ML17055D972

Forwards Rev 6 to Vol I to Updated FSAR for Nine Mile Point Nuclear Station Unit 1,for Mods Completed Prior to 880101

ML17055D972
Person / Time
Site:	Nine Mile Point
Issue date:	06/24/1988
From:	Terry C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17055D973	List: ML17055D972
References
5086G, NMP1L-0275, NMP1L-275, NUDOCS 8807060213
Download: ML17055D972 (28)

Text

AC'CELZRATZD RIPE'M30N BEMONS7R ON SYSTZM REGULATOR NFORMATION DISTRIBUTION &STEM (RIDS)

ACCESSION"NBR:8807060213 DOC.DATE: 88/06/24 NOTARIZED: YES DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH. NAME AUTHOR AFFILIATION TERRY7C.D. Niagara Mohawk Power Corp.

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

SUBJECT:

Forwards Rev 6 to Vol I of updated FSAR for Nine Mile Point Nuclear Station, Unit I. R 7 Ir gR DISTRIBUTION CODE: A053D COIlZES RECEIVED:LTR I ENCL // SIZE: /3 ~~M TITLE: OR Submittal: Updated FSAR (.50.71) and Amendments 7 D

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL' ID CODE/NAME LTTR ENCL PD1-1 LA 0 PDl-1 PD 1 0 BENEDICTgR 1 1 HAUGHEYgM 1 1 h INTERNAL: ACRS AEOD/DOA/IRB 1 1 ST/ADS 7E 1 0 NUDOCS-ABSTRACT REG FI 01 1 1 RGNl 1 1 EXTERNAL: ARM/DCB 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1 SAIC LINER,R 1 1 j

h TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13

Y NIAGARA U MOHAWK NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474-1511 U.S. Nuclear Regulatory Commission June 24, 1988 Attn: Document Control Desk NMP1L 0275 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 6 to the Nine Mile Point Nuclear Station Unit 1 Final Safety Analysis Report (Updated). This revision supplies information on a replacement page basis, as indicated on Table l. 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 10 CFR 50.59 since the last submittal of the Final Safety Analysis Report (Updated) on June 29, 1987. Modifications completed prior to January 1, 1988, were reviewed and, if applicable, incorporated into the Final Safety Analysis Report (Updated).

Sections IV and XV were revised to incorporate significant parameters and analyses associated with Reload 10 Cycle 9 and Reload ll Cycle 10.

Very truly yours, NIAGARA MOHAWK P ER CORPORATION C. D. Terry Vice President Nuclear Engineering and Licensing NJFipns 5086G Attachments xc: Regional Administrator, Region I Mr. Jay Dunkleberger Mr. R. A. Capra, Director Division of Policy Analysis and Planning Mr. R. A. Benedict, Project Manager New York State Energy Office Mr. W. A. Cook, Resident Inspector . Agency Building 2 Records Management Empire State Plaza 0>

Al bany, NY 12223 $

88070b0213 880b24I PDR ADOCK 05000220I K PNU~

'I V

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of l

]

Niagara Mohawk Power Corporation Docket No. 50-220

]

(Nine Mile Point Unit 1)

AFFIDAVIT C. D. Terr , being duly sworn, states that he is Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.

Subscribed and sworn to before me, a Notary Public in and for the State of New York and County of , this 4 ~ day of 1988.

otary Public in and for County, New York My Commission expires:

BETH A. MENIKHEfM Notary Publfc In the State Quatllted Inn Ononrfa of New Yorff o Y nonrfaea County No.

My Commfaalon Errfrfrea 4804074 nu

l 1 C

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

REVISION 6 (1988)

Table 1 Remove and Destro Re lacement Pa e Volume I Cover Sheet Volume I Cover Sheet Table of Contents p. vii Table of Contents p. vii

p. xvii p. xvii

p. xxi p. xxi

p. xxvi p. xxvi

p. XXX p. XXX

p. xxxi p. xxxi List of Figures. p. xxxix List of:Figures p. xxxix

p. xl p. xl

p. xliii p. xliii

p. xliv p. xliv

p. xlvi p. xlvi List of Tables p. li List of Tables p. li p, lii p. lii

p. liii p. liii I-10 I-10

-ll -11

-12 -12 II-1 I I-1

-4 Figure II-3 -4 Figure II-3

-5 -5

-13 -13

-14 -14

-15 -15

-16 -16

-16a -16a

-16b -16b

-16c -16c

-16d -16d

-16e -16e 5116G

I '

~

q

Table l (Continuedl Remove and Destro Re lacement Pa e III-3 Figure III-1 III-3 Figure III-1

-7 Figure III-2 -7 Figure III-2

-8 Figure III-3 -8 Figure III-3

-9 Figure III-4 -9 Figure III-4

-10 Figure III-5 -10 Figure III-5

-11 Figure III-6 -11 Figure III-6

-12 Figure III-7 -12 Figure III-7

-13 Figure III-8 -13 Figure III-8

-14 Figure III-9 -14 Figure III-9

-25 -25

-26 Figure III-14 -26 Figure III-14

-27 -27 44 44

-45 -45

-46 Figure III-18 -46 Figure III-18 IV-1 IV-1

-3 -3 4 4

-5 -5

-8 -8

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

-ll -ll

-12 -12

-13 -13

-14 -14

-19 -19

-23 -23

-24 -24

-25 -25

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

-27 -27

-28 Figure IV-3 -28 Figure IV-3

-29 -29

-30 -30

-34 Figure IV-5 -34 Figure IV-5

-34a

-40 -40 VII-1 VI I-1

-2 -2 4 4

-7 -7

-8 -8

-9 -9

-18 -18 5116G

I e 0 r'h

Table 1 (Continued) ~

Remove and Destro Re lacement Pa e VIII-80 VIII-80

-81

-82

-83

-84

-85

-86

-87

-88

-89

-90

-91

-92

-93

-94

-95

-96

-97

-98

-99

-100

-101

-102 IX-2 IX-2

-3 -3 4

-6 -6

-9 Figure IX-1 -9 Figure IX-1

-'l l -11

-14 Figure IX-2 -14 Figure IX-2

-15 -15

-21 Figure IX-3 -21 Figure IX-3

-22 Figure IX-4 -22 Figure IX-4

-23 Figure IX-5 -23 Figure IX-5

-27 Figure IX-6 -27 Figure IX-6

-31 -31 X-59 X-59

-75 -75 XII-8 XII-8

-9 Figure XII-1 -9 Figure XII-1

-10 -10

-11 -11

-12 -12

-13 -13 5116G

I I

Table i <Continued> ~

Remove and Destro Re lacement Pa e XII-14 XII-14

-15 -15

-16 -16

-17 -17

-19 -19 Volume II Cover Sheet Volume II Cover Sheet Table of Contents p. vii Table of Contents p. vii

p. xvii p. xvii

p. xxi p. xxi

p. xxvi p. xxvi

p. xxx p. xxx

p. xxxi p. xxxi List of Figures p. xxxix List of Figures p. xxxix

p. xl p. xl

p. xliii p. xliii

p. xliv p. xliv

p. xlvi p. xlvi List of Tables p. li List of Tables p. i

p. lii p.

1 lii

p. liii p. liii XIII-1 XIII-1

-2 Figure XIII-1 -2 Figure XIII-1

-4 -4

-5 -5

-9 -9

-20 -20 XV-7 XV-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

-12 Figure XV-4 -12 Figure XV-4

-13 -13

-14 -14

-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 5116G

Table 1 (Continued) ~

Remove and Destro Re lacement Pa e XV-79 XV-79

-80 -80

-81 -81

-81a

-94a -94a

-137

-137a

-137b

-137c

-137d

-137e

-137f

-137g,

-137h

-1371

-137)

-137k

-171 -171 5116G

P NIAGARA MOHANK POHER CORPORATION NINE MILE POINT UNIT 1 Table 2 Modifications Implemented Under 10 CFR 50.59 Not PreviousTy Submitted to the Nuclear Regulatory Commission These changes were reviewed and did not involve any unreviewed safety questions as defined in 10 CFR 50.59(a)(2).

MOD NUMBER MODIFICATION DESCRIPTION 78-34 Fire Protection Upgrade Structural Modifications, such as: installation of radiant heat shields, fire walls, and stair towers.

79-05

• Main Steam Line Radiation Monitor Cable Replacement

. Installation of a .Steel Plate to provide a barrier between Channels 11 and'12 of the Main Steam Line Radiation Detection System.

80-30 Improve Refuel Bridge Replace the present drive system with one using a separate drive motor for each drive wheel.

80-54 Fire Protection-Sprinkler System Addition of smoke purge capability to elevation of 250 of the Turbine Building.

The exterior 10" fire main will be "hot tapped" and an 8" valve and supply line will be installed. Installation of Additional Automatic Sprinkler Systems along with Deluge Systems, Motor control centers will be modified by adding cubicles for miscellaneous fire protection equipment.

80-55 Fire Protection-Smoke Purge Addition of roof and sidewall vents to improve smoke purge capability to the Turbine Building.

80-57

• Control Room Ventilation-Smoke Purge Additional smoke purge capability added to the main control room, the auxiliary control room, and the cable spreading room.

5086G

Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 80-58 Fire Protection-Detection Upgrade Addition of fire detectors, seven local control panels, and replacement of the existing main fire control panel in the control room.

Installation of a high temperature alarm, including a sensor in the seal oil unit room.

81-04

• 10" Vacuum Breakers Breakers added to the six SRV discharge lines.

81-12-1

• Reactor Building Wall Crack Strut Installation of a compression strut supporting the Reactor Building wall at the location of the crack. Removal of compression strut; since -the strut impedes access and Reactor Building wall is functional without it. Decouple screenhouse wall from Reactor Building wall.

82-07

• Reactor Building Ventilation Access Doors Replacement of some sections of Reactor Building normal exhaust duct work.

82-21

• Machine Shop Smoke Removal Installation of a welding smoke extraction system and a cutting smoke extraction system.

82-30 Reactor Recirculation MG Set Watt Metering - Replacement of motor generator sets watt meter and circuitry.

82-58 New Station Transformer Installation of new transformer.

82-62 Add Fire Detection-Respiratory Protection Trailer.

82-72

• Service Water and Radwaste Discharge Monitors Installation of a new monitor to sample effluent from the Reactor Building and Turbine Building service water return lines.

5086G

MOD NUMBER MODIFICATION DESCRIPTION 82-79 Emergency Planning-EOF Power Modifications Consolidate and improve the telecommunication system by installing the mini and major consoles, telephone support cabinets and electrical routing.

82-83

• Replacement of Air Ejector Flow Controller Pneumatic Devices with Electronic Devices The present pneumatic devices no longer work, forcing manual operation of flow control valves. Electronic devices will replace the existing pneumatic devices.

82-85

• Security and Radiation 8 Exposure Management System

. Install ".wrap .around" -type. door frames over the existing door frames, The new frames will provide the necessary strike depth to assure a secure condition.

82-86 Roof Repairs Resaturate roof with coal tar or asphalt where it is needed. Also, includes the replacement of the expansion joint between Reactor Building and Turbine Building.

82-92

• Diesel Generator Lube Oil Modifications Replace AC pump with 2 DC pumps, replace lube oil cooler, reroute cables.

83-06

• Degraded Grid Voltage Involves the rewinding of motors from a rated voltage of 575 volts to 550 volts to meet Class IE safety electrical qualifications.

83-14 Computer EMM Bulk Core Replacement Replace EMM bulk core memory with 400 ns large core storage. Convert power feed to lu-lb in auxiliary control room from 240 VAC to 120 VAC.

5086G

0 s

4

~, ~

Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 83-25 Radwaste Replacement and Addition of Tanks and Piping-Uti li ty Collector Tank, Waste Chemical Addition Tank, Laundry Waste.

83-40 Document Control-675 MB Disk Power Supply.

83-53 Scriba Substation Phase I Add relay protection associated cabling and electrical cabinets required to connect into Scriba Substation.

83-54

• Replace 24V Batteries - Replaced battery banks and new junction boxes installed.

83-58-2

• Control Room Design Review (NUREG 0737) Fixes from DCRDR based on NUREG 0737 Supplement l.

83-87

• Piping Replacement Replace Emergency Condenser piping with new 316 stainless steel piping.

84-53 EOF Communications Link EOF moved to Training Center.

84-58

• Feedwater Pump Control Circuit Modification Provide annunciation in control room, additional motor protection, backup power source, increased vessel overfill protection.

85-16 Scriba Substation-Phase II Disconnected 345 KV line ¹10 between NMP1 and FitzPatrick.

85-17 Scriba Substation Phase III Reroute ¹9 outgoing transmission line to Scriba substation.

85-19 Document Control-Additional Power Requirements for Xerox 2080 5086G

Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 85-22 Electrical and Diesel Fire Pump Modification Separation of cables and removal of Electrical Fire Pump Remote Lockout capability.

85-27

• Diesel Generator Cooling Water Check Valves Replace valves with new models.

85-29

• MG Set 167 Protective Relaying Upgrade with ITE packages.

85-31 Emergency Battery Pack Additions Emergency lighting supply.

85-37

• Fire Protection-Fire Doors Procurement and installation of devices or components and rework necessary to maintain the doors'esign rating and UL label.

85-42 Unit II Modification Backwash Discharge Install 8-inch discharge line for water treatment system.

85-67-1 Containment Spray Raw Water Control Cables Reroute two control cables to separate Division I and Division II.

85-72

• Energy Management System-Install Remote Terminal Unit and replace transducers in panels 1S25 and 1S27.

85-81

• Induction Heating Stress Improvement To improve the resistance of stainless steel piping materials to IGSCC.

1 85-85

• Condensate Transfer System Replacement Supports Redesign of supports to improve their safety margin.

85-91

• 4160V Feeder Cable Reroute (101-11) Reroute cables to prevent potential loss of safety-related equipment.

5086G

Table 2 (Continued)

MOD NUMBER MODIFICATION DESCRIPTION 85-93 RPIS Rod Drift-Replace circuit capacitors to reduce random and false rod drift indications.

86-06

• Drywell Penetration Modifications for Jet Thrust Loads Relocate instrument air piping for main steam isolation, install thrust detectors and supports.

86-24 Fire Protection Breathing Air Compressor Provide backup emergency power supply for the air compressor.

86-54

• Install New Instrument Tubing 8 Valves on Nitrogen Tanks Will reduce the risk of nitrogen leakage and tank overfill, reduce the number of nuisance alarms in control room and decrease calibration time 86-56

• Conduit Supports-Q1P Concern 6-00062 Upgraded safety-related conduit supports for multiple conduits above elevation 300'n Turbine Building.

87-07

• Repair to West Entry Control Room Door-Held hinges for Door

¹73 to the door frame.

87-19 Eliminate Diesel Generator High Crank Case Pressure Trip-Install Overpressure Diaphragm Baffle Plate and increase Air Supply Tube Diameter.

87-70

• Structural Repair for Raw Water Supports 93-R12 and 93-R13 Addition of cover plates to strengthen the support steel.

• Safety-Related.

5086G