ML20095J135

Forwards List of Current Approved Changes to Hope Creek Generating Station Ufsar,Replacing Current List in Front of UFSAR W/Attached List

ML20095J135
Person / Time
Site:	Hope Creek
Issue date:	12/10/1995
From:	Raymond R Public Service Enterprise Group
To:	NRC
References
NUDOCS 9512260327
Download: ML20095J135 (10)

Text

PUBLIC SERVICE ELECTRIC & GAS COMPANY 12/15/95 DOCUMENT DISTRIBUTION NOTICE PAGE 1 OF 1

TRANSMITTAL: DDG 0431821 TO: NbbUMENTCbULATORYCOMMISSION LEAR RE D

NTROL DESK COPYHOLDER: HFSR-011 WASHINGTON, DC 20555 DESCRIPTION: SLM-778 CHANGE LIST HJE PLEASE INSERT THE FOLLOWING DOCUMENTS INTO YOUR CONTROLLED FILE / MANUAL.

SUPERCEDED DOCUMENTS MUST BE SO MARKED AND PHYSICALLY REMOVED OR DESTROYED.

SHT/

CLASS DOCUMENT ID VOL INST REV STAT TYPE FORMAT QTY PROC HFSR-CHANGE LIST 000 N/A A HFSR H

001 l

o e o r.

e 1

4 V u v d '.)

)

l PLEASE SIGN AND DATE THIS NOTICE TO ACKNOWLEDGE RECEIPT g

AND RETURN WITHIN 5 WORKING DAYS TO:

PSE&G DDG/MC N04 PO BOX 236 HANCOCKS BRIDGE, NJ 08038 TO CHANGE YOUR DISTRIBUTION STATUS, PLEASE CHECK THE APPROPRIATE SPACE BELOW:

REMOVE FROM DISTRIBUTION CHANGE COPYHOLDER INFORMATION

__ SEE MY INSTRUCTIONS ABOVE 951226'0327 951210 PDR ADOCK 05000354 DATE:

COPYHOLDER SIGNATURE: -

P PDR DDG USE ONLY:

DATA ENTRY COM3LETED:

PSEG

(,!

Pubhc Service Electnc and Gas Cornpany P O. Box 236 Hancocks Briage. New Jersey 08038-0236 Nuclear Business Unit TO:

Hope Creek UFS opy Holders FROM:

R.

L. Raymon g Senior Staff ngineer - Licensing and Regulation

SUBJECT:

APPROVED CHANGE NOTICES TO THE HOPE CREEK UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) SINCE THE LAST REVISION DATE:

DEC 101995 REF:

LR-I95723 Attached is a list of the current approved changes to the Hope Creek Generating Station Updated Final Safety Analysis Report (UFSAR).

Replace the current list in the front of your copy of the UFSAR with the attached list.

This list will be updated on a monthly basis to keep you apprised of changes to the UFSAR.

This g-list should be consulted when reviewing the UFSAR during the

\\ 'j process of writing 50.59 Safety Evaluations.

The changes listed

-e t

in the table are cart of the UFSAR but do not show up in the current text of the printed UFSAR copies or in the database.

However, the text of the approved change notices can now be found on DMS at the beginning of the UFSAR immediately after this letter in the form of marked-up pages of the UFSAR.

All of the previously identified " backlog" UFSAR change notices that should have already been incorporated into the UFSAR have e

now been fully approved or cancelled.

The approved change notices are included in the attached list.

An interim revision of the UFSAR will be published 12-29-95 to incorporate all of the approved backlog change notices as well as all approved current cycle change notices as of 11-1-95.

If you have any questions regarding any of the changes listed or you need to review any of the change notices listed, please contact me on extension 1249.

Attachment RLR/pfr C

File 2.1.3 v

95 2168 REV 6 94

.=

CONT 80' COPY #

L 1

The following is a list of approsed changes to the llope Creek UFSAR w hich will he i cllhfed in f

jj

]

the next revision.

llope Creek UFSAR Changes y,g, i /[

tg 12n/95 g%%

i Affected Affected CN Number Sections Pages/ Figures Description llSAR 87173 7.5 T 7.5-1,Shts Safety Parameter Table 1,2,3,4,5,6,7,10,12,13,1 5,16,17,19,20,23 ilSAR 88-017 6.2 6 2-50,6.2 51, 6.2-52 Water Seal Test ilSAR 88-032 9A 9A-21 Fire Protection - Ladders llSAR 89-001 9.5.1.4.2 9.5-60 Fire Protection - Testing IISAR 89-007 9A T 9A-1 Fire Protectior$ Containment Added Room & Cable Trays IISAR 89-016 9.1 9.1-1,9.1-42 Modification to the Spent Fuct Pool Heat Exchangers 11S 1

11.3 11.3-13,23,24, T1. I l-1 Changes to the condenser olT-gas hydrogen gM analyzers due to implementation of DCP 4 HC-0029.

F 1.2 18 O

HSAR 90-013 9.3 T 9.3-8 NEW Designation of Radioactive Drains and j

Non-radioactive Drains HS AR 90-014 8.2 8.2-10 Manual Trip-A-Umt Interlock Hope Creek Keency/ Deans Line llSAR 904)22 10.2 Modify EHC BPV Control Logic F 10.2 11 j

HSAR 90-027 7.3 Ilydrogen Recombiner Trips F 7.3-52 IISAR 90-032 9.2 T 9.2-4 Added Aux. Boiler Cond. Coolers llSAR 90-034 9A T 9A 1, Pg Updated to Indicate Combustible Load 17,39,40,48,T 9A-15; Contributions based on DCP 5EC-3022 Pg 3,4, T 9A-15, Pg 1.

T 9A-62, Pg i IISAR 90-035 3.10, 8.3 3.10.3(P5),8 3-Elimination of Topaz Inverter from ECCS 7a.b.c d(1,2) and RCIC Circuitry and ECCS Leak Dctcction System.

F 8.3-8 bG

Ilope Creek UFSAR Changes Page 2

12/7/95 Affected Affected

\\

CN Number Sections Pages/ Figures Description ilSAR 90-040 11.4 11.4 13,11.4 14 Upgrade of Closed Circuit Television System Used to Observe the Solid Radwaste Packaging and Drum Handhng.

3 IISAR 904)41

9. A 9A-1, p 31; 9A9, p 1, Temporary Reactor Recirc Vibration 25 Monitoring per DCR 4EC-3186 IISAR 90-043 7.6 7.6-4,7.6-37 Clarify PIS-N658 Valves F 7.6-i l llSAR 90-051 6.2 Correct typo's in existing USAR figures.

F 6.2-27,Shts 1,2,6,8,13,I5,22,30,35, 38,5 ilSAR 90-052 3.4 Update Finish Grade and Drainage Plan F3.4-3, Sh I and 3 ilSAR 914)09 9.5 Table 9A-1, Table 9A-Update Fire Loads in Control Room Arcas 7

61 for Carpeting.

HSAR 91-010 9A 9A.6.3, T 9A 15,T 9A-Fire Protection - Add Rooms 4

>\\

ilSAR 91-012 9.5, 10.4, i1.3 Table 9.5-3 Installs flydrogen Water Chemistry, Ilydrogen/ Oxygen Injection System to control intergranular stress corrosion cracking (IGSCC) per DCP 4HC-0242 i

Packages 1,2,3 & 4.

10.4-5 sh 1,2&3; 10.4-6 sh 1; i1.3-1 HSAR 91-031 9.5 9.5-1 Standards for noncombustible coatings.

IISAR 924)22 7.5 T7.5-1 Displayed Parameters important to Safety llSAR 92-030 4.1,4 2.4.3,4.4,4 6 4.1 2, 20,4.2-1,-2, Add description of ABB Control Rods.

4.3-4,4.4-10,4 6-26,-

45 ilSAR 92-035 9.2 9.2 16 Delete reference to use of sodium nitrite as corrosion inhibitor for STACS system.

llSAR 93-001 6.2 T 6 2-30 pg 7 Primary Penetration Leak Rate Testing 1

l

\\

Ilope Creek UFSAR Changes page 3

12/7/95 O

Q Affected Affected CN Nu.mber _ _ Sections.. _

Pages/ Figures Description IISAR 93-003 3.6, 3.2, 3.9 T 3.6-2,3.2-3,3.6-6,3 6-Snubber Reduction Project (SRP) for: SRV 6 A,3.6-20,3.6-21,3.6-Lines D H M Main Steam Line A, B, C.

27,3 9-49,3.9-4h,3.9-D, Loop A, B, C, D, SRV Lines A. B, C.

4r,3.9-4c,3.9-4f,3 9-4 E, G. J. L, R. Recirc Loop A. RiiR Loop A, B Systems per DCP 4EC-1021, Package 1,2,3,4,5,&6 F 3 6-30,3.6-31, Shts 1.2 IISAR 934X)4 9.2 T 9.2-9. 9.2-49, 52 Deletes the use of Sodium Nitrate RACS Corrosion Inhibitor flS AR 93-005 9.2 9.2-41 -42, -46, T 9 2-Describes the Corrosion Control 6, T 9.2-7, T 9.2-6 T Methodology Used for the Chilled Water

9. 2-8 System

!!SAR 934)o6 13 1 13 1-33 Tech Spec Amendment #56; Clarifications to Unit Staff Qualifications llS AR 93-008 8.3 T 8.3-11 (deleted)

Degraded Grid Voltage Analysis ilSAR 934)o9 5.4 Reactor Water Clean-up System Filter

[]

Dcmineralization u

a V

F 5 4-20 IISAR 93-013 18 1.8-119, 1.8-120 Deletion of Commitment to Install a Category 1 System for Post-Accident Neutron Monitoring.

IISAR 93-014 7.3,7.2,3 1,15.2,15.9 1.227;31-27;7.2-Eliminated the MSLRM Initiated Scram j

,15 A,11.5 15,16,19,7.3-24,11.5-and MSIV/MSL Drain Valve Closure per 11,12;15.2-17,15.9-Tech Spec Amendment 53 and DCP 4EC-66,15-vi,xv,xvi;15.5-3038 18,19,20;15 A-1 thru 14,19 thru 21,24; T7.2-l&2,7.3-5,11.5-2,15 0-2,6,7,8 159-41,1544 liSAR 93-021 11.4 11.4-7 Chemical Treatment of LWMS IISAR 93-022 3 11 3.11-9,10 Change to FSAR for safety & non-safety related mechanical equipment qualification.

O

..-m 4

l Ilope Creek UFSAR Changes

pag, 4

12/7/95 Affected Affected i

.CN Number

. Sections _

Pages/Figuren Description IISAR 93-023 9A 6A, T6 2 30, T9A 1, Containment Atmosphere Control Valve Pages 25 & 31. T9A-8, Replacement Pages 1 & 22. T9A-10, Pages 1,2 & 7 3

j Figurc 6.2-29 1f IISAR 93-024 9 A, 6.2 T 9A-1, T 9A-10, T Reflects a change in combustible loading i

9A-12, T 6.2 30 due to the replacement ofisolation valves 1

in the Containment Atmospheric Control l

System.

1

!!SAR 93-027 3.6 T3 6 22 Revises LPCI Injection Piping Stress

]

Levels due to Snubber Reduction Program 1

IISAR 93-028 36 T3.6-14 Revises RCIC Piping Stress Levels due to Snubber Reduction Progam i

ilSAR 93-029 9A 9A-25,SIIT 4 UFS AR Table 9A-25 editorial changes.

j llSAR 93-032 3.6 T3 6-23 Revises Core Spray Piping Stress Levels due to Snubber Reduction Program l

IISAR 93-033 3.6 T3.6-22 Revises LPCI Injection Piping Stress ls Levels due to Snubber Reduction Program 3

9-liSAR 93-034 3.6 T3 6-10 Reviscs RWCU Piping Stress Levels due to Snubber Reduction Program F 3 615 i

j llSAR 93-035 3.6 T3.6 3,3.617 Revises Main Steam Drain Piping Stress j

Levels due to Snubber Reduction Program i

F 3.6-27 I

l IISAR 93-038 9A T9A-1, Page 15 of 55 Room 3418,3419 Carpeting Fire Load increase 11SAR 94-002 9.1 9.1-124, T 9.1-12 (2 of Lift of RPV licad Insulation Package using 4

9), T9.1 21 Kevlar Sting Arrangement and Polar j

Crane Auxiliary and flook to reduce time spent in Reactor Cavity j

liSAR 94-003 9.1 9.l-80 Expands Spent Fuci Pool (SFP) Slot Plug Laydown Arca & Safe Load Path - Reactor l

Building Slab Equipment & La>down -

Arca it. EL. 201'-0" F 9.1-32, Sht 3 of 13, DWG P-0047

O 4

c.

. Hope Creek UFSAR Changes Page 5

12/7/95..

Affected '

Affected

_ Sections __

Pages/ Figures De_scription CN Number ilSAR 944)o4 9.I 9.1-62 to 64,71,81, Allows the use of a Circular Nut Rack 84,124, T 9.1-6,12, when Detensioning the RPV licad 14, T 9.1 21 F 9.1-32 (11 of 13)

IISAR 944X)9 9.2 9.2-4 SSW IIcad Tank Function 11SAR 94-010 82,8.3 8211,83.-2,837 External distribution system breaker arrangement ilSAR 944)l4 9.5 9.5-37,9.5-4' Reflects the Replacement of Adjustable Pressure Restricting Valves on Fire liose Stations with Non-Pressure Reducing Glove Valves per DCP 4flE4X)97, Pkg. I ilSAR 94-015 9A T9A-12 Sht 8 or 42, Turbine Lube Oil T9A 1 pg 32 of 55 IISAR 94-018 9.5 9.5-28 Fire Pump Testing flSAR 94-019 11.4 11.4 6 Liquid Radioactive Waste System

allizer c

IISAR 94-020 1.8, 1.12, 1.15, 14.2 14.2-208, 1.8 157, SBO Incorporation 1.1217 thru 20; new Section 1.15 llSAR 94-022 5_4 5.4-46,5.4-52 RilR Crosstic Flowpath F5.4-13 Sht. 2, F6.3-12 Shts 1,2,3 IIS AR 94-023 1.10 1.10 59 Clarifics the Discussion Concerning the 11PCI Torus Suction Isolation Valve to Maintain Consistency llSAR 94-024 9.1 9.1 22,9.1-25,9.1 26 Resiscs the Minimum Allowable

& 27, 9.1-29 & 30 Temperature in the Spent Fuel Pool to 40 degrecs F l

IlSAK 944)25 1.10, 6.2 1.10 115,6.2-Clarifics the Performance of Leakage i

89,119,120,123,124,12 Reduction Tests during CILRT 6; T 6.2-22, I&2 IISAR 94-027 9,1 T 3.2 1. T 9.1-4, 9.1-6, Revise to include REM

• Light Wet 9.1-14 Transfer Equip per DCP 4EC-3410-01 1

Hope Creek UFSAR Changes Page 6-12n/95 a

Affected Affected CN Number Sections Pages/ Figures Description llSAR 94-028 17.2 17.2-1,-42 Change Selected Oversight Practices of QA Organie.ation to More Efrectively Monitor implementation of the Nuclear Department Procedure System flSAR 94-029 1.8, 9.5 1.8 147, 9.5-Ratscs the Alarm Level and the Transfer 118,121.125 Pump Start Level of the EDG Day Tanks per 4EC-3375 IISAR 94-030 12.2 T 12.2133 (4 of 6)

Changed Extraction Steam Piping Specification per DCP 4EC-3344, Pkg. 6 IISAR 94-031 5.4 T 5.4-3 Correct the Minimum Available NPSif for the RWCU Main Cleanup Recirculation Pumps

- IISAR 94-032 5.4 T 5.4-3 Correct the Shell Side Design Pressure for the Non-regenerative ficat Exchanger ilSAR 94-033 7, 7.1, 7,7 7.1-8,9,10, 7.7-Deleted section that discussed Sensing 34,35,36,37,38,39,40 Line Failures concurrent with a Single Electrical Failure. Section is no longer applicable. Feedwater Control System was O

also revised. Changes made to reflect the Installation of the Digital Feedwater System DELETE F 7.7-7 IISAR 94-035 7,1 7.1-23, Table 7.1-2, Correct the revision date for R.G.I.29 Rev Pagc 2 of 3 3

i l

IISAR 94-036 9, 9 A 9Aiii. 9A-85 thru 88, T Revises Structural Steel Fireproofing Plan 9A 103 and -104 and Deletes Tables with Redundant l

Information 1

l IISAR 94-037 3.6,9.2 9.2-8, -35, -51, T 3.6-Reflects Change to Maximum Ultimate l

28 and 9.2 9 licat Sink Operability Temperature i

ilSAR 94-039 11.5 I l.5-8,9,14 Modified the Plant Annunciator System i

Description by climinating the Main l

Control Room Annunciators that are continuously alarmed I

ilSAR 94-041 9A T 9A 15 Sht 7 Revises the Fila table for penetration seals in Room 3301 A l

IISAR 94-042 1.10

l. A.I.3, Pg 1.1011 Clanfy Shift Operations Shift Manning I

e.

.,n.nm

.r

-.m r

7 -

.m.- - -.

g

l l

~

s Ilope Creek UFSAR Changes p,,,

7 12/7/95

)

\\

Affected Affected i

CN Number Sections Pages/ Figures Description l

IISAR 94-043 6.2 6.2-90,6,2-119,6.2-Clarify the Monitoring of the CRD Line i

122,6.2 123; T 6.2.22, Leakage Monitor during the CILRT Page 2; T 6.2-23 IISAR 944)44 9.5 9.5-79 Explain uhy a Dedicated Audible Fire Alarm System is Not Provided ilSAR 94-046 11.2 11.2 10 T 11.2 10, Organic Polymer Pleated Filter Elements Sheet 4 of 5 to be used in the Liquid Raduaste Equipment Drain Filter per DCP 4EC-3344 IISAR 94-047 9A T 9A-1; 9A-32 thru 9A-Clarify Cable Chase Combustible Loading 35 i

t ilSAR 95-002 1.2, 9.5, i1.4, 12.2 T 9.5 2, T 9.5-3, T Implements LLRSF per DCP $EC-3030 l

12.3 12.2 145 Pkg.1 CD P505 and DCP SEC-3030 Pkg.

l 2 CD P509 F 1.2 1, F 2.4-9, F 2.4 25, F 3.4-3, F 3.5 1, F 3.5-17, F 3.5-18, F 3.5-19, F 9.5 15, F 11.4-new, F 12.3-new IISAR 95-004 2.3 2 3-36; T 2.3-29 Reduce Level of Design Detail in UFS AR for Meteorological Instrumentation llSAR 95-006 3.3 T 3.3 2,2 of 2 Correct FRVS Location llSAR 954)21 3.1, 13.1, 17.2 13.1-26, 13.1 27, 17.2 Tech Dept System Manager Title Change 21 IISA.R 954)22 7.5 7.5-19; 7.5-21; 7.5-23 Tech Spec Amendment 73. Approval Relocation of Loose Parts Detection System from the Tech Specs to the UFSAR l

llSAR 95-029 9.3 9.3-33 Deletes pressure value for nitrogen gas supply for Post Accident Sampic Panel llSAR 95-030 15 T.O.C.,151 15-ii,15 1 19 Correct typo BWR to PWR.

O v

1

Ilope Creek UFSAR Changes p,g, g

12/7/95 Affected Affected kj i

CN Num,ber

. Section s. _

_Pages/ Figures Description _

l

}iSAR 95-031 62,6.3 6.2-127, T 6.2-16, T Elimination of Type C Leak Rate Tests for 6.2-24, T 6 2-25 CIVs in Certain Primary Containment i

Penetrations that Terminate Below the Minimum Water Level in Torus.

i Reclassifying HPCI and RCIC Turbine Exhaust Vacuum Breaker Network Associated with Cont. Pent. P204 F 6.2-27, F 6.2-45, F 6.2-46 IISAR 95-036 1.14 1.14-Vessel Lesel Sensing Line Backfill ilSAR 95-047 6.3 6.3-Surveillance Test Interval, Out-of-Senice Times for ECCS, RCIC i

)

a l

i O