Text

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)
	v • d • e

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.

7-Is--g /

DISTR IH E:

ADOID CDPIES RE IV D:LTR I

ENCL Q+ SIZE:

TITLE:

OR Submittal:

General Distr bution NOTES:

RECIPIENT ID CODE/NAME PD1-1 L*

HENEDICTI R COPIES LTTR ENCL 1

0 1

RECIPIENT ID CODE/NAME PDi-1 PD COP IEB LTTR ENCL 5

5 INTERNAL: ARM/DAF/LFMH NRR/DEST/ADB NRR/P H

WL 1

0 1

1 1

1 NRR/DEST/ADE NRR/DOEA/TSH OQC/HDB1 REB/DE/EIH 1

1 1

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1 EXTERNAL:

EQSQ HRUBKEi S NRC PDR 1

1 1

1 LPDR 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 87070702l,3 87o60220 pDR ADOCK 0500 DR 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

Albany, NY 12223

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UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation

)

(Nine Mile Point Unit 1)

)

Docket No. 50-220 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 Subscribed, acknowledged and sworn to before me on this

~ day of June, 1987.

MARYFRATESCHf 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 82-050 82-090 82-090-3 82-093 83-047 83-058-3 83-074 83-075 83-084 84-014 84-021 84-052 Reactor and Turbine building Crane Hoisting Controls Improve Operating Reliability (150/25 ton), Non-Safety Related 1

Replace Cleanup Isolation Valves with Appendix J Test Connections Safety-Related.

Not Described in FSAR.

Control Room Ventilation Positive Pressure (Painted Control Room Peripheral Walls)

Control Room Emergency Vent System Upgrade Safety-Related Gamma Traversing In-Core Probe Installation (Replace Neutron Tips with Gamma Tips)

Relocate Control Room Meteorological Computer Terminals Not Safety-Related, Too Detailed for FSAR Safety Parameter Di splay System Implementation of SPDS

1) Additional Process Variables,

2) Hardware Additions and

3) Software Developments Improve Transformer Protection Power Board 101 Upgrade Power Cable to Process Computer Panel Board 167 to Increase Current Capacity, Non-Safety Related, Not Described in FSAR Change Cooling Source of Instrument Air Compressor to Turbine Building Closed Loop Cooling.

Miscellaneous Process Computer Hardware (CRT's for SPDS

& Remote TIP Panel),

Non-Safety Related Emergency Condenser Steam Line Plug (Request for Procurement Only)

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.

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Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 84-055-1 84-064 85-005 85-025 85-026 85-030 85-039 85-046 85-052 85-055 85-066 85-094 85-098 85-102 85-108 85-109 Emergency Condenser Steam Line Test Taps Not Described in FSAR Turbine Valve Test Control Circuit Replace Pushbutton Switches.

Non-Safety Related.

Connector Details not Described in FSAR.

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)

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Replaced Emergency Condenser Steam Line Drain Seismic Restraints Support.

Automatic Depressurization System Inhibit Switch Modify Confirmatory Logic Doppler Acoustic Sodar; Prepare Location By Anticipated Transient Without Scram Level Transmitter Test Taps Relocation Reactor Protection System Component Supply Voltage-New Cable Routing Specific Cable Routes Not Normally Described in FSAR Replace Containment Spray Heat Exchangers/Straps Safety-Related Miscellaneous Roof Repairs (Replacement/Maintenance)

Replaced Roofing Materials Control Blade Pin 5 Roller Changeout/Replacement Material Upgrade

Replace, With Larger Gauge, the DC Power Cable Between Emergency Condenser Motor-Operated Isolation Valve and Battery Valve Board Containment Isolation on High Radiation (Drywell Vent 5 Purge)

Replace SRM/IRM Dry Tubes Mounting with New GE Design Safety-Related, Details Not Described in FSAR Reroute Core Spray Pump Control Cables Specific Routing Not Described in FSAR

.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 86-016 86-019 Reactor Vessel Coupon Holder Installation of Coupons 'A'nd 'C'ompleted During Non-Safety Related/Details Not Described in FSAR Repair

& Replace Turbine Bypass Valve Linkage Anchor FSAR Description,Not Affected, Non-Safety Related 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 Table of Contents

p. xxi List of Figures

p. xliv III-17

-21

-25

-27 49 Volume I Coversheet Table of Contents

p. xxi List of Figures

p. xliv III-17

-21

-25

-27

-49 IV-1

-8

-10, Figure IV-1

-11

-13

-14

-25

-26, Figure IV-2

-40 IV-1

-8

-10,

-11

-13

-14

-25

-26,

-40 Figure IV-1 Figure IV-2 V-28

-31 V-28

-31 VI-9

-12 VI-9

-12 VII-6

-11

-33 VII-6

-11

-33 VIII-3 4

-5

-16, F.i gur,e,VI II-3

-57 VIII-3 4

-5

-16,

-57 Figure VIII-3 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 Table of Contents (one sheet)

List of Figures (one sheet)

Volume II Coversheet Table of Contents (one sheet)

List of Figures (one sheet)

XIII-9A

-10

-17

-18, Figure XIII-2 XIII-9A

-10

-17

-18, Figure XIII-2 XV-6

-7

-8, Figure XV-2

-8a, Figure XV-2a

-8b, Figure XV-2b

-10, Figure XV-3

-13

-14, Table XV-3

-15

-16, Figure XV-5

-17, Figure XV-6

-17a, Figure XV-6a

-19, Figure XV-7

-80 XV-6

-7