased the quality of those structures / components fabricated of light gauge material. There were no Technical Specification changes or unreviewed safety questions identified as a result of this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 53

Attachment to AECM-87/0019 ,

SRASN: NPE-86-109 DOC NO: CN-3303-CUCNR0111 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 7.3.1.1.1.4.12.4, which describes the logic and sequencing of the Safety Relief Valves, was revised by deleting the term " sensing element".

REASON FOR CHANGE: To provide clarification and to correctly reflect the absence of a Sensing element as depicted in P&ID M-1077C.

SAFETY EVALUATION: The change to the FSAR does not alter the original design function, the physical design, or operation of the system. No Technical Specification change or unreviewed safety question was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes i

J19ATTC86123001 - 54

Attachm:nt to AECM-87/0019

-SRASN: NPE-86-110 DOC i;0: CN-3410-CUCNR0105 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 12.4-5 was changed by revising.the thyroid dose rates in the Containment and in the Auxiliary Building during refueling.

REASON FOR CHANGE: To correctly reflect values obtained from a re-analysis.

SAFETY EVALUATION: The revised values are based on a refined analysis of existing operational conditions, and do not_ affect previously evaluated accidents or equipment. No Technical Specification change was identified for this change to the FSAR and there were no unreviewed safety questions.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 55

Attachment to AECM-87/0019 SRASN: NPE-86-111 DOC NO: CN-3337-CUCNR0065 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 12.4-11 was changed by incorporating the Containment Personnel Lock man-hr./yr.

occupancy value.

REASON FOR CHANGE: To modify commitments made in responses to NRC questions.

SAFETY EVALUATION: This change to the FSAR does not physically affect the plant, perviously analyzed accidents, or equipment.

No Technical Specification changes were identified for this change and there were no unreviewed safety questions associated with this change.

FACILITY DESCRIPTION CHANGE: No i

(

1 J19ATTC86123001 - 56

Attachment to AECM-87/0019 SRASN: NPE-86-112- DOC N0: :CN-3285-CUCNR0064 SYSTEM: N/A

. DESCRIPTION OF CHANGE: FSAR Section 18.1.12 was changed by expanding the discussion of Plant Staff operating experience information and by identifying the organizational entity which serves.as the independent safety engineering group and the procedures which fulfill requirement I.C.5 of NUREG-0737.

REASON FOR CHANGE: To reflect current and accurate information relative to NUREG-0737 requirements.

SAFETY EVALUATION: This change to the FSAR was for clarification

, only and did not affect previously evaluated accidents or

( equipment performance. No Technical Specification change was identified for this change and there was no unreviewed safety question.

FACILITY DESCRIPTION CHANGE: No i

4 J19ATTC86123001 - 57

Attachm:nt to AECM-87/0019 SRASN: NPE-86-113 DOC N0: CN-3174-CUCNR0053 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 9.4-12 was revised by changing the values of the horsepower for the fan motors in the Water Treatment Building Ventilation Subsystem and the Radial Well Switchgear House Ventilation System.

REASON FOR CHANGE: To provide an accurate description of the as-built plant.

SAFETY EVALUATION: This change to the FSAR had no effect on

- previously analyzed accidents or equipment performance. There were no unreviewed safety questions or Technical Specification changes associated with this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 58

Attachment to AECM-87/0019 SRASN: NPE-86-114 DOC N0: CN-3196-CUCNR0139 SYSTEM: P64 DESCRIPTION OF CHANGE: FSAR Figure 9.5-1 was revised by deleting manual locked-open valve NSP64-F336.

-REASON FOR CHANGE: To reflect as-built conditions.

SAFETY EVALUATION: The valve was not required since suitable isolation valves are provided downstream, and there was no change to the facility since the valve was never installed. No Technical Specification change or unrdviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: Yes J

l i

1 1

4 J19ATTC86123001 - 59

Attachment to AECM-87/0019 SRASN: NPE-86-115 00C N0: CN-3236-CUCNR0130 SYSTEM: P64 DESCRIPTION OF CHANGE: This change deleted the note below

" Typical Deluge System" on FSAR Figure 9.5-8a dealing with motor operated valves to be provided in the Deluge System.

REASON FOR CHANGE: This change was made to reflect the as-built condition of the plant.

SAFETY EVALUATION: Motor operated valves were deleted from P&ID's (FSAR Figures 9.5-2 and 9.5-3) during construction. The

" note" associated with the motor operated valves was inadvertently not removed from the Figure 9.5-8a. This editorial change was made to correct that inconsistency. Due to the nature of this change no Technical Specification change and/or unreviewed safety questions were identified.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 60 ,

Attachment to AECM-87/0019 SRASN: NPE-86-116 DOC N0: CN-3172-CUCNR0121 SYSTEM: N22 DESCRIPTION OF CHANGE: FSAR Figure 10.4-9b was changed to add drawing continuation flags to new P&ID drawings M-1120 A and B.

The new drawings showed the Allis-Chalmers furnished Primary Water Cooling System for the generator.

REASON FOR CHANGE: _This change was made to reflect the as-built configuration of the plant.

SAFETY EVALUATION: The change to FSAR Figure 10.4-9b did not affect the system's integrity or function. The change was consistent with the design criteria for this system. -There were no unreviewed safety questions or Technical Specification changes identified from this change.

FACILITY DESCRIPTION CHANGE: Yes 1

l J19ATTC86123001 - 61

i AttachmGnt to AECM-87/0019 SRASN: NPE-86-117 DOC N0: CN-3185-CUCNR0122 SYSTEM: P44 DESCRIPTION OF CHANGE: FSAR Figure 9.2-23 was changed to delete drain line 1"-JBD-980/ valve F351 and to change vent valve F1038 from a gate to globe REASON FOR CHANGE: The drawing was revised to reflect actual plant configuration.

SAFETY EVALUATION: These changes were consistent with the system

-design criteria and did not affect'the integrity or function of the component or system. The changes did not result in a Technical Specification change or the creation of an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes 4

J19ATTC86123001 - 62

Attachment to AECM-87/0019 SRASN: NPE-86-118 DOC N0: CN-3226-CUCNR0124 SYSTEM: N33 DESCRIPTION OF CHANGE: The computer point identity for pressure switch NIN33N067 was changeu from N018 to N067 on FSAR Figure 10.4-3.

REASON FOR CHANGE: The change was made to resolve a discrepancy between drawings and to reflect the actual plant configuration.

SAFETY EVALUATION: The change to Figure 10.4-3 was consistent with the as-built condition for this system. The change did not result in a Technical Specification change or identification of an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes k

J19ATTC86123001 - 63 o

Attachment to AECM-87/0019 SRASN: NPE-86-119 DOC N0: CN-3395-CUCNR0125 SYSTEM: N/A DESCRIPTION OF CHANGE: The elevation of the two capped equipment drains for the Glycol Cooler area was changed from 118'-0 to 107'-6" in FSAR Figure 9.3-13.

REASON FOR CHANGE: The change was made to reflect plant as-built conditions.

SAFETY EVALUATION: The change to FSAR Figure 9.3-13 was purely a correction to be consistent with the as-built condition for this '

system. The change did not affect the function or integrity of either the component or system. No unreviewed safety question or Technical Specification change were identified as a result of this change.

FACILITY DESCRIPTION CHANGE: Yes 6

J19ATTC86123001 - 64

Attachment to AECM-87/0019 SRASN: NPE-86-120 DOC N0: CN-3443-CUCNR0128 SYSTEM: N19,P11 DESCRIPTION OF CHANGE: FSAR Figures 9.2-16 and 10.4-10 were changed to show the condensate transfer pumps minimum flow line returns to line 8"-HBD-328 and not to the condensate storage tank.

REASON FOR CHANGE: The figures were revised to reflect the plant as-built condition.

SAFETY EVALUATION: The changes to Figures 9.2-16 and 10.4-10 were consistent with the as-built conditions of this system. The changes did not result in a Technical Specification change or identification of an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 65

Attachment to AECM-87/0019 l

SRASN: NPE-86-121 DOC N0: CN-3237-CUCNR0126 SYSTEM: PS2 DESCRIPTION OF CHANGE: This FSAR Change deleted the "C" closed position designator for manual valve IP52F166 shown on FSAR Figure 9.3-3.

REASON FOR CHANGE: To correct a drawing error on FSAR Figure 9.3-3.

SAFETY EVALUATION: Per FSAR 9.3.1.3 the Instrument and Service Air Systems perform no safety-related functions. This FSAR change did not change the original Service Air System design intent and only corrected a drawing error. No unreviewed safety questions or Technical Specification changes have been identified for this FSAR change.

FACILITY DESCRIPTION CHANGE: No 6

J19ATTC86123001 - 66

\

Attachment to AECM-87/0019 SRASN: NPE-86-122 DOC N0: CN-3426-CUCNR0127 SYSTEM: R51 DESCRIPTION OF CHANGE: This FSAR change revised the.model number of the motor operator for valve E51-F019 in FSAR Table;3.10-3 to reflect the correct Limitorque actuator model.

REASON FOR CHANGE: To reflect the correct as-built conditions of  ;

the plant. ';

s SAFETY EVALUATION: This FSAR change did not change the original design intent of valve E51-F019 and only corrected an error in FSAR Table 3.10-3. The Limitorque motor operator is seismically qualified, and will per.7rm it's intended function. No Technical Specification changes or unreviewed safety questions were identified as a result of this FSAR change.

\

FACILITY DESCRIPTION CHANGE: Yes M..

E k

D 1

o A t

T w ,

J19ATTC86123001 - 67

Attachment to AECM-87/0019 A.

' t,

< s d( -

TffASN:NPE-86-123-i DOC N0: CN-3176-CUCNR0093 SYSTEM: T46

~ DESCRIPTION OF CHANGE: This change is to reflect a reduction of the normal ambient temperature in the ESF Electrical Switchgear

. - Rooms 1A308 and 1A309 during normal plant operations-from a maximum of 104 degrees F to 90 degrees F.

REASON FOR' CHANGE: This change is to update the UFSAR to show actual plant. design.

SAFETY EVALUATION: This change only updates the information contained within the UFSAR. There is no physical change to any system or components. The change is a more conservative value

~

that does not affect the probability or consequences of an accident or malfunction of equipment important to safety. No possibility of a new accident or equipment malfunction is J' introduced. There is no impact on the Technical Specifications g" . and no unreviewed safety question was identified by this change. .

FACILITY DESCRIPTION CHANGE: Yes L

h*

f W

.% ' s f

'\ :

t J19ATTC86123001 - 68 s

h

Attachment to AECM-87/0019 SRASN: NPE-86-124 DOC NO: CN-3288-CUCNR0009 SYSTEM: E12 DESCRIPTION OF CHANGE: This change revised piping and instrument i diagrams (P&ID) M-1085A&B to show valves Q1E12-F051A&B, F210 F211, and F065A as normally closed valves and to show E12-F051A&B and F065A&B as fail closed valves.

REASON FOR CHANGE: This change corrects the valve positions as shown on P&ID's M-1085A&B to reflect agreement with other plant documents.

SAFETY EVALUATION: This change corrects drawings to reflect the actual plant configuration. No plant system or component or valve position is affected. There.is no change to Technical Specifications and'no unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: Yes I

4 A

J19ATTC86123001 - 69

Attachment to AECM-87/0019 SRASN: NPE-86-125 DOC NO: CN-3382,3275-CUCNR0010 SYSTEM: B21 DESCRIPTION OF CHANGE: This change revises FSAR Table 9.3-2 to reflect that B21-F032A&B valve position upon loss of air is dependent on water flow conditions at the time air is lost and revises Table 3.2-1 and Section 6.2.4.3.1.1.1 to reflect B21-F010A/B as lift check valves rather than simple or swing check valves.

REASON FOR CHANGE: These changes provide clarification of component function and correct minor errors.

SAFETY EVALUATION: These changes do not modify any plant system or equipment, but rather clarify and correct drawings to reflect actual plant conditions and to agree with other design information.

There is no change to Technical Specifications and no unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: Yes e

i t

f J19ATTC86123001 - 70

Attachment to AECM-87/0019 SRASN: NPE-86-126 DOC NO: CN-3009,3169,3479-CUCNR0015 SYSTEM: E22 DESCRIPTION OF CHANGE: These changes revise UFSAR Table 6.3-9 to change E22-F205 to the correct number E22-F036, revise Section 5.4.7.2.1 to read " containment spray" instead of "drywell spray",

and revise Section 5.4.7.1.1.2 to reflect LPCI 3 Loop Flow of 22,000 GPM.

REASON FOR CHANGE: These changes correct minor errors in the UFSAR to make the applicable sections agree with other sections.

SAFETY EVALUATION: There is.no design change and no impact on Technical Specifications. There is no effect on accident analysis. This change does not modify equipment or equipment operation or plant configuration. There is no effect on the margin of safety. Therefore, no unreviewed safety question was created from this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 94

Attachm:nt to AECM-87/0019 SRASN: NPE-86-127 DOC NO: CN-3028,3282,3449-CUCNR0023 SYSTEM: B33 DESCRIPTION OF CHANGE: This change clarifies UFSAR Section 5.4.1.9.3 and Table 5.4-1 by adding discussion of the " fail-as-is" position of the recirculation flow control valves, corrects Section 5.4.4.2 to show the steam lir.e venturi's method of providing indication and feedwater flow control, and corrects Section 5.4.1.3 to reflect the correct method of obtaining reactor recirculation loop temperature.

REASON FOR CHANGE: These changes correct minor discrepancies in the FSAR and reflect the as-built plant design.

SAFETY EVALUATION: This change has no impact on Technical Specifications. There is no physical change to the plant, and therefore no increase in the probability or consequences of an accident or of a malfunction of equipment important to safety.

There is no possibility of a new accident or malfunction of equipment and there is no effect on the margin of safety.

Therefore, no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 71

Attachment to AECM-87/0019 SRASN: NPE-86-128 DOC N0: CN-3377-CUCNR0042 SYSTEM: P75 DESCRIPTION OF CHANGE: These changes alter UFSAR Figures 9.5-11 and 9.5-12 by (1) adding the prefix "N1P75" to equipment numbers, and (2) changing note 10 to specify the new Nicholson Air Traps.

-These changes do not affect the description of the Starting Air System in the UFSAR REASON FOR CHANGE: These changes update piping & instrument diagrams shown in Fioures 9.5-11 and 9.5-12.

SAFETY EVALUATION: The Nicholson Air Trap performs the same function as the previous air trap. Therefore, there is no increase in the probability or consequences of an accident or of a malfunction of equipment important to safety, and no possibility of a new accident or malfunction. The updating of Figures 9.5-11 and 9.5-12 has no effect on any system or component. This change has no impact on Technical Specifications and does not create an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: Yes 4

l l

t i J19ATTC86123001 - 72 L

Attachment to AECM-87/0019 SRASN: NPE-86-129 DOC N0: CN-3287-CUCNR0092 SYSTEM: N/A DESCRIPTION OF CHANGE: This is a change to UFSAR Section 6.2.2.2 to delete the phrase "in the drywell" from a discussion of the location for the use of HVAC flexible drywell fiberglass insulation. -Also, this deletion makes the discussion consistent with Table 6.1-2.

REASON FOR CHANGE: This change removes an ambiguity by which a reader could incorrectly understand that the HVAC flexible drywell fiberglass insulation is in the drywell only instead of the containment.

SAFETY EVALUATION: This is UFSAR clarification that has no effect on any system, component, plant operation, or accident analysis.

There is no effect on Technical Specification and no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 73

Attachment to AECM-87/0019 SRASN: NPE-86-130 DOC N0: CN-3447-CUCNR0046 SYSTEM: T48 DESCRIPTION OF CHANGE: Section 7.3.1.1.8.1 of the FSAR originally stated that the Standby Gas Treatment System Pressure Controllers regulate the pressure of the enclosure building by positioning the inlet vanes on each of the filter fan trains to maintain 0.25 W.C. However, the controllers actually perform this function by positioning 14 valves.

REASON FOR CHANGE: To correctly reflect plant as-built conditions in the UFSAR.

SAFETY EVALUATION- This is a change to the FSAR and has no effect on any plant system or component. There is also no effect on the stated function of maintaining pressure at 0.25 in W.C.;

only in the details of how this function is actually performed.

It will not effect the system availability as required by Technical Specifications and no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 74

Attachment to AECM-87/0019 SRASN: NPE-86-131 DOC N0: CN-3202-CUCNR0014 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.9-3c was revised to: (1)show that valves E12-F074A/B have a system isolation function rather than a containment isolation function; (2) correctly depict valves G33-F051 and F052A&B as check valves rather than motor operated valves; and (3) add valves 821-F147A/B to the table.

REASON FOR CHANGE: To correctly reflect plant as-built conditions in the UFSAR.

SAFETY EVALUATION: This change corrected minor errors in Table 3.9-3c and did not invalidate or adversely affect accident analyses. There was no Technical Specification change or unreviewed safety question associated with this change.

FACILITY DESCRIPTION CHANGE: Yes 6

l J19ATTC861230014- 75

Attachment to AECM-87/0019 i

SRASN: NPE-86-132- DOC NO: CN-3210-CUCNR0072 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.9-3c was revised by deleting valves P64-FA10A/B from the list of active valves.

REASON FOR CHANGE: To correctly reflect as-built conditions in the UFSAR. The valves were deleted from the list (of active valves) because they serve no " active" safety function.

SAFETY EVALUATION: The change to the FSAR does not alter the design basis, plant cor. figuration, or operation. There was no unreviewed safety question or Technical Specification change -

associated with this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 76

Attachment to AECM-87/0019 SRASN: NPE-86-133 DOC N0: CN-3210-CUCNR0057 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.9-3c was changed to reflect containment isolation rather than drywell isolation as the active function for valves E61-F595A/B/C/D, F596A/B/C/D, F597A/8/C/D, and F598A/B/C/D.

REASON FOR CHANGE: To correctly reflect plant as-built conditions in the UFSAR and to correct an inconsistency between the revised tables and Tables 6.2-44 and 6.2-49 which correctly identify the isolation function of these valves.

SAFETY EVALUATION: This change to the FSAR does not alter the design basis or plant configuration for the valves, and there is no effect on any FSAR accident analysis. No Technical Specification change or unreviewed safety question was identified from this change.

FACILITY DESCRIPTION CHANCE: Yes J19ATTC86123001 - 77

Attachment to AECM-87/0019 SRASN: NPE-86-134 DOC N0: CN-3191-CUCNR0146 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised Table 9.3-3 to agree with figure 4.5-2, which indicates that the sample point tap is off Recirculation Loop "A", not Loop "B". Also, FSAR Figure 9.3-7a was revised to show that the portion of the gas return line internal to the post accident sampling station is provided with heat tracing. The portions of the gas return line external to the post accident sampling station were already correctly shown with heat tracing.

REASON FOR CHANGE: To make FSAR Table 9.3-3 consistent with FSAR Figure 5.4-2. FSAR Figure 9.3-7a was revised to reflect an "as-built" condition.

' SAFETY EVALUATION: These FSAR changes were either editorial in nature or to reflect the original plant design intent. No physical plant equipment was changed as a result of these changes. No unreviewed safety question or Technical Specification change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 78

I Attachment to AECM-87/0019- ;

SRASN: NPE-86-135 DOC NO: CN-3210-CUCNR0056 SYSTEM: E12 DESCRIPTION OF CHANGE: This.FSAR change revised the active function description of valves E12-F074A and B in FSAR Table'  !

i- 3.9-3c from containment isolation to system isolation.

REASON FOR CHANGE: To update FSAR Table 3.9-3c to be consistent with FSAR Table 6.2-49 and 6.2-44; and Technical Specification Table 3.6.4-1.

SAFETY EVALUATION: Neither Technical Specification Table 3.6.4-1 nor FSAR Tables 6.2-49 and 6.2-44 list valves E12-F074A and B as required to perform a-containment isolation function, nor are these valves assumed in any accident analysis to serve as containment isolation valves. Containment isolation for the affected penetrations are accomplished by valves E12-F073A and B, and a closed piping system outside of containment; per the requirements of Note 7 of FSAR Table 6.2-49. No unreviewed safety questions or-Technical Specification change have been identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes i-i F

e a

l J19ATTC86123001 - 79

+ ,,v- e - v,v, - --

Attachment to AECM-87/0019 SRASN: HPE-86-136 DOC N0: CN-3223-CUCNR0027 SYSTEM: 821 DESCRIPTION OF CHANGE: FSAR Table'3.10-6 was revised to reflect the correct location of 821-N058 and B21-H099 pressure transmitters.

REASON FOR CHANGE: To correctly reflect as-built conditions in the UFSAR.

SAFETY EVALUATION: This change to the FSAR was made only to reflect the correct MP&L numbers in the seismic qualification tables; no equipment change was made. There was no safety concern with this change and no unreviewed safety question or' Technical Specification change was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 80

Attachment to AECM-87/0019 i

SRASN: NPE-86-138 DOC N0: CN-3291-CUCNR0070 SYSTEM: E21 DESCRIPTION OF CHANGE: FSAR Figure 8.3-1 was changed by deleting-the surge suppressors from the LPCS Pump Motor and adding Pull Box PBB212 for the Instrument Air Compressor, NIP 53C001-B.

REASON FOR-CHANGE: To correctly reflect as-built conditions in j the UFSAR. .

SAFETY EVALUATION: This change had no effect on accident analyses or equipment performance. There was no unreviewed safety question or Technical Specification change identified for this change.

FACILITY DESCRIPTION CHANGE: Yes i .

i 6

4 l

J19ATTC86123001 - 81

1 Attachment to AECM-87/0019 i SRASN: NPE-86-139 DOC N0: CN-3293-CUCNR0129 SYSTEM: P64 DESCRIPTION OF CHANGE: FSAR Figure 9.5-4 was changed by the deletion of Notes 1 and 2 which described pressure restricting and pressure reducing valves for use on fire protection hose l stations or racks. <

REASON FOR CHANGE: To correctly reflect as-built conditions in the.UFSAR.

SAFETY EVALUATION: This change to the FSAR does not alter the system function, application, or design. There were no safety concerns associated with this change and no unreviewed safety question or Technical Specification change was involved.

FACILITY DESCRIPTION CHANGE: Yes i

L J19ATTC86123001 - 82

Attachment to AECM-87/0019

-SRASN: NPE-86-140 DOC N0:iCN-3286-CUCNR0135 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Figures 9.4-3 and 9.4-10 were changed to delete the Control Rod Drive maintenance facility ventilation system.

REASON FOR CHANGE: To correctly reflect as-built plant conditions. The deleted facility description involved in this change concerns planned modifications to the original design which were never implemented even though the description was incorporated into the FSAR. These modifications are planned for implementation in a future design change.

SAFETY EVALUATION: This change to the FSAR does not affect the actual physical plant; also, the system has no function in the normal operation of the plant nor does it have a safe shutdown function. The system is a support system used for maintenance only. There was no identification of'an unreviewed safety question for this change or change to the Technical Specifications.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 83

Attachment to AECM-87/0019 SRASN: NPE-86-141 DOC N0: CN-3284-CUCNR0002 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.2-4 was changed to incorporate paragraph NC/ND/NF-2610, Summer 1976 addenda of the ASME Code.

REASON FOR CHANGE: To reflect current requirements and to permit continued use of existing materials-for which allowance was previously made by a code case for fabrication of pipe supports. That code case has now expired, but the provisions were incorporated into the Summer 1976 addenda.

SAFETY EVALUATION: The change to the FSAR does not introduce any operational or functional change to any of the plant systems, nor does it affect the structural integrity of any component. No new failure modes were created and no unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 84

Attachment to AECM-87/0019 SRASN: NPE-86-142 DOC N0: CN-3271-CUCNR0038 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 9.5.5.3 was revised by changing the HPCS diesel generator run time at 50 percent load from 15 minutes to 30 minutes. .This 30 minute loaded run is to be conducted after an extended no-load operation.

REASON FOR CHANGE: To make the FSAR consistent with the manufacturers specification.

SAFETY EVALUATION: Changing the FSAR to agree with this manufacturer's specification does not create the possibility of an accident and no margin of safety is reduced in that the HPCS diesel generator will still function as originally designed.

Increasing the loaded run time of the diesel generator will decrease the probability of malfunction in that it will reduce the amount of oil in the exhaust system and air box that may have accumulated due to extended light load operation. No unreviewed safety question or Technical Specification change was ~ identified for this change.

FACILITY DESCRIPTION CHANGE: No 9

'I J19ATTC86123001 - 85

Attachment to AECM-87/0019

~SRASN: NPE-86-143 DOC N0: CN-3020-CUCNR0054R01 SYSTEM: N/A DESCRIPTION OF. CHANGE: FSAR Section 12.3.4.1.3 was changed to reflect that the plant radiation monitors share 3 multipoint recorders instead of 2 recorders.

REASON FOR. CHANGE: To correctly reflect current plant as-Luilt conditions.

SAFFTY EVALUATION: This change to the FSAR is not a design change and does not affect instrument availability or trip

_ point. The monitors do not perform any function which mitigates consequences of an accident. No new failure modes'were created and no unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes I

I i J19ATTC86123001 - 86

Attachm:nt to AECM-87/0019 SRASN: NPE-86-144 DOC N0: CN-3435-CUCNR0089R01 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 3.8.1.6.2, 3.8.3.6.2a, and 3.8.4.6.2a were changed by deleting reference to "All Other Structures" and the specified strength of 4,000 psi. Section 3.8.4.6.2a was also changed by the addition of the following references:

Turbine Pedestal 3000 psi Turbi'e Building Floor Slabs Unic 1 3000 psi Unit 2 4000 psi Turbine Building Foundation and Walls 4000 psi Radwaste Building 4000 psi REASON FOR CHANGE: To clarify the specified concrete compressive strengths.

SAFETY EVALUATION: The information provided by this change to the FSAR serves no operational purpose. Structural adequacy and integrity are not affected by this change. No unreviewed safety question or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 87

Attachment to AECM-87/0019 4

SRASN: NPE-86-145 DOC NO: CN-3440-CUCNR0017 . SYSTEM: N/A-1 DESCRIPTION OF CHANGE: FSAR Section'7.6.1.7.3 was revised by clarifying the description of the low-power setpoint for the rod block requirement and reference to specific setpoint values was deleted.

REASON FOR CHANGE: To provide a clear description of system operation.

SAFETY EVALUATION: This change to the FSAR does not alter the operation of the system. No plant equipment was affected; no new failure modes were introduced; and the system function was not altered.- No unreviewed safety question-or Technical Specification change was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes i

4 0

4

(

i t

J19ATTC86123001 - 88 l-

Attachment to AECM-87/0019 SRASN: NPE-86-146 DOC N0: CN-3327-CUCNR0099 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 12.6-1 was revised by the addition of the Standby Gas Treatment System sampling station at elevation 135 ft. and the HVAC units area at elevation 245 ft.

Figure 12.6-6 was revised by adding the designation of Zone A-V for the HVAC units area.

REASON FOR CHANGE: To provide an accurate description of the system in the UFSAR.

SAFETY EVALUATION: This change to the FSAR does not modify equipment. Post-accident dose rates, shielding, and access are not changed.- No unreviewed safety question or Technical Specification change was identified for this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes i

1 L

L i

J19ATTC86123001 - 89

4 Attachment to AECM-87/0019 SRASN: NPE-86-147 00C.N0: CN-3013-CUCNR0030 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Tables 4.4-1 and 2 'were revised by changing the values of thermal and hydraulic design i characteristics. The anticipated values were replaced with final values used in the GGNS-1 specific analyses.

REASON FOR CHANGE: To reflect accurate values of the design characteristics to obtain consistency with Chapter 6 and 15 of i the FSAR.

SAFETY EVALUATION: This change to the FSAR represents minor clarification _ to provide consistency throughout the FSAR and does not apply to an accident nor affect its probability of occurrence._ No equipment malfunction modes were created and no unreviewed safety question or Technical Specification change was identified.

FACILITY DESCRIPTION CHANGE: Yes i

l i

J19ATTC86123001 - 90 l

l-

Attachment to AECM-87/0019 SRASN: NPE-86-148 DOC 1:0: CN-3388-CUCNR0098 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 6.2.1.1.2.6, 9.4.7.3, and 9.4.8.3 were changed to indicate that the containment average temperature will be maintained below the Technical Specification limit, and clarification statements were added regarding qualification of equipment located in the drywell and containment.

REASON FOR CHANGE: To provide consistency with the GGNS Technical Specifications.

SAFETY EVALUATION: This change to the FSAR does not alter the ,

design or configuration of the plant. The change does provide r

consistency with the Technical Specifications. No.unreviewed safety question was identified for this change.

FACILITY DESCRIPTION CHANGE: No r.

l l

J19ATTC86123001 - 91 l

I

Attachment to AECM-87/0019 SRASN: NPE-86-149 DOC N0: CN-3435-CUCNR0080 SYSTEM: N/A-DESCRIPTION OF CHANGE: This FSAR change revised Section 3.8.4.1.2.2.c to exclude the Radwaste Building Roof Hatch Covers from tornado generated missile protection requirements.

REASON FOR CHANGE: To make FSAR Section 3.8.4.1.2.2.c consistent with requirements of FSAR Section 3.3 and Table 3.3-1.

SAFETY EVALUATION: Per FSAR Section 3.8.4.1.2.2, the Radwaste Building is classified as a non-Catagory I structure. Per FSAR Section 3.3, only Catagory I structures listed in FSAR Table 3.3-1 require tornado missile protection. This FSAR change is in accordance with the original design requirements since the Radwaste

_ Building is a non-Catagory structure. This FSAR change has no adverse safety or operations impact.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 92

Attachmsnt to AECM-87/0019

.SRASN: NPE-86-150 DOC NO: CN-3477-CUCNR0035 SYSTEM: N/A.

DESCRIPTION OF CHANGE: 'This FSAR change incorporated the material in FSAR Q&R 021.7 into UFSAR Table 6.2-56. The change also corrected omissions.in the original Table 021.7-1, particularly Parameters 2.10 and 2.11. Note 6 to that table was-also revised.

REASON FOR. CHANGE: To incorporate Q&R. material into the main body of the FSAR and to correct omissions and provide. clarification as a part of the annual FSAR update.

SAFETY EVALUATION: This_FSAR change.did not adversely affect plant safety or operations. The added values for. Parameters 2.10 and 2.11 were provided by General. Electric and found to be within allowable design limits. The clarification of Note 6 is of an editorial nature with no adverse safety impact. No unreviewed safety question or. Technical Specification change were identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 93

Attachment to AECM-87/0019 SRASN: NPE-86-152 DOC N0: CN-3352-NPE-85/0081-CUCNR006 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.8-1 was changed to reflect updated values of the calculated factors of safety for sliding, -

overturning, and buoyance for seismic category 1 structures.

REASON FOR CHANGE: To reflect the results of the latest IN

' stability analyses performed for the Control Building and Units 1

~

and 2 Auxiliary Buildings.

SAFETY EVALVATION: .The change to the FSAR is based on analyses

~

performed utilizing as-built conditions, more refined design ,

assumptions, and results of the latest seismic analyses. No accident consequences are affected and allowable stability limits are not only met, but exceeded. No Technical Specification changes were required and there were no unresolved safety.

questions involved with this change.

FACILITY DESCRIPTION CHANGE: Yes k

7 5 h

=

x i J19ATTC86123001 - 159

\. Attachment to AECM 97/0019 r .

7 SRASN: NPE-86-162 DOC'N0: CN-3447-CUCNR0013 SYSTEM: E22 m

DESCRIPTION OF CHANGE: This change revised the description for 4- i

'%~

l' the HPCS Pump Discharge Valve automatic closure. The HPCS Pump Discharge Valve will automatically close on receipt of high water level signal. Drywell pressure has no effect on operation of this valve.

s REASON FOR CHANGE:

- the description for,This the HPCSchange resolves Pump DischargeFSAR Valveinconsistencies automatic in closure and makes the FSAR description consistent with General 4 Electric .(0.E.) design intent and the design specification which is correct. .

SAFETY' EVALUATION: The Technical Specifications are not affected.

.c The valve will function within the original design specification..

^% - This chargh does not alter the: valve operation per original design, but ratheriresolyes FSAR inconsistencies and brings the cF5AR Section into d.onformance with the G.E. design intent and

.' specification. The change does not degrade or prevent action described in Chapter 15 " Sequence of Events" Tables for the accident analyzed. There is no effect on the margin of safety.

[h FACILITYDESCRIPTIONCHANGEbYes s

b Q' ,

l

, n ~

x _

p s 'l \.

, - l.

y l

4

?

f g t

l t

% 4 th J19ATTC86123001 --96 s .

t L

Attachment to AECM-87/0019 SRASN: NPE-86-163 DOC N0: CN-3479-CUCNR0020 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised FSAR 7.5.1.2.3.6 to indicate that two radiation monitors are located in the Control Room and two radiation monitors are located in the Upper Cable Spreading Room.

REASON FOR CHANGE: To update FSAR 7.6.1.2.3.6 to reflect "as-built" plant conditions.

SAFETY EVALUATION: This FSAR change reflects the original design intent for the locations of the radiation monitors, and was not the result of any plant design changes. The radiation monitors continue to be seismically supported, powered from proper electrical power sources, 2nd qualified for their intended purpose. No unreviewed safety questions or Technical Specification changes were generated as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 97

Attachment to AECM-87/0019 SRASN: NPE-86-164 DOC NO: CN-3433-CUCNR0039 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change deleted, "and/or by steam generated in the covered part of the core", from Criterion 5 in FSAR 6.3.3.2.

REASON FOR CHANGE: To clarify and accurately reflect the analysis discussed in Criterion 5 of FSAR 6.3.3.2.

SAFETY EVALUATION: This FSAR change did not adversely affect plant safety or operations. Per General Electric, no credit for the steam cooling phenomenon was taken in the analysis described in Criterion 5 of FSAR 6.3.3.2. Therefore, deletion of this information did not adversely affect the analysis. No unreviewed safety question or Technical Specification change has been identified as a result of this FSAR change.

FACILITY DESCRIPTION' CHANGE: No i

8 l

l 1

I l

I l

i J19ATTC86123001 - 98 l

Attachment to AECM-87/0019

- SP.ASN: NPE-86-165 DOC N0: CN-3241-CUCNR0040 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change added a new UFSAR Section 5.2.2.2.3.3 to provide a description of the Safety Relief Valve (SRV) Low-Low Set Relief Function. Also, FSAR 7.3.1.1.1.4.12.2 and 7.3.1.1.1.4.12.9 were revised to indicate that operation of any SRV in the automatic relief mode will activate the SRV Low-Low Relief Logic, and that two valve actuation is possible due to the low-low set function (7.3.1.1.1.4.12.9 only).

REASON FOR CHANGE: To accurately reflect the design of the SRV ,

Low-Low Set Function and Logic in the FSAR.

SAFETY EVALUATION: These FSAR changes incorporated changes to the SRV Low-Low Set Logic design which were previously approved by the NRC via a Technical Specification change. NRC approval is documented by letter from A. Schwencer to J. P. McGaughy, Jr.

dated February 21, 1984. No unreviewed safety question or Technical Specification changes were identified as a result of incorporating this change into the FSAR text.

FACILITY DESCRIPTION CHANGE: Yes

(

J19ATTC86123001 - 99

_, - ., . _ - ~ , _ - . _ __ ._ . . - _ - _ _ . . . _ . _ _ __

Attachment to AECM-87/0019 SRASN: NPE-86-166 DOC N0: CN-3339-CUCNR0063- SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change _ replaced FSAR_ Table 15.4-2, " Input Parameters And Initial. Conditions For Rod Withdrawal", with a new Table 15.4-2, " Rod Block Alarm Distances (BWR/6)".

REASON FOR CHANGE: To correct' inconsistences between the FSAR analysis for rod withdrawal error at power and Technical Specification limits.

SAFETY EVALUATION: This.FSAR change incorporated the more restrictive rod withdrawal distances reflected in the original design. criteria and Technical Specifications for the 70 to 100%

power range. Since the rod withdrawal distances were reduced for this evaluated condition, the consequences of the accident is not increased. No unreviewed safety question or Technical Specification changes were identified as a result of this FSAR change.

FACILITY ~ DESCRIPTION CHANGE: Yes J19ATTC86123001 - 100

Attachment to AECM-87/0019 SRASN: NP2-86-167 DOC N0: CN-3370-CUCNR0024 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change updates the information in FSAR Tables 3.10-1 thru 3.10-6.

REASON FOR CHANGE: To reflect current equipment seismic qualification information and status.

SAFETY EVALUATION: This FSAR change was a " General Revision" of FSAR Tables 3.10-1 thru 3.10-6. These changes were: (1) editorial; (2) typographical corrections; (3) updated component location and model number; (4) updated seismic qualification status; (5) updated qualification information; (6) deleted non-safety related components; and (7) deleted equipment not installed. No unreviewed safety question and Technical Specification change have been identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes Q

J19ATTC86123001 - 101

Attachment to AECM-87/0019 SRASN: NPE-86-168 DOC N0: CN-3453-CUCNR0074R01 SYSTEM: N/A 4

DESCRIPTION OF CHANGE: This change revises UFSAR Table 3.9-2 to change the method of load combinations from absolute sum to the

. square root of the sum of squares revises Table 3.9-33 (110.33-1)"

to reflect preoperational testing that was performed by Specification 9645-M-275.0, and to. incorporate additional piping systems in various testing programs in response to NRC Question

'110.49; revises Table 3.9-2S to incorporate ASME Code Case N-196-1.

! REASON FOR CHANGE: This change corrects minor errors in the UFSAR and provides updated information in Section 3.9 of the UFSAR.

SAFETY EVALUATION: The revision to Table 3.9-2 corrects a minor t error. Table 110.33-1 was changed to Table 3.9-33 and updated to

~

reflect preoperational testing performed by Specification 9645-M-275.0 and in accordance with ASME Section III, Class 1, 2, and 3, and ANSI Piping Code B31-1. Code Case N-196-1 has been approved by the ASME Council, and by the NRC in. Regulatory Guide 1.84. There is no ir< pact on Technical Specifications or the margin of safety. There is no effect on the structural integrity of any system or component, and all systems function in their intended manner. Therefore, no unreviewed safety question was

. identified.

FACILITY DESCRIPTION CHANGE: Yes

-f

J19ATTC86123001 - 160

x v

Attachment to AECM-87/0019 SRASN: NPE-86-170 DOC N0: CN-3473-CUCNR0085 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 5.3.2.2 was revised to reference Figures 5.3-4 and 5.3-4a,. Figure 5.3-4a was revised, and Figures 5.3-6 and 5.3-7 were deleted based on changes made in accordance with revised 10CFR50 Appendix G.

REASON FOR CHANGE: To reflect changes made in compliance with revised 10CRF50 Appendix G.

SAFETY EVALUATION: No hardware or operating procedure changes resulted from the deletion of the figures. The deleted figures are not referenced nor do they form any portion of the basis for any Technical Specification. No Technical Specif-; cation change or unreviewed safety question was involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 146

Attachment to AECM-87/0019 SRASN: NPE-86-171 DOC N0: CN-3473-CUCNR0086 SYSTEM: N/A DESCRIPTION OF CHANGE: Section 5.3.2.1.5 was incorporated into the FSAR and was corrected so that the second paragraph reflected that there were no deviations from requirements. Table 5.3-6 was corrected so that the phosphorous value for weld SP62148 would be 0.013.

REASON FOR CHANGE: To correct responses to NRC Questions as incorporated into the text of the UFSAR.

SAFETY EVALUATION: This change to the FSAR does not result in any hardware or operating procedure changes. The change does not constitute any portion of any basis for any Technical Specification and therefore, no change in a margin of safety will occur. No Technical Specification change or unreviewed safety question was involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes i

l l

i l J19ATTC86123001 - 145

^

Attachment to AECM-87/0019 1

SRASN: NPE-86-172 DOC N0: CN3455-CUCNR0021 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change added the last sentence

.to the first. paragraph of UFSAR 7.7.1.12 to indicate that the Startup Transient Monitoring System would remain as a permanent plant' monitoring system upon completion of the Startup Test Program.

REASON FOR CHANGE: To reflect the Startup Transient Monitoring System as a permanent plant system in the UFSAR.

SAFETY EVALUATION: This FSAR change did not adversely affect plant safety or operations. The original requirements of the  !

Startup Transient Monitoring System required the system to be designed and installed as though it was a permanent plant system. No unreviewed safety question or Technical Specification change was identified as a result of this FSAR change.

i

~

FACILITY DESCRIPTION CHANGE: No t

a 9

h i

e J19ATTC86123001 - 134 1

. . . - . ~_. . . _ . _ . . _ . - . . _ . . . . . , _ - , , - _ , - _ . _ . _ - . - - .- . . . . , _ . - - _ - - . - , - .

Attachment to AECM-87/0019 SRASN: NPE-86-173 DOC N0: CN-3445-CUCNR0032 SYSTEM: N/A ,

DESCRIPTION OF CHANGE: This.FSAR change revised Note "cc" of FSAR Table 3.2-1 to indicate that both the Diesel Generator-Engine skid mounted piping and valves; and the off-engine piping and valves were~ welded by welders qualified under the previsions of ASME Section IX.

REASON FOR CHANGE: To clarify welder qualifications for Diesel Generator Engine skid mounted and off-engine piping and valves.

SAFETY' EVALUATION: This~ FSAR change did not adversely affect

. plant. safety or. operations. This FSAR change was a clarification of required welder qualifications only and did not result in any physical plant changes. No unreviewed safety question or Technical Specification change was identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes j:

I 1

J19ATTC86123001 - 151

. - . . , .a - ,,,, - , - . . . - - - . - , - - - , _ . - , - . . - . , - ., ..

Attachment to AECM-87/0019

SRASN: NPE-86-174 DOC N0: CN-3445-CUCNR0058 SYSTEM: N/A DESCRIPTI0f; 0F Ci-lANGE: This FSAR change added the classification of piping and valves beyond the first inboard isolation valves for the Main Steam Isolation Valve Leakage Control System (MSIVLC) to FSAR Table 3.2-1.

REASON FOR CHANGE: To complete the MSIVLC System classification in FSAR Table 3.2-1.

SAFETY EVALUATION: This FSAR change did not adversely affect plant safety or operations. The classification presented in revised FSAR Table 3.2-1, Item XLIII.2.b is in accordance with the original MSIVLC System design intent. No safety concerns or Technical Specification changes were generated as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 152

' Attachment to AECM-87/0019 SRASN: NPE-86-175 DOC N0: CN-3393-CUCNR0075 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised the second paragraph of FSAR 8.1.4.3 to indicate that four 125 VDC systems serve the Balance Of Plant (B0P) load groups in Unit 1.

REASON FOR CHANGE: To update the FSAR to reflect "as-built" Unit 1 plant conditions.

SAFETY EVALUATION: Per FSAR 8.1.4.3, the 125 VDC systems for B0F load groups are not directly related to the safety of the plant.

The inclusion of two additional Unit I load groups and associated batteries provides greater reliability and capacity for powering B0P 125 VDC loads. No unreviewed safety questions were identified as a result of the enhancement described in this FSAR change.-

FACILITY DESCRIPTION CHANGE: Yes i

J19ATTC86123001 - 150

Attachment to AECM-87/0019 SRASN: NPE-86-176 DOC N0: CN-3445-CUCNR0077 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.2-1 was revised by the addition or modification of design information concerning the components in the Off-Gas System.

REASON FOR CHANGE: To provide clarification and additional information regarding the design of the Off-Gas System.

SAFETY EVALUATION: The change to the FSAR does not alter the design, configuration, or operation of the Off-Gas System.

Therefore, accident analyses and equipment important to safety are not affected. No Technical Specification change or unreviewed safety questior, was involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes i

l l

J19ATTC86123001 - 140

Attachment to AECM-87/0019 SRASN: NPE-86-177 DOC N0: CN-3445-CUCNR0091 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.2-3 was revised by providing a correlation of safety classes with other design information.

REASON FOR CHANGE:= To provide clarification and consistency with Table 3.2-1 of the FSAR.

SAFETY EVALUATION: The change to the FSAR does not alter the design, plant configuration, or operation. No Technical Specification change was required for this change to the FSAR and no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes 4

J19ATTC86123001 - 139

, . . , _ __-y _ _ _ , _ . - _ . , _ ~ _ , , , _ _ , _ . . _ , - , . , . _ . ,,.m,, . - , _ . _ , , , _ -, , , . . _ , , . . _ . , _ _ _ , _ . _ _ _ , _ _ , , . _ . _ , _ _ _ _ _ _ _

Attachment to AECM-87/0019 SRASN: NPE-86-178 DOC N0: CN-3445-CUCNR0095 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.2-1 Item XIX, 12 was added to reflect a sample station as a principal component of the Reactor Water Cleanup System.

REASON FOR CHANGE: To reflect the current plant configuration and to provide consistency with other FSAR information.

SAFETY EVALUATION: This change to the FSAR does not introduce any design changes and the system performance is not altered. No new failure modes are created. No Technical Specification changes or unreviewed safety questions were involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes

.I i

J19ATTC86123001 - 138

Attachment to AECM-87/0019 SRASN: NPE-86-179 DOC N0: CN-3445-CUCNR0096 SYSTEM: N/A DESCRIPTION OF CHANGE: This change revises Table 3.2-1 to change identification of Leak Detection System components from temperature elements, switches, etc., to generalized headings of electrical modules, instrumentation, etc. Also, it revises the Scope Supply Code, the Location Code, and the Principal Construction Code to reflect current plant configuration and to meet the original design requirements.

REASON FOR CHANGE: This change is intended to clarify the codes used in Table 3.2-1.

SAFETY EVALUATION: This change clarifies the codes used in Table 3.2-1. There is no effect on operations or on any system or component and no change to the original design requirements. The change does not degrade or prevent action described in Chapter 15

" Sequence of Events" Tables for accident analyzed. .There is no impact on Technical Specifications or the margin of safety. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes I

i l

i J19ATTC86123001 - 161

Attachment to AECM-87/0019 SRASN: NPE-86-180 DOC N0: CN-3445-CUCNR0106 SYSTEM: N/A DESCRIPTION OF CHANGE: This change revises Items 1, 2, 3, 6,-7, 8, 10, 11 under Section XIX of UFSAR Table 3.2-1 to provide a more definitive and consistent classification of the systems, components, or structures currently listed in this Table.

REASON FOR CHANGE: This change is for the purpose of clarifying Table 3.2-1 and does not change any plant system or components itself.

SAFETY EVALUATION: This change revises Table 3.2-1 only and provides criteria and classification information that is consistent with the original design criteria. There is no effect on any system or component, or on Technical Specifications or the margin of safety. Therefore, no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 162

~

Attachment to AECM-87/0019 SRASN: NPE-86-181 DOC N0: CN-3297-CUCNR0110 SYSTEM: 833 DESCRIPTION OF CHANGE: This FSAR change revised the Reactor Recirculation Pump (Q1B33C001A-N and Q1833C0018-N) motor horsepower rating from 7940 HP to 8099 HP on FSAR Figure 8.1-1.

REASON FOR CHANGE: To be consistent with FSAR Table 5.4-1 and to agree with the actual motor. nameplate rating.

SAFETY EVALUATION: This FSAR change provided no adverse safety or operational impact. No unreviewed safety questions or Technical Specification changes were identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 102

Attachment to AECM-87/0019 SRASN: NPE-86-182 DOC N0: CN-3445-CUCNR0118 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.2-1 was revised by correcting the Quality Group Classification in Sections II.5, II.19, and III.2.Section II.19 and III.3 were revised by correcting the Principal Construction Code.Section V.7 and V.8, III.2, and III.3 were revised to provide a more precise description of the component boundaries.

REASON FOR CHANGE: To maintain Table 3.2-1 consistent with plant design criteria and the FSAR text.

SAFETY EVALUATION: This change to the FSAR does not provide physical changes to or affect the integrity of equipment. The change is consistent with original design criteria and the FSAR text. No Technical Specification change or unreviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 163

Attachment to AECM-87/0019 SRASN: NPE-86-183 DOC N0: CN-3265-CUCNR0152 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 8.1.4.1d, 8.1.4.2.1, and FSAR Figure 8.2-4 were revised to reflect that the AC power supplies for the switchyard are connected to the 13.8KV/480V station service transformer instead of. Unit 2 Div. II ESF.

REASON FOR CHANGE: To reflect the current as-built condition of Unit 1.

SAFETY EVALUATION: The change is bounded by previous analyses for accident consequences. The reliability of the offsite power system has not been changed. Plant design precludes failure of any portion of the offsite power system from creating a malfunction of equipment important to safety. No Technical Specification change or unreviewed safety question was involved for this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes i

4

~

J19ATTC86123001 - 103

Attachment to AECM-87/0019 SRASN: NPE-86-184 DOC N0: CN-3345-CUCNR0155 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised FSAR 9.5.6.2.2 and FSAR Figure 8.3-12b to indicate that the HPCS (Div. III)

Diesel Generator's electric motor-driven standby air compressor is powered from a non-class 1E electrical power supply.

. REASON FOR CHANGE: To update the FSAR to reflect a General Electric design change that was physically implemented prior to issue of the GGNS operating License. This design change was required to meet Regulatory Guide 1.75 requirements.

SAFETY EVALUATION: Per FSAR Figure 9.5-13a the HPCS Diesel Generator's electric motor-driven starting air compressor is non-safety related. Regulatory Guide 1.75 required that non-class 1E loads be separated from class 1E power supplies.

Therefore, the electrical motor-driven starting air compressor's electrical power source was changed to a non-class 1E electrical power source. ho Technical Specification change or unreviewed safety question was identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes l

J19ATTC86123001 149

Attachment to AECM-87/0019 SRASN: NPE-86-185 DOC N0: CN-3124,3125-CUCNR0073 SYSTEM: N/A DESCRIPTION OF CHANGE: The following Sections of Table 3.2-1 in the FSAR were revised to provide a more definitive and consistent classification of the systems, structures, or components listed in the Table: 1.2,4,5,6, and 9; XIII.1,2,3 and 4, XIV.1, and 2; XV.1: XVI.1,2,3, and 4; XVII.1, and 2; and XLVI.1 through 19 and Note P. In addition classification of New Fuel Inspection Stand is being added to Section XIII. The changes above include the substitution of a specific reference to the applicable code, or with the term "other" while making reference to a clarifying note, in lieu of using the term "none". Also, the safety classes and/or Seismic Categories of the Fuel Service Equipment, Reactor Vessel Service Equipment, Invessel Service Equipment, and Refueling Equipment were changed to be consistent with plant design criteria and the FSAR text. The Essential, Safety and Seismic Classifications in Tables 9.1-2 & 9.1-3 were also revised to be consistent with the applicable design criteria and FSAR text.

REASON FOR CHANGE: This change provides a more consistent classification of the systems, structures, and components listed in Table 3.2-1, and makes other minor changes to be consistent with plant design criteria and the UFSAR text.

SAFETY EVALUATION: This change is to the text of the UFSAR and does not modify any plant systems or equipment or operations.

Therefore there is no impact on Technical Specifications or on the margin of safety. There is no new failure mode created, nor is there any increase in the probability or the consequences of an accident or malfunction of equipment important to safety.

Therefore, no unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 135 .

Attachment to AECM-87/0019 SRASN: NPE-86-186 -DOC N0: CN-3415-CUCNR0076 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change added design codes for ductile concrete expansion anchors to FSAR Sections 3.8.1.2.2.1 and 3.8.3.2.2.1 from ACI 349-80, Appendix B, Section B.7 including the'1984 Supplement.

REASON FOR CHANGE: To provide a basis for the future use of ductile concrete expansion anchors at GGNS.

SAFETY EVALUATION: This FSAR change did not adversely affect plant safety or operations. Use of ductile concrete expansion anchors will be analyzed on a case-by-case basis. This will ensure adequate anchorage by remaining within design allowable limits for shear and tension, and the combined effects of shear and tension. No unreviewed safety questions or Technical Specification changes were identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 104

Attachment to AECM-87/0019 SRASN: NPE-86-191 DOC N0: DCP-82-704-(CN-3234) SYSTEM: P64 DESCRIPTION OF CHANGE: The halon system detector numbers were changed to reflect the correct system number of P64 rather than P65.

REASON FOR CHANGE: To reflect the proper equipment numbers for the detectors which are used to activate fire suppression and thus are part of the Fire Protection System (P64) rather than the Fire Detection System (P65).

SAFETY EVALUATION: No electrical or mechanical equipment or system changes are involved. The only change will be to replace nameplates and update drawings to clarify the equipment number.

There was no Technical Specification change associated with this FSAR change and no unreviewed safety question was identified.

J19ATTC86123001 - 105

Attachment to AECM-87/0019 SRASN: NPE-86-195 DOC N0: CN-3383-CUCNR0108 SYSTEM: N/A DESCRIPTION OF CHANGE: Various pages of the FSAR, Chapter 7, were revised to standardize the use of the terms " Channel", " Trip System", and " Trip Function". Missing isolation signals were ,

,added to Section 7.3.1.1.2 tables. Reference to the fuel grapple 1 interlock in the Refueling Interlock System was deleted. Also, the first sentence in d. of Section 7.3.1.1.1.6.4 concerning the LPCI injection valves was deleted.

REASON FOR CHANGE: To provide consistency with the Technical Specification terminology, to provide clarity, and to reflect present plant design.

SAFETY SVALUATION: No procedure or hardware changes were necessitated by this change to the FSAR. The changes are descriptive-in nature and provide clarification. There is no change to the existing facility. This change to the FSAR did not involve an unreviewed safety question and no change to the Technical Specifications was required.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 107

Attachment to AECM-87/0019 SRASN: NPE-86-197 DOC N0: CN-3186-CUCNR0018 SYSTEM: 210 DESCRIPTION OF CHANGE: FSAR Figure 9.1-26 was changed to reflect the deletion of the vortex breaker shown in the spent fuel pool on line 20 inch-HCC-24.

REASON FOR CHANGE: To reflect the as-built condition.

SAFETY EVALUATION: This change did not alter the system operation as confirmed by testing. The change had no impact on system operation and did not introduce rew interfaces or interactions with other safety related systems, structures or components. No Technical Specification changes were required and there were no unreviewed safety questions involved with this

, change.

FACILITY DESCRIPTION CHANGE: Yes a

J l

l 1.

a k

4 J19ATTC86123001 - 108

Attachment to AECM-87/0019 SRASN: NPE-86-198 DOC N0: CN-3436-CUCNR0031 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 5.2.5.2k was added to incorporate the material formerly in Q&R 110.48 and minor errors were corrected. This material discusses high/ low pressure interfaces of various systems with the reactor coolant system.

REASON FOR CHANGE: To incorporate material into the main body of the FSAR and to reflect current as-built plant conditions as previously contained in the Q&R response.

SAFETY EVALUATION: This change to the FSAR does not reduce the ability of the systems to function as high/ low interfaces, so the consequences of an accident are not increased. The probability or consequences of equipment malfunction are also not increased.

No Technical Specification changes are required and no unreviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 109

4 Attachment to AECM-87/0019 SRASN: NPE-86-199 DOC NO: CN-3271-CUCNR0036- SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 8.3.1.1.4.1(1) was revised to describe how normal surveillance testing permits the testing of only a single diesel generator set at a time and by deleting the reference to a key lock mode switch.

REASON FOR CHANGE: To provide consistency with other FSAR sections and drawings.

SAFETY EVALUATION: This change to the FSAR does not modify any equipment in the plant and does not affect any plant condition.

No Technical Specification change or unresolved safety question was involved with this change.

. FACILITY DESCRIPTION CHANGE: Yes I

i 1

J i

4 i

i E

i i

i l

f

J19ATTC86123001 - 165

, _ _ , . . . _ _ _ _ _z_ ._.-_.. ..__._ _ __ ___ _ ._ . _ . . _ - _ . _ . _ _ _ _ _ _ _ .

Attachment to AECM-87/0019 SRASN: NPE-86-200 DOC N0: CN-3455-CUCNR0037 SYSTEM: N/A DESCRIPTION OF CHANGE: Table 9.5-15 was added to incorporate the material formerly in Q&R 40.41 and to indicate that no emergency battery packs are provided for certain Auxiliary Building Switchgear Rooms. Additionally, the number of Switchgear Rooms on EL.166 of the Auxiliary Building is changed from 4 to 2.

REASON FOR CHANGE: To reflect current as-built conditions and to incorporate.Q&R material into the main body of the FSAR.

SAFETY EVALUATION: The only substantial change was the addition of a note regarding no emergency battery packs in the Switchgear

-Rooms._ This addition was not germane to accident precursors and does not create the possibility of equipment malfunctions. No Technical Specification change or unresolved safety question was involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 110

Attachment to AECM-87/0019 SRASN: NPE-86-201 DOC N0: CN3305-CUCNR0044R01 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 3.11 was revised to clarify the GGNS EQ program including deletion of Tables 3.11-4 through 3.11-7 and the addition of a reference to MP&L's Environmental Qualification Files at the GGNS site. Some of the parameters were changed to agree with MP&L's response to NUREG-0588.

REASON FOR CHANGE: To reflect the current status of the Environmental Qualification program.

SAFETY EVALUATION: .This change does not affect the originally {

evaluated accident scenarios and the probability / consequences of equipment malfunction is not increased. No Technical Specification change or unresolved safety question was identified by this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 131

Attachment to AECM-87/0019 SRASN: NPE-86-202 DOC N0: CN3311-CUCNR0050R01 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 3.1, 5.2, 5.3 and 6.6 were s revised to reflect the correct edition / addenda of the ASME Code,

, to revise references for flaw inspection, and to update the information concerning submittals of preservice and inservice inspection and testing programs and plans.

REASON FOR CHANGE: To provide consistency with the Inservice Inspection and Testing program.

1

SAFETY EVALUATION

Performance of the ISI program should minimize the possibility of pressure boundary malfunction by early detection of degradation. The probability and consequences of an accident are not affected by this change. No Technical Specification change and no unreviewed safety question were identified by this change to the FSAR.

FACILITY DESCRIPTION CHANGE: No J

i

)

l 4

! l I

i i

! J19ATTC86123001 - 132 I

_ . . . _ . - _ _ _ _ _ . _ _ _ _ _ _ . _ .__ _ . _ 1 ,.._. _ _ .__ _ _ __ _ _ , . , _ . _ . _ - . _ _ _ - . _ _ - .

Attachment to AECM-87/0019 SRASN: NPE-86-203 DOC NO: CN3342, 3369-CUCNR0051 SYSTEM: N/A DESCRIPTION OF CHANGE: Figures in FSAR Chapter 5 and Appendix 5A were changed to show that the closure of the safety-relief valves would begin when the pressure drops to 0.98 times the nominal opening pressure setpoint.

REASON FOR CHANGE: To provide consistency with analyses performed in Chapter 5, 6, and 15 of the FSAR.

SAFETY EVALUATION: This change only corrects the FSAR to be consistent with the safety analysis. There is no change in the actual closing setpoints of the safety-relief valves in the plant or in the safety analysis. No Technical Specification change was identified for this change and there was no unreviewed safety question involved with the change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 133

I Attachment to AECM-87/0019 SRASN: NPE-86-204 DOC N0: CN-3273-CUCNR0060 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised performance data for the Control Building Air-Conditioning System's fan-coil unit, and the computer Room Air-Conditioning System's fan-coil units in FSAR Table 9.4-13. Also, performance data for the Control Building Elevator Machinery Room Unit Heater was added to FSAR Table 9.4-13.

REASON FOR CHANGE: To accurately reflect pre-operational test results for the affected components in FSAR Table 9.4-13.

SAFETY EVALUATION: Per FSAR 9.4.10.3 the Control Building L Air-Conditioning System, the Access Control Area Air-Conditioning System, the Computer Room Air-Conditioning System, and the Control Building Elevator Machinery Room Unit Heater have no safety related functions. Failure or reduced performance of these systems will not compromise any safety related system or component and will not prevent safe reactor shutdown. No Technical Specification change or unreviewed safety question was identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes 1

i l

l i l l

F I J19ATTC86123001 - 147

Attachment to AECM-87/0019 SRASN: NPE-86-205 DOC N0: CN-3420-CUCNR0061 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Chapters 3 and 6 were changed to reflect revised blowdown data and compartment pressures resulting from various postulated high energy piping breaks inside containment and in the Auxiliary Building.

REASON FOR CHANGE: To reflect the slower Reactor Water Cleanup isolation valve closure times, rerouted piping, and a revision in the vent path analytical model.

SAFETY EVALUATION: This change to the FSAR is for a design analysis only and does not constitute a physical modification or change to the system configuration. The adequacy of the existing structures was confirmed. There is no increase in the probability or consequences of an accident or malfunction of equipment important to safety. No Technical Specification change or unreviewed safety question was identified by this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 130

Attachment to AECM-87/0019 SRASN: NPE-86-206 DOC N0: CN-3314-CUCNR0107 SYSTEM: N/A DESCRIPTION OF CHANGE: Section 2.3.4.3 of the FSAR and Table 2.3-187 were revised to delete information pertaining to the previous methodology for calculating.the relative concentration, Chi /Q, at the Control Room Emergency Intake for vhrious accidents.

REASON FOR CHANGE: To delete information which has been replaced by new information on Control Room Chi /Q methodology approved by the NRC.

SAFETY EVALUATION: This change to the control room intake Chi /Q methodology and the related revisions to the post accident control room habitability analysis were reviewed and approved by the NRC as reflected in Supplement 6 to the Safety Evaluation Report.

Equipment important to safety was not affected. No Technical Specification change or unreviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 125

Attachment to AECM-87/0019 SRASN: NPE-86-207 DOC N0: CN-3467-CUCNR0131R01 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Tables 3.10-3 and 3.10-4 had indicated that Foxboro instruments, meters, and required accessories were used in the remote shutdown panels. These tables were revised to show that Bailey instruments and GE 180 meters are used.

REASON FOR CHANGE: To reflect the use of Bailey instruments and GE 180 meters in the Remote Shutdown Panels.

SAFETY EVALUATION: The installed equipment has been proven reliable and is qualified for the intended service. The original design functions of the equipment have been maintained by this change. No Technical Specification change or unreviewed safety question was identified for this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 126

Attachment to AECM-87/0019 SRASN: NPE-86-208 DOC N0: CN-3324-CUCNR0133 SYSTEM: N/A DESCRIPTION OF CHANGE: The Fire Hazards Analysis (formerly FSAR Appendix 9A) was revised to reflect various changes in the program based on reanalysis conducted to meet the requirements of 10 CFR 50, Appendix R.

REASON FOR CHANGE: To reflect a current description of the FHA for meetir.g the provisions of Appendix R to 10 CFR 50 and to provide a clearer definition of the fire protection program.

SAFETY EVALUATION: Th% change did not reduce the overall adequacy of the fire protection program, and no other hazards or inappropriate system interactions were introduced. No Technical

~

Specification chang? cr unreviewed safety question was introducad by this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 127

Attachment to AECM-87/0019 SRASN: NPE-86-209 DOC NO: CN-3314-CUCNR0143 SYSTEM: N/A

, DESCRIPTION OF CHANGE: The FSAR was changed to reflect a revised discussion of the SGTS exhaust rate during drawdown of the secondary containment. The revised discussion reflects the actual operating characteristics and performance of the SGTS. i l REASON FOR CHANGC: To reflect the operating characteristics of j the SGTS for drawdown of secondary containment.

SAFETY EVALUATION: This change reflects actual characteristics j and performance as verified by testing and does not alter the

! design, configuration, or operation of the facility. There is no I

. adverse impact on equipment important to safety. No Technical Specification change was required for this charge and no unreviewed safety question was identified.

i FACILITY DESCRIPTION CHANGE: Yes I

i l

l 1

i >

1 i

i ,

l -i i

1 l

I i

i I

I l J19ATTC86123001 - 128 I

i

Attachment to AECM-87/0019 SRASN: NPE-86-210 DOC NO: CN-3397,3445-CUCNR0045 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 3.2-1 was expanded to include additional data for the principle _ components concerning safety class, quality group, seismic category, etc. FSAR Section 9.5.4.1.lc was revised to be consistent with Table 3.2-1.

REASON FCR CHANGE: To provide consistent classification of the systems, structures, and components listed in the FSAR tables.

SAFETY EVALUATION: This change to the FSAR did not affect the operation, integrity, or function of the equipment. The change was consistent with the original design criteria. No Technical Specification change and no unreviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 136

Attachment to AECM-87/0019 SRASN: NPE-86-211 DOC N0: CN-3473-CUCNR0083 SYSTEM: N/A

! DESCRIPTION OF CHANGE: FSAR Section 5.3 was revised by the deletion of specific references to Appendix G or H of 10CFR50 and replacement with a generic reference to the appropriate Appendix.

REASON FOR CHANGE: To reflect current requirements of 10CFR50 Appendix G and H.

SAFETY EVALUATION: This change to the FSAR did not involve the

, addition, change, or deletion of technical information that would affect any installed hardware or operating procedures. No hardware or procedural changes were made. The changes were clarification of commitments or requirements. No direct Technical Specification change or unreviewed safety question was involved with this change. However, a proposed Technical Specification change for the Unit 1 RPV Pressure VS Temperature Curve was submitted in AECM-86/0351 as an indirect result of this

' FSAR change.

FACILITY DESCRIPTION CHANGE: Yes l

4 i

4 J19ATTC86123001 - 141

Attachment to AECM-87/0019 SRASH: NPE-86-212 DOC NO: CN-3311-CUCNR0097 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 3.9.6 was revised to identify Specification MP&L-M-189.1 as the base document for Inservice Testing of pumps and valves. Section 5.4.13 was revised to reflect that inspection and testing of safety / relief valves is in accordance with the ASME Code,Section XI. Section 5.4.7 was revised to delete reference to a RCIC head spray line and to reflect that valves in the RHR system that perform a high-pressure low-pressure boundary are considered Category A valves. Section 6.3 was revised by adding a statement that Inservice Testing is discussed in Section 3.9.6 and by adding a paragraph stating that valves performing an isolation function to protect the low-pressure portions of the ECCS from full reactor pressure will be leak rate tested as Category A valves and that check valves performing the same function will be Category A and C valves.

REASON FOR CHANGE: To provide clarification and to reflect'the use of Specification MP&L-M-189.1 as the base document for Inservice Testing.

SAFETY EVALUATION: The change to the FSAR addresses the performance of Inservice Testing which is not a basis for an accident and does not affect the evaluated consequences of a malfunction of equipment. Performance of Inservice Testing provides added assurance for the safe operation of pumps and valves. No Technical Specification change or unreviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 142

Attachment to AECM-87/0019 SRASN: NPE-86-213 DOC NO: CN-3343-CUCNR0123R01 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 15.2 and associated tables were revised to reflect a change in the condenser vacuum transient analysis such that the vacuum decay rate is 10 inches Hg/sec rather than 2 inches Hg/sec.

REASON FOR CHANGE: To reflect new analyses conducted for changes in as-built conditions.

SAFETY EVALUATION: The faster vacuum decay results in higher system pressures, but they remain lower than for other reported events. Changes reflected as operator actions only involved clarifying phrases or did not involve an action that would increase the probability of an accident. No Technical Specification change or unreviewed safety question was involved with this change.

FACILITY DESCRIPTION CHANGE: Yes l

l r

J19ATTC86123001 - 137

Attachment to AECM-87/0019 SRASN: NPE-86-214 DOC N0: ,CN-3413-CFSAR84-0159R00 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 3.8 was revised to clarify the design codes of the Containment and Drywell.

REASON FOR CHANGE: To reflect the as-built condition of the plant.

I SAFETY EVALUATION: Thic iange.to the FSAR did not affect the probability or consequeri of any previously evaluated accident and no new accident scenarios were created. There were no Technical Specification changes or unreviewed safety questions involved with this change.

FACILITY DESCRIPTION CHANGE: Yes t

i

)

I J

i l

i

J19ATTC86123001 - 143 i

- - - . _ _ . _ -- ~ _ _ _ _ _ _ _ _ _... _ . _ _... _ _ _ _ - -._ _ _ _ . . -

Attachment to AECM-87/0019 SRASN: NPE-86-215 DOC N0: CN-3433-CFSAR3433R00 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Figures 6.3-8, -63, -64, -65, and -66 were revised to reflect a reanalysis of the main steam line break which does not take credit for HPCS operation.

REASON FOR CHANGE: To reflect the results of the reanalysis that was performed since the actuating level instrument for the HPCS may not be considered reliable due to drywell environmental conditions.

SAFETY EVALUATION: There was no increase in the probability or consequences of equipment malfunction or of an accident previously evaluated in the FSAR. No Technical Specification changes or unreviewed safety questions were involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 144

1 Attachment to AECM-87/0019 SRASN: NPE-86-216 DOC N0: CN-3183-CUCNR0148 SYSTEM: N/A DESCRIPTION OF CHANGE: These changes to the FSAR encompass figures that are adaptations of design drawings which were updated to reflect later revisions of the design drawings. No FSAR text changes are associated with these modifications.

REASON FOR CHANGE: To incorporate revised FSAR Figures which were based on design drawings that involve various changes made through the established configuration control process.

SAFETY EVALUATION: Changes to the plant reflected in the drawings received the necessary 10CFR50.59 applicability screening and evaluation as appropriate. A majority of the changes involved minor editorial or other clarifying changes and did not increase the probability of an accident. No Technical Specification change or unreviewed safety question was involved with this change to the FSAR.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 166

Attachment to AECM-87/0019 SRASN: NLS-86-013 DOC N0: CN-3131-NLS-SE-025 SYSTEM: N/A DESCRIPTION OF CHANGE: UFSAR Section 9.5.4.3 incorporated an exception to Section 4.3 of ANSI N195-1976 from that previously discussed in FSAR Q&R 40.44 since the Diesel Generator Fuel Oil Storage Tank's fill and vent connections are not in a vital area.

REASON FOR CHANGE: To correct a discrepancy between the as-built plant condition (and GGNS Physical Security Plan) and the FSAR description.

SAFETY EVALUATION: Justification for the exception to Section 4.3 of ANSI N 195-1976 was provided to the NRC via letter (AECM-83/0504) dated August 26, 1983 and during subsequent discussions. This justification was judged by the NRC staff to be acceptable.

No unreviewed safety nuestion or Technical Specification change was identified as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: Yes s

J19ATTC86123001 - 111

Attachment to AECM-87/0019' SRASN: NLS-86-014 DOC NO: CN-3328-NLS-SE-86-007 SYSTEM: N/A DESCRIPTION OF CHANGE: The amount of chlorine shipped down the Mississippi River, per FSAR 2.2, is updated. The chlorine barge accident is eliminated as a Design Basis Event.

REASON FOR CHANGE: Probabilistic evaluation conservatively shows the probability of a chlorine accident on the Mississippi River is about 1.8 X 10-7 per year which is within NRC Acceptance Criteria for the elimination of the accident as a Design Basis event.

SAFETY EVALUATION: This change addresses an offsite potential situation that has no effect on Technical Specifications, or systems or equipment. (Although this particular change to the FSAR has no effect on the Technical Specifications, the same information has been used as a part of the justification for a separate change deleting control room detectors from the Technical Specifications. That change was reviewed and approved by the NRC prior to changing the Technical Specifications.) This change does not decrease the margin of safety or change previous environmental evaluations.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 112

Attachment to AECM-87/0019 SRASN: NLS-86-015 DOC N0: CN-3475-NLS-SE-86-0010 SYSTEM: N/A DESCRIPTION OF CHANGE: This change removes the technical i

references to and description of the Emergency Facility Information S System (SPDS)ystem from the FSAR. (ERFIS) and These arethe Safety Parameter information systems used Display to provide data to the Control Room, the Technical Support Center (TSC), and Emergency Operations Facility (EOF) when required.

Both systems are non-safety reifted.

REASON FOR CHANGE: The EFIS and SPDS are required to be modified by NUREG 0737 Supplement 1. The modification was done during the first refueling outage. The FSAR currently does not accurately describe these systems. This change removes incorrect information from the FSAR. A later FSAR update will include a revised description of the ERFIS/SPDS which will accurately describe the system functions, requirements, and operation.

i SAFETY EVALUATION: The ERFIS/SPDS Systems are not safety related i and do not mitigate any accident or emergency condition. No safety related functions, procedures, or actions previously evaluated will be adversely affected by this change. There is no impact on Technical Specifications and no unreviewed safety question is identified by this change.

FACILITY DESCRIPTION CHANGE: Yes i

u I

i J19ATTC86123001 - 113

Attachment to AECM-87/0019 SRASN: NLS-86-016 . DOC NO: CN3328-NLS-SE-86-008 SYSTEM: N/A DESCRIPTION OF CHANGE: This change revises Tables 2.2-2 and 2.2-3 to reflect more recent information on the amounts of hazardous materials annually transported on the Mississippi River. The total amounts of toxic and flammable chemicals shipped per year have increased over the amounts previously listed in the FSAR.

REASON FOR CHANGE

This change incorporates more accurate

information concerning hazardous material river traffic into the UFSAR.

SAFETY EVALUATION: The UFSAR discussion of hazardous material accidents is not affected by the increased quantities of hazardous materials listed in Tables 2.2-2 and 2.2-3. Analyses were re-evaluated to show that the increased loads of traffic have no effect on any accident analysis or on any system or on any equipment important to safety. There is no effect on Technical Specifications or on any margin of safety.

, FACILITY DESCRIPTION CHANGE: No l

l i

a I

J19ATTC86123001 - 114

{

Attachment to AECM-87/0019 SRASN: NLS-86-017 DOC N0: CN-3302-NLS-SE-86-019 SYSTEM: N/A DESCRIPTION OF CHANGE: This change adds to Section 18.1.36 a statement concerning the potassium iodide supply that will be maintained in the Control Room. The statement reads, "...a sufficient supply of 130 mg. tablets is maintained." The FSAR currently states only that a potassium iodide supply will be provided.

REASON FOR CHANGE: To clarify the FSAR for potassium iodide supply.

SAFETY EVALUATION: This change does not affect Technl cal Specifications, or the margin of safety, or any plant s,.' stem or equipment. N0 unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 156

i Attachment to AECM-87/0019 SRASN: NLS-86-019 DOC N0: CN-3313-NLS-SE-0011 SYSTEM: E12 DESCRIPTION 0F CHANGE: This change created UFSAR Section 6.2.1.1.5.8 to discuss Humphrey Issue 14.0 which concerns a potential containment pressurization flow path through a failed LPCI check valve into the containment spray header. Analysis indicated that back flow could raise containment pressure by a maximum of 0.8 psig. Since sprays are actuated at 9.0 psig, a maximum pressure of 9.8 psig could be attained before containment pressure starts to go down. This presents no concern since maximum backflow increases containment pressure by less than 1 psig.

REASON FOR CHANGE: This change addressed and answered the concerns raised by Humphrey Issue 14.0, which concerned a failure in the check valve in the LPCI line to the reactor vessel that could result in direct leakage from the pressure vessel to the containment atmosphere.

SAFETY EVALUATION: Since the maximum expected pressure of 9.8 psig does not exceed the maximum containmer,t internal design pressure of 15 psig, there is no impact on technical Specifications. Also, no new failure mode is created, and there is no increased in the probability or consequences of an accident or of a malfunction of equipment important to safety. Therefore, no unreviewed safety question was created.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 115

Attachment to AECM-87/0019 SRASN: NLS-86-020 DOC N0: CN-3313-NLS-SE-86-0012 SYSTEM: N/A DESCRIPTION OF CHANGE: This change incorporates descriptions of analyses of concerns raised by Humphrey Issues 5.1, 5.t . 9.2, 5.5, 5.8 into FSAR~Section 6.2.1.1.5.5 or into a new Section 6.2.1.1.5.6 as appropriate. The analyses showed that the Small Break Accident (SBA) is bounding and that: containment pressurization remained below the design pressure of 15 psig; that local temperature rises near leak paths raise no environmental qualification concerns; that peak drywell temperature in the presence of small breaks does not exceed the drywell design temperature. The new section 6.2.1.1.5.6 was created to deal with local temperature effects of bypass leaks.

REASON FOR CHANGE: This change addresses some of the concerns raised by Humphrey Issues.

SAFETY EVALUATION: Analysis indicated that Technical Specification 3.6.2.2, "Drywell Bypass Leakage", is bounding, and therefore, there is no impact on Technical Specifications. No new failure mode is created, and there is no increase in the probability or consequences of an accident or of a malfunction of equipment important to safety. There is no impact on the margin of safety. Therefore, no unreviewed safety question is created by this change.

FACILITY DESCRIPTION CHANGE: No 9

i i

l J19ATTC86123001 - 116

Attachment to AECM-87/0019 SRASN: NLS-86-021 DOC N0: CN-3313-NLS-SE-86-0013 SYSTEM: M24 DESCRIPTION OF CHANGE: This change is a sumary of the analysis of the effects of differences in water elevation between suppression pool and drywell weir annulus on load definition for vent clearing. Within the bounds of Technical Specifications, whenever the weir wall level is lower, there are lower loads in the suppression pool area. When weir wall level is up to 7 inches higher, only very small changes for bubble loads and pool swell occur, and those are bounded by existing conservatisms in the pool swell load definitions.

REASON FOR CHANGE: 'This change provided a summary of the analysis of the effects of differences in elevation between suppression pool and drywell weir annulus on load definition for vent clearing.

SAFETY EVALUATION: Any differences in water elevation between the weir annulus and the suppression pool that are within (

Technical Specification bounds result in either reduced vent I clearing inertia, reduced pool swell response and loads, or in a slight change in load definition which is of no safety concern and is bounded by existing conservatisms in the pool swell load definitions. There is, therefore, no impact on Technical Specifications, the margin of safety, or the structural integrity of systems and components. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: No J19ATTC86123001 - 157 1

Attachment to AECM-87/0019 SRASN: NLS-86-022 DOC N0: CN-3313-NLS-SE-86-0014 SYSTEM: M24 DESCRIPTION OF CHANGE: This change consists of the addition of a new section to the UFSAR (Section 6.2.2.3.2) which addresses the various suppression pool stratification issues rising from Humphrey Issues. The analyses demonstrated that the suppression pool operates within design limits.

REASON FOR CHANGE: This change addressed and answered the concerns of the Humphrey Issues as they pertained to suppression pool stratification and mixing issues.

SAFETY EVALUATION: The analyses show that the suppression pool operates within design limits. Therefore, no new failure mode is created. There is no increase in the probability or consequences of an accident or of a malfunction of equipment important to safety. No change to the Technical Specifications is required due to this change. No unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: No i

I l

l 1

J19ATTC86123001 - 158

Attachment to AECM-87/0019 SRASN: NLS-86-023 DOC N0: CN-3313-NLS-SE-86-0015 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 6.2.2.3.1 was revised to state that to maintain maximum efficiency in containment cooling and pool cooling, spray cycling would not be required. Also, spray cycling may be increased by bypass leakage. Analytical results were provided.

REASON FOR CHANGE: To incorporate the analysis of Humphrey Issues 4.9 and 5.3, provided to the NRC in correspondence (AECM-82/353, dated 8/19/82 and AECM-82/497, dated 10/22/82).

SAFETY EVALUATION: Analysis results.are consistent with Technical Specifications and within design limits. There is no effect on systems / components, no change in limiting conditions for operation or surveillance requirements, no effect on margin of safety, and no environmental impact. No unresolved safety question was identified by this change.

^

FACILITY DESCRIPTION CHANGE: No l

i l

l i

l f

J19ATTC86123001 - 153

Attachment to AECM-87/0019 SRASN: NLS-86-024 DOC N0: CN-3313,NLS-SE-86-0016 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 6.2.2.3.1 was changed to state that transfer of the RHR System from the suppression pool cooling mode to the containment spray mode reduce; the heat transfer from the suppression pool.

REASON FOR CHANGE: To address Humphrey Issue 4.8, previously addresset in correspondence to the NRC (AECM-82/353 dated 8/19/82 and AECM 80/497 dated 10/22/82).

SAFETY EVALUATION: Analysis results are within design limits and therefore consistent with Technical Specifications. Analyses indicate probability or consequences of occurrence of previously evaluated accident is not increased; also, probability or consequences of malfunction of equipment important to safety not increased; possibility of accident or malfunction of equipment important to safety different than previously evaluated in FSAR not created. No effect on structural integrity or operability of systems and components, therefore no effect on margin of safety.

FACILITY DESCRIPTION CHANGE: No i

J19ATTC86123001 - 148

Attachment to AECM-87/0019 SRASN: NLS-86-025 DOC N0: CN-3392-NLS-SE-86-003 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised Appendix 13A to update the resumes of key personnel associated with the operation of GGNS.

REASON FOR CHANGE: To provide the current status of experience for individuals fulfilling GGNS positions.

SAFETY EVALUATION: This FSAR change was administrative in nature and did not adversely affect plant safety or operations. No unreviewed safety question or Technical Specification changes were generated by this FSAR.

FACILITY DESCRIPTION CHANGE: No l

l l

L I

l l

l .

i -J19ATTC86123001 - 117 i

Attachment to AECM-87/0019

'SRASN: NLS-86-026 DOC N0: CN-3452,3451,3476-NLS-SE-86-002 SYSTEM: N/A DESCRIPTION OF CHANGE: These FSAR changes revised FSAR Appendices 10A, 6D, 2.3A, 2.5A, 2.58 and 2.5C by deleting the text of the appendices and adding a reference for location of the deleted information.

REASON FOR CHANGE: Information containment in the affected appendices was not required for retention in the Updated FSAR.

SAFETY EVALUATION: These FSAR changes did not adversely affect plant safety or operations. The information contained in the deleted appendices was not changed and is available via the reference provided in the revised FSAR Appendices. No unreviewed safety question or Technical Specification changes were generated as a result of these FSAR changes.

FACILITY DESCRIPTION CHANGE: No i

4 i

?

i i

1 i

i J19ATTC86123001 - 118

Attachment to AECM-87/0019 SRASN: NLS-86-027 DOC N0: CN-3328-NLS-SE-86-009 SYSTEM: N/A 2

DESCRIPTION OF CHANGE: This FSAR change revised the following:

(1) FSAR 2.2.1 to update the airlines servicing the Jackson, Mississippi and the Natchez-Adams County Airports; (2) the last paragraph of FSAR 2.2.1 to indicate the non-use of the railroad track 2.75 miles east-southeast of the GGNS site; (3) the second paragraph of FSAR 2.2.2.5 to indicate the current status of airport development within a 50 mile radius of GGNS: (4) FSAR 2.2.2.6 to indicate the status of the small port development on the Mississippi River in Claiborne County; (5) the fourth paragraph of FSAR 2.2.3.1.1 was deleted, since the railroad track is no longer used; (6) FSAR Figure 2.2-3 to indicate the current ownership of several railroad tracks and completion of Interstate Highway 20 west of Vicksburg, Mississippi.

REASON FOR CHANGE: To reflect the current status of airline service, airport expansion, industrial development, and railroad ownership and use as described in the FSAR.

SAFETY EVALUATION: These FSAR changes did not substantially change the potential hazards traffic as described in the FSAR.

These changes did not result in any additional hazards analyses or revisions to previous hazard analysis. Therefore, these FSAR changes had no adverse safety or operations impact. No Technical Specification change or unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: No i

5 i

I t

J19ATTC86123001 - 119 I

Attachment to AECM-87/0019 SRASN: NLS-86-028 DOC N0: CN-3328-NLS-SE-86-006 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Table 2.2-6 and -7, Figure 2.2-5, and Section 3A/1.95-1 were changed to reflect the onsite storage of 600 additional gallons of nitrogen, 10 cylinders of chlorine, 3-40,000 gallon tanis of sulfuric acid, and 200 lbs. of Freon R-22.

REASON FOR CHANGE: To reflect corrected quantities and locations for onsite storage of chemicals and to clarify the means of compliance with Reg. Guide 1.95.

SAFETY EVALUATION: This change to the FSAR did not affect the probability of occurrence or consequences of an accident and did not affect equipment important to safety. No Technical Specification changes were required and there were no unreviewed safety questions associated with this change.

FACILITY DESCRIPTION CHANGE: Yes l

i J19ATTC86123001 - 155

Attachment to AECM-87/0019 SRASN: NLS-86-029 DOC N0: CN-3454-NLS-SE-86-001 SYSTEM: N/A DESCRIPTION OF CHANGE: This FSAR change revised FSAR 8.2.2.1 to update the offsite 500 KV transmission lines outage rate from an average 0.73 to 0.74 outages / year /100 miles of line. Also, FSAR Table 8.2-1 was updated to include 500 KV transmission line outage information for the years of 1980 to 1985.

REASON FOR CHANGE: To update the FSAR to include 500 KV transmission line outage rate and information for the years 1980 to 1985.

SAFETY EVALUATION: This FSAR change reflects a minor variation in the annual 500'KV transmission line outage rate and does not indicate a change to the overall reliability of offsite electrical power sources. The existing GGNS accident analyses include a total loss of all offsite electrical power and remains unchanged as a result of this FSAR change. No Technical Specification changes or unreviewed safety questions were generated as a result of this FSAR change.

FACILITY DESCRIPTION CHANGE: No 3

J19ATTC86123001 - 120

Attachment to AECM-87/0019 SRASN: NLS-86-030 DOC N0: CN-3319-NLS-SE-86-005 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 3.2.4.2 and Table 3.2-1 were revised to reflect the description of the installed Hydrogen Ignition System.

REASON FOR CHANGE: To include the Hydrogen Ignition System description as part of the Combustible Gas Control System.

SAFETY EVALUATION: No physical changes to equipment were involved in this change. The Hydrogen Ignition System is an existing system which was already covered by Technical Specifications, so no change was needed to Technical Specification as a result of this change. The Hydrogen Ignition System is passive and only operates to mitigate consequences of a degraded core accident in which significant quantities of hydrogen are released. Such an accident is beyond the design basis accidents previously evaluated in the FSAR, therefore, there is no increase in the probability of occurrence or in the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or any other accident analysis previously submitted. The Hydrogen Ignition System has been installed to mitigate pcstulated post accident degraded core hydrogen generation in compliance with 10CFR50.44. As such its adequacy has been the subject of extensive past and ongoing analyses, research and tests. Results have been submitted to and reviewed by the NRC. The conclusions of those reviews have been that the Hydrogen Ignition System in conjunction with procedural guidance represents an adequate approach to mitigating postulated post accident degraded core hydrogen generation until completion of the ongoing program and final review and approval by the NRC. No unreviewed safety question was identified by this change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 129

Attachment to AECM-87/0019 SRASN: NLS-86-031 DOC N0: CN-3319-NLS-SE-86-004 SYSTEM: N/A DESCRIPTION OF CHANGE: The subject FSAR change discusses the manual actuation criteria for the hydrogen recombiners as required by GGNS procedures.

REASON FOR CHANGE: The change was made to provide hydrogen recombiner manual initiation either upon reaching top of active fuel or based on hydrogen concentration.

SAFETY EVALUATION: The subject of the change is not addressed in the Technical Specifications. No change to the GGNS Technical Specifications was determined necessary and no unreviewed safety question was created by this change.

FACILITY DESCRIPTION CHANGE: No l-i l

l 4

i i

! J19ATTC86123001 - 121

Attachment to AECM-87/i]19 SRASN: NLS-86-032 DOC NO: CN-3319-NLS-SE-86-0017 SYSTEM: N/A DESCRIPTION OF CHANGE: This change deleted the statement in FSAR 6.2.5.3.1 that calculations have been performed to determine the consequent functional requirements of the Combustible Gas Control System to maintain hydrogen concentrations within the control limit.

REASON FOR CHANGE: Previous wording applied to the Combustible Gas Control System before the addition of the Hydrogen Ignition System and did not include consequent functional requirements of the Hydrogen Ignition System. The wording no longer applies to the expanded Combustible Gas Control System.*

SAFETY EVALUATION:. The change does not change calculations performed to determine consequent functional requirements of the Combustible Gas Control System, and therefore, has no effect on Unit One Technical Specifications and does not create an unreviewed safety question.

FACILITY DESCRIPTION CHANGE: No 1

4 i

I I

l 4

l J19ATTC86123001 - 122 i

Attachment to AECM-87/0019 SRASN: NLS-86-033 DOC N0: CN-3475-NLS-SE-86-018 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Sections 138.1.9.1, 138.1.9.5, 138.2.3.3, 13B.2.3.4, and Figure 13B-2 dealing with emergency communication systems were deleted from the text of the UFSAR, since it has been incorporated into the Emergency Plan.

REASON FOR CHANGE: The intent.of the information is incorporated into the Emergency Plan Revision 9 and/or 10, or in FSAR Section 18.2. Figure 13B-2 was not a commitment nor required by any federal regulation.

SAFETY EVALUATION: This change to the FSAR did not affect any accident previously evaluated nor any equipment important to safety. No Technical Specification change was required for this change and there were no unreviewed safety questions associated with the change.

FACILITY DESCRIPTION CHANGE: Yes J19ATTC86123001 - 123

Attachment to AECM-87/0019 SRASN: PLS-86-004 DOC NO: CN#3382-SE-86-035 SYSTEM: C41 DESCRIPTION OF CHANGE: FSAR Section 9.3.5 describes the standby liquid control system. The change to FSAR Section 9.3.5.3.

deleted the last sentence which stated: assurance that the system will still fulfill its function during repairs is obtained by demonstrating operation of the operable pump.

REASON FOR CHANGE: To provide consistency with the technical specifications which specifies additional requirements for assurance of system operability.

SAFETY EVALUATION: Operability of the standby liquid control system is addressed in Technical Specification 4.1.5 and deletion of the sentence from the FSAR has no impact on the system reliability; no impact on any accident evaluated in the FSAR; nor any impact on system operability. The change ishtlitorial and provides consistency with the technical specifications. No unreviewed safety question identified for this change.

FACILITY DESCRIPTION CHANGE: No l

J19ATTC86123001 - 168

Attachment to AECM-87/0019 SRASN: PLS-86-055 DOC NO: CN-3406-SE-86-079 SYSTEM: N/A DESCRIPTION OF CHANGE: FSAR Section 12.5.3.6 is revised to delete a sentence that indicated TLDs provided the official record of personnel exposure.

REASON FOR CHANGE: To avoid contradiction in that the statement was not correct for all cases; e.g., TLDs are not the official record for neutron exposure.

SAFETY EVALUATION: The change to the FSAR did not affect any Technical Specification, plant system, equipment, or FSAR accident analysis. No new failure modes were created and no unreviewed safety question was identified.

FACILITY DESCRIPTION CHANGE: No 1

J19ATTC86123001 - 169

Attachment to AECM-87/0019 4

SRASN: NSP-86-012 DOC N0: CN-3462-NLS-SE-87-002 SYSTEM: C84 DESCRIPTION OF CHANGE: FSAR Section 2.3.3.2, meteorological Data Processing, was changed to reflect that six computer programs are used for data processing. An updated description is given on the digital data composition and magnetic tape capability. Four.

sections were consolidated into one which describes the current computer programs and methods used for data processing and analysis.

REASON FOR CHANGE: To reflect the current method of data processing and analysis for reporting meteorological data.

SAFETY EVALUATION: This change did not reduce meteorological monitoring capabilities. No equipment changes or modifications were made, and no operational or parameter modifications were imposed by this change. Also, the scope and type of accident possibilities were not changed. This change did not involve a Technical Specification change and no unreviewed safety question.

FACILITY DESCRIPTION CHANGE: No 1

i l

4 l

4 I

i

! J19ATTC86123001 - 167

, - . , , , _ . - ,,-m . . , - , , .,,.__.,---,_,_._,___,_-__-...,_,,___y___,_ _y__. , , _ , ,_ ._.

'1 ATTACHMENT 2 UCNR SAFETY EVALUATIONS PREVIOUSLY REPORTED IN AECM-86/0362 J19ATTC86123001 - 173 i - . - _ _ _ . _ . _ _

Attachment to AECM-87/0019 UCNR SAFETY EVALUATIONS PREVIOUSLY REPORTED IN AECM-86/0362 Page One UCNR FACILITY

~50.59 SRASN DESCRIPTION No. No. CHANGE SE-86-029 PLS-86-001 No SE-86-030 PLS-86-002 No SE-86-031 PLS-86-003 No SE-86-036 PLS-86-005 Yes SE-86-040 PLS-86-006 Yes SE-86-042 PLS-86-007 Yes SE-86-044 PLS-86-008 No SE-86-027 PLS-86-019 No SE-86-039 PLS-86-021 No SE-86-037 PLS-86-023 Yes SE-86-038 PLS-86-024 No SE-86-043 PLS-86-025 Yes SE-86-048 PLS-86-028 No SE-86-045 PLS-86-029 Yes SE-86-059 PLS-86-030 No SE-86-060 PLS-86-031 No SE-86-075 PLS-86-032 No SE-86-074 PLS-86-033 Yes SE-86-073 PLS-86-034 No SE-86-072 PLS-86-035 No SE-86-071 PLS-86-036 Yes SE-86-070 PLS-86-037 Yes SE-86-069 PLS-86-038 Yes SE-86-068 PLS-86-039 Yes SE-86-067 PLS-86-040 No SE-86-066 PLS-86-041 Yes SE-86-065 PLS-86-042 No SE-86-064 PLS-86-043 No SE-86-063 PLS-86-044 No SE-86-054 PLS-86-045 No SE-86-058 PLS-86-046 No SE-86-056 PLS-86-047 Yes SE-86-057 PLS-86-048 No SE-86-050 PLS-86-049 Yes SE-86-028 PLS-86-050 Yes SE-86-077 PLS-86-052 No SE-86-078 PLS-86-053 No SE-86-080 PLS-86-058 No SE-86-061 PLS-86-059 No SE-86-086 PLS-86-062 No SE-86-046 PLS-86-064 Yes SE-86-047 PLS-86-065 Yes SE 86-049 PLS-86-066 Yes SE-86-087 PLS-86-068 No SE-86-088 PLS-86-070 Yes J19 MISC 87012801 - 1

Attachment to AECM-87/0019 UCNR SAFETY EVALUATIONS PREVIOUSLY REPORTED IN AECM-86/0362 Page Two UCNR FACILITY 50.59 SRASN DESCRIPTION No. No. CHANGE SE-86-089 PLS-86-072 No SE-86-091 PLS-86-073 No SE-86-092 Pt.S-86-074 Yes SE-86-093 PLS-86-076 No SE-86-094 PLS-86-077 No SE-86-096 PLS-86-079 No SE-86-097 PLS-86-081 No SE-86-100 PLS-86-082 No SE-86-105 PLS-86-083 No SE-86-076 PLS-86-089 No SE-86-032 PLS-86-095 No CUCNR0019 NPE-86-036 Yes CUCNR0154 NPE-86-052 Yes CUCNR0088 NPE-86-053 No CUCNR0132 NPE-86-054 Yes CUCNR0115 NPE-86-055 Yes CUCNR0156R01 NPE-86-154 Yes NLS-SE-86-023 NLS-86-001 No NLS-SE-86-026 NLS-86-005 No NLS-SE-86-020 NLS-86-007 No NLS-SE-86-021 NLS-86-008 No NLS-SE-86-022 NLS-86-009 No NLS-SE-86-024 NLS-86-010 No NLS-SE-86-029 NLS-86-011 No J19 MISC 87012801 - 2

9 j

ATTACHMENT 3 10 CFR 50.59 SAFETY EVALUATIONS NOT PREVIOUSLY REPORTED FOR UFSAR REVISION 0 l

9 J19ATTC86123001 - 174

Attachment to'AECM-87/0019 SRASN: NPE-86-153 DOC N0: DCP-83-0229 SYSTEM: G18 DESCRIPTION OF CHANGE: This Design Change Package relocated the Solid Radwaste Hydraulic Compacter, NSG180007, from elevation 118'-0" in the Radwaste Building.

REASON FOR CHANGE: To provide better access to stair number OR01; elevator number 5; and Rooms OR203, OR204, and OR207 on elevation 119'-0" in the Radwaste Building.

SAFETY EVALUATION: This modification did not change the original design intent of the Solid Radwaste System. The Hydraulic Compactor continues to perform its intended design function. The consequences of a failure of the relocated compactor remains unchanged and is enveloped by the analysis presented in UFSAR 15.7. This change is considered to be an enhancement with no adverse safety or operations impact. No Technical Specification change or unanswered question were identified.

J19ATTC86123001 - 95

^

Attachment to AECM-87/0019 SRASN: NPE-86-187 DOC NO: MNCR-0807-84-CFR0807-84R00 SYSTEM: G33 DESCRIPTION OF CHANGE: FSAR Figure 5.4-21 was revised to show

, valve G33-F101 as normally open and valve G33-F103 as normally closed.

REASON FOR CHANGE: To correctly reflect the position of the valves on the reactor vessel drain line.

SAFETY EVALUATICH: The function of the drain line is not changed. The change shows that the motor-operated-valve is to be used as the primary flow path and the manual valve is to remain

! normally closed. The change does not modify the pressure boundary. No Technical Specification change was required for this change and there was no unreviewed safety question involved with this change.

1 i

t i

i 9

i 4

J19ATTC86123001 - 154 i

Attachment to AECM-87/0019 SRASN: NPE-86-188 DOC N0: DCP-81-0022R0,R1- SYSTEM: Fil DESCRIPTION OF CHANGE: A new fuel channel air tugger / hoisting system was installed which will be used to install channels on new fuel bundles.

REASON FOR CHANGE: To provide assistance to plant personnel for installing channels on new fuel bundles when positioned on the new fuel inspection stand.

SAFETY EVALUATION: The air tugger system does not perform a safety function and will not increase previously_ evaluated accident or malfunction consequences. No new accident scenarios were created due to the installation of the tugger system. No Technical Specification change was required and no unreviewed safety question was identified for this change.

J19ATTC86123001 - 170

Attachment to AECM-87/0019 SRASN: NPE-86-190 DOC N0: DCP-82-0424 Rev.1 SYSTEM: P64 DESCRIPTION OF CHANGE: New grooves were cut into certain Fire Protection Sprinkler System valve stems to provide normally closed indication. Position switches were adjusted for operation in the new grooves. P& ids and FSAR Figures 9.5-2 and 9.5-7 were changed to reflect that the valves are normally closed.

REASON FOR CHANGE: The normal position of the valves was changed to closed in order to prevent inadvertent actuation of the suppression system from damaging the charcoal beds.

SAFETY EVALUATION: This change did not introduce any new failure modes. The new equipment and installation is equal to or better

.than that which was replaced. No Technical Specification change was required and no unreviewed safety question was identified for this change.

J19ATTC86123001 - 171

Attachment to AECM-87/0019 SRASN: NPE-86-192 DOC N0: DCP-82-4080 SYSTEM: Z17 DESCRIPTION OF CHANGE: Registers in the Unit 2 Computer Room for HVAC were closed off to provide additional cooling to the Unit I computer room. FSAR Figure 9.4-16 was revised to reflect this change.

REASON FOR CHANGE: To provide additional cooling to the Unit 1 computer room.

SAFETY EVALUATION: The system is non-safety related and the design intent for Unit 1 has not been changed. The change did not affect previously analyzed accidents or equipment important to safety. -There were no unresolved safety questions involved with this change.

J19ATTC86123001 - 164

Attachment to AECM-87/0019 SRASN: NPE-86-193 DOC N0: DCP-82-4128 SYSTEM: E32 DESCRIPTION OF CHANGE: FSAR Section 6.7.1.4.5 was revised to reflect that the third timer in the MSIV Leakage Control System is set at about 13 minutes to allow sufficient time for flow to stabilize.

REASON FOR CHANGE:  ! To reflect a realisgic (setpoint) time that will allow the MSIV-LCS flow to stabilize and allow accurate

- determination of leakage flowrates.

LSAFETY EVALUATION: _This change to the FSAR reflects a setpoint that will prevent unnecessary isolation of the system.. The setpoint was origin;lly determined to be too low during preoperational testing. The change to the FSAR did not require a change to the Technical Specifications and did not involve an unreviewed safety question.

J19ATTC86123001 - 106

7 Attachment to AECM-87/0019 SRASN: PLS-86-112 DOC N0: SE-84-068 SYSTEM: D17 DESCRIPTION OF CHANGE: FSAR Table 11.5-2 was changed by deleting the superscript (b) from the Gross Alpha Analysis.

REASON FOR CHANGE: To correct an apparent typographical error in that footnote (b) was applicable to the item immediately below Gross Alpha Analysis.

SAFETY EVALUATION: This change to the FSAR does not affect previously analyzed accidents nor does it affect any safety equipment. No change to the Technical Specifications was required and there were no unreviewed safety questions associated ~

with this change.

J19ATTC86123001 - 124 -