ML18038A262

Forwards Rev 5 to Updated Fsar.Sections IV & Xv Revised to Incorporate Significant Parameters & Analyses Associated W/ Current Fuel Cycle.New Reload Analysis,Noting Changes Re Next Reload,Will Be Submitted in Dec 1987 or Jan 1988

ML18038A262
Person / Time
Site:	Nine Mile Point
Issue date:	06/29/1987
From:	Mangan C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18038A263	List: ML18038A262
References
(NMP1L-0164), (NMP1L-164), NUDOCS 8707070213
Download: ML18038A262 (16)

Text

REGULATORY ORMATION DISTRIBUTION SYS 0 (RIDS)

ACCESSION NHR: 8707070213 DOC. DATE: 87/06/2V NOTARIZED: NO DOCKET F*CIL: 50-220 Nine Mile Point Nuclear Stations Unit lz Niagara Powe 05000220 AUTH. NAME AUTHOR AFFILIATION MANQANz C. V. Niagara Mohawk Power Cor p.

RECIP. NAME RECIPIENT AFFILIATION Document Control Hranch (Document Control Desk)

BUHJECT: Forwards Rev 5 to updated FSAR. Sections IV h XV revised to incorporate significant parameters Zc analyses associated w/

ren fuel cycle. New reload analgsisz noting changes re next relo will b submitted in De 1987 or Jan 1988.

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DISTR IH E: ADOID CDPIES RE IV D:LTR I ENCL Q+ SIZE:

TITLE: OR Submittal: General Distr bution NOTES:

RECIPIENT COPIES RECIPIENT COP IEB ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 L* 1 0 PDi-1 PD 5 5 HENEDICTI R 1 INTERNAL: ARM/DAF/LFMH 1 0 NRR/DEST/ADE 1 1 NRR/DEST/ADB 1 NRR/DOEA/TSH 1 NRR/P H 1 OQC/HDB1 1 0 WL 1 1 REB/DE/EIH 1 EXTERNAL: EQSQ HRUBKEi S 1 1 LPDR NRC PDR 1 1 NSIC TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL

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V NIAGARA U MOHANK NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 June 29, 1987 (NMPlL 0164)

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 Gentlemen:

. Niagara Mohawk Power Corporation hereby submits one (1) signed original and ten (10) copies of Revision 5 to the Nine Mile Point Nuclear Station Unit 1 Final Safety Analysis Report (Updated).'his revision supplies information on a replacement page basis, as indicated on Table 1. A vertical bar indicates textual changes. Figure changes are indicated by revision number and year.

In addition, Table 2 (attached) lists modifications made in accordance with 10CFR50.59 since the last submittal of the Final Safety Analysis Report (Updated) on June 23, 1986. Modifications completed prior to January 1, 1987, were reviewed and, if appl:icable, incorporated into the Final Safety Analysis Report (Updated).

Sections IV and XV were revised to incorporate significant parameters and analyses associated with the current fuel cycle; however, Niagara Mohawk intends to submit a new reload analysis in December 1987 or early January 1988. The new reload will necessitate extensive changes to these sections of the Final Safety Analysis Report.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION C. V. Ma gan Senior Vice President DPC/pns 3328G Attachments cc: Mr. Jay Dunkelberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza 87070702l,3 87o60220 Albany, NY 12223 pDR ADOCK 0500 DR

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UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation ) Docket No. 50-220 (Nine Mile Point Unit 1) )

AFFIDAVIT:

C. V. Mangan, being duly sworn, deposes and says:

I am Senior Vice President of Niagara Mohawk Power Corporation, duly I

authorized to act on the Corporation's behalf; as such, I have read the documents attached hereto and find that the statements made therein are true to the best of my knowledge, information and belief.

. Mangan .

Senior ice President Niagara Mohawk Power Corporation

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Subscribed, acknowledged and sworn to before me on this day of June, 1987.

MARY FRATESCHf Notary Pubtro In tho State ot New Yorfr Qualified ln Onondaga County No.

4797550 My Corn Issfon Expires Notary,,Publ i c 3328G

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT 1 Table 2 Modifications Implemented Under 10CFR50.59 Not Previously Submitted to the Nuclear Regulatory Commission" MOD NUMBER MODIFICATION DESCRIPTION 76-022 Reactor and Turbine building Crane Hoisting Controls Improve Operating Reliability (150/25 ton), Non-Safety Related 1

82-050 Replace Cleanup Isolation Valves with Appendix J Test Connections Safety-Related. Not Described in FSAR.82-090 Control Room Ventilation Positive Pressure (Painted Control Room Peripheral Walls) 82-090-3 Control Room Emergency Vent System Upgrade Safety-Related 82-093 Gamma Traversing In-Core Probe Installation (Replace Neutron Tips with Gamma Tips)83-047 Relocate Control Room Meteorological Computer Terminals Not Safety-Related, Too Detailed for FSAR 83-058-3 Safety Parameter Di splay System Implementation of SPDS 1) Additional Process Variables,

2) Hardware Additions and 3) Software Developments83-074 Improve Transformer Protection Power Board 101 Upgrade 83-075 Power Cable to Process Computer Panel Board 167 to Increase Current Capacity, Non-Safety Related, Not Described in FSAR 83-084 Change Cooling Source of Instrument Air Compressor to Turbine Building Closed Loop Cooling.84-014 Miscellaneous Process Computer Hardware (CRT's for SPDS & Remote TIP Panel), Non-Safety Related 84-021 Emergency Condenser Steam Line Plug (Request for Procurement Only)84-052 Turbine Building Closed Loop Cooling Pump Mechanical Seals Non-Safety Related. Not Described in FSAR.

• While some modifications may have been performed earlier, inclusion indicates closeout of the entire modification package.

3328G

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Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 84-055-1 Emergency Condenser Steam Line Test Taps Not Described in FSAR 84-064 Turbine Valve Test Control Circuit Replace Pushbutton Switches.

Non-Safety Related. Connector Details not Described in FSAR.85-005 Remove Thermal Overload from Reactor Drain Valve 37-09R Then Lock It Closed to Prevent Spurious Opening and Loss of Reactor Coolant Inventory (Reactor Drains Not Discussed in FSAR) ~

85-025 Replaced Emergency Condenser Steam Line Drain Seismic Restraints Support.85-026 Automatic Depressurization System Inhibit Switch Modify Confirmatory Logic 85-030 Doppler Acoustic Sodar; Prepare Location By 85-039 Anticipated Transient Without Scram Level Transmitter Test Taps Relocation 85-046 Reactor Protection System Component Supply Voltage-New Cable Routing Specific Cable Routes Not Normally Described in FSAR 85-052 Replace Containment Spray Heat Exchangers/Straps Safety-Related 85-055 Miscellaneous Roof Repairs (Replacement/Maintenance)

Replaced Roofing Materials85-066 Control Blade Pin 5 Roller Changeout/Replacement Material Upgrade 85-094 Replace, With Larger Gauge, the DC Power Cable Between Emergency Condenser Motor-Operated Isolation Valve and Battery Valve Board 85-098 Containment Isolation on High Radiation (Drywell Vent 5 Purge)85-102 Replace SRM/IRM Dry Tubes Mounting with New GE Design Safety-Related, Details Not Described in FSAR 85-108 Reroute Core Spray Pump Control Cables Specific Routing Not Described in FSAR 85-109 .ECIV 39-07 Cable Replacement Increased Gauge, Too Detailed for FSAR 3328G

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Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 85-111 Reactor Vessel Coupon Holder Installation of Coupons 'A'nd 'C'ompleted During Non-Safety Related/Details Not Described in FSAR 86-016 Repair & Replace Turbine Bypass Valve Linkage Anchor FSAR Description,Not Affected, Non-Safety Related 86-019 Add Lugs to Pipe Support 03-H4 Non-Safety Related, Too Detailed for FSAR 3328G

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AGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT 1 FINAL SAFETY ANALYSIS REPORT (UPDATED)

REVISION 5 (1987)

Table 1 Remove and Destro Re lacement Pa e Volume I Coversheet Volume I Coversheet Table of Contents p. xxi Table of Contents p. xxi List of Figures p. xliv List of Figures p. xliv III-17 II I-17

-21 -21

-25 -25

-27 -27 49 -49 IV-1 IV-1

-8 -8

-10, Figure IV-1 -10, Figure IV-1

-11 -11

-13 -13

-14 -14

-25 -25

-26, Figure IV-2 -26, Figure IV-2

-40 -40 V-28 V-28

-31 -31 VI-9 VI-9

-12 -12 VII-6 VII-6

-11 -11

-33 -33 VIII-3 VIII-3 4 4

-5 -5

-16, F.i gur,e,VI I I-3 -16, Figure VIII-3

-57 -57 IX-20 IX-20 3175G

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT 1 FINAL SAFETY ANALYSIS REPORT <UPDATED)

REVISION 5 (1987)

Table 1 Remove and Destro Re lacement Pa e X-59 X-59

-78 (NEW)

-79 (NEW)

Volume II Coversheet Volume II Coversheet Table of Contents (one sheet) Table of Contents (one sheet)

List of Figures (one sheet) List of Figures (one sheet)

XIII-9A XIII-9A

-10 -10

-17 -17

-18, Figure XIII-2 -18, Figure XIII-2 XV-6 XV-6

-7 -7

-8, Figure XV-2 -8, Figure XV-2

-8a, Figure XV-2a -8a, Figure XV-2a

-8b, Figure XV-2b -8b, Figure XV-2b

-10, Figure XV-3 -10, Figure XV-3

-13 -13

-14, Table XV-3 -14, Table XV-3

-15 -15

-16, Figure XV-5 -16, Figure XV-5

-17, Figure XV-6 -17, Figure XV-6

-17a, Figure XV-6a -17a, Figure XV-6a

-19, Figure XV-7 -19, Figure XV-7

-80 -80

-94a, Figure XV-33a (NEW) 3175G

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