ML18094A351

Forwards Rept Re Status of Implementation of TMI Action Plan Items,Per 890414 Request

ML18094A351
Person / Time
Site:	Salem
Issue date:	04/18/1989
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NLR-N89079, NUDOCS 8904260166
Download: ML18094A351 (10)

Text

Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer APR 1 8 1009 NLR-N89079 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

STATUS OF IMPLEMENTATION OF TMI ACTION PLAN ITEMS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) hereby submits its response to your letter, dated April 14, 1989, which requested us to promptly review and report the status of the implementation of the TMI Action Plan Items for each of the Salem Units.

The enclosure to this letter contains Enclosure 1 of your letter with the status of each item updated as per your instructions.

Completion of the items in Enclosure 1 has been verified using our records on the TMI event.

In some cases, the item numbers in the enclosure did not correlate directly with NUREG 0737, NUREG 0737 Supplement 1, or the other related documents we reviewed.

In these cases we statused the item using the descriptive text of the TMI associated NUREGs (i.e., NUREG-0737, -0660, -0645, etc.),

as indicated in our response.

In addition, a verification of actual implementation of item responses was conducted to the fullest extent possible considering the time constraints imposed by your letter.

This verification compared our original response with the current plant configuration.

Verifications were performed to assure that this correspondence is as accurate as possible.

390426C> 166--;*==-9-u4re ___ J PDR ADOCK 05000272 p

F'DC

Document Control Desk NLR-N89079 2 -

APR 18 1900 PSE&Gs responses to the TMI Action Plan Items are being controlled within the Station Procedure and Design Control Processes.

Should you have any questions or comments concerning this response, please do not hesitate to contact us.

Enclosure c

Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Sincerely, Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

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0 MUlTI-PLAMT I ',Sul NUMBER ACTION NO.

I.A. l.1.1 "I.A.1.1.2 "I. A. L. 1. 3 FOOi

"'I.A.l.1.4 I. A. l. 2

l. A. 1. 3. l F002 J.A.1.3.2 F002 l.A.2.L.l 1.1\\.2.l.2 IA.2.l.3 J.A.?.1.4 F003 I. A. 2. 1. 5 I. f\\. 2. 3 I.A. 3. L 1 1.A.3.l.2 I. A. 1. l. 3.A 1.1\\.J.l.3.B

~1.B.1.2 l.C.1.1 I. C. L 2. A F004 J.C. L.7.B F004 i.C.1.3.A F005 l.C.1.3.B FOD5 I. c.?

I.[. 3 I. c. 4 l.C.~

F006 l.C.6 F007

'"l.C.1.1

"'I. C. 7. 2

"'!. C. B I. ll. l (See F008 & F071) 1.0.2. 1 FOD9 SALEM GENERATING STATION - UNITS 1 & 2 ISSUE TITLE LICENSEE IMPLEMEHTATIOM STATUS

=~~ ~~~lltlc:t ADVISOR - ON DUTY ******, *.*.**.*..............*....*****. ; **.*** ~ *********************..*************..**

SHI T HNIC ADVISOR - TEa! SPECS ******....**...........*...******.*.******* G *************************************.**

FT ECllUCAL ADVISGa - TRAllED t'Ell LL CAT 8................*.*..*.**.*.**..* G *****.*.*....**...**....*.**.*********...

SHIFT TECtlUCAL ADVISOR - DESCR111E* LONG TERM PROGRAM.*.*.....*.**************** G *.***************.***********

• n<<;,* **....

SH~FT SUPERVISOR RESPONSIBILITIES ******.*.**.............*...***..*********.** -~ ***********.******.********* ~.,~~.. ~-***.*.

SH FT MANNING - LIMIT OVERTIMES **********...**.............*.**..******...*************.****.*.*.******.****** ~ ******...

SHIFT MNMIMG - MIN SHIFT CREW *********.*...*........*... *........****.***.**** -~ *.********.*********.***************....

IMMEDIATE UPGRADING Of RO & SRO TRAINING AND QUAL. - SRO EXPER..........................................................

llllEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - SRO'S BE R0 1S lYR ********* G........................................

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - 3 MO. TRAIHING ****.******* G.................................. ~.

IfltEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - MODIFY TRAINING *******.... G *..***.** ******** * *: *.**.*..***.*** **.*

DllEDIATE UPGRADING OF RO & SllO TRAINING AND QUAL. - fACIUTY CERTIF ******.*** *§........... *.............................

AllllNISTRATION OF TRAINIMG PROGRAMS *****.......*...........**.**..********************.**.************.*******.*********

REVISE SCOPE & CRITERIA FOR LICENSING EXAMS - INCREASE SCOPE.....**..*.***.***. C *******.**.**..****.*..*****.***.******..

REVISE SCOPE & CRITERIA FOR LICENSllG EXAMS - INCREASE PASSING GRADE.**..***.** ~.**.*********.***.*******************..*

REVISE SCOPE &. CRIT. FOR UC. EXAMS - SUIJLATOR PLANTS WITH SIMULATORS *****.*. -~ *.*****..*.**..**.**.***.**.**.****.** <.

REVISE SCOPE & CRIT. FOR UC. EXAMS - SltlllATOR :. OTHER PLANTS....****.*****.* -~ **....***.******..***.*******.***...*.**

EVALUATION OF ORGANIZATION & MANAGEMENT *..*.*....*......*....**..*..*.*.***..*. C....*...*..*.. *.*..* ** *... ** * * * *.** * * * * * *

• SHORT-TERM ACCIDENT & PROCEDURES REVIEW - SB LOCA....*.*............*..********

C.. *************************** : * ***********

SHORT-TEllt ACCID. & PROCEDURES REV. - INADEQ. CORE COOL. REANAL. GUIOELINES **.* G.....*..................................

SHORT-TERM ACCID. & PROCEDURES REV. -

INMJEQ. CORE COOL. REVISE PROCEDURES ***** C.. *********************************..**..*

SHORT-TERM ACCID. & PROCEDURES REV - TRANSIENTS & ACCDTS. REA.MAL GUIDELINES (PROC. GEH. PKG.) ** %***********************

SHORT-TElltl ACCID. & PROCEDURES REV. - TRANSIENTS & ACCORS. REVISE PROCEDURES (UCPGRADED EOP'S) *********.***.****.**.*...*

SHIFT & RELIEF TURNOVER PROCEDURES **.*.*.... *.*.****************************** *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• SHIFT-SUPERVISOR RESPONSIBILITY *******. *.*..... * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• CONTROL -ROOM ACCESS ********* * *** * *. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * "c" * * * * * * * * * * * ** * *********************....*

FEEDBACK Of OPERATING EXPERIENCE ****.*..** *.*.. ******************************* *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * *. * * * * *. * *..

VERIFY CORIECT PUlFORMMCE OF OPERATING ACTIVITIES.*.....*.*.****** *********** *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NSSS VENDOR REV. OF PIOC -

LOW POWER TEST PROGRAM.....*...**.*.* * **. * * * * * * * * * * *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• NSSS VENDOR REV. OF PROC - POWER ASCENSION & EMER. PROCS.**. * *.** * ** * * * * * * * * * * *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• PILOT tlJll Of SELECTED EMEAGENCY PROC FOR NTOLS *..*... * * *. * * * * * * * * * * * *** * * * * * * * * "$ * * -~ T * * * *.. * * * * * * * * * * * * * * * * * * * * * *.. *. *

.... CONTROL-ROOM DESIGN REVIEWS (EllTER DATA FDR MPA FOOS & ttPA F-071) *.*********** C~~--~-~~-*-**********************~***

PLANT-SAFETY PARMETER DISPLAY CONSOLE - DESCRIPTION **.*..**..****************** *************************************

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llJLTl-PLANT ISSUE NUMBER ACTION NO.

I. ll. 2. 2

1. ll. 2. 3

• I.G.1.1

"'I.G.1.2

"'I.G.1.3 11.B.l.l Jl.B.1.2 11.B.Ll 11.B.2.1

"'II.B.2.2

"'Il.B.2.3

• I I. B. 2.4 "Il.8.3.l

"'11.B.3.2

"'II.B.3.3

• ILB.3.4 ILB.4.1

• JI.B.4.2.A

"'II.B.4."2.B H.D.l.l

""Il.D.1.2.A

"'11.D.1.2.B 11.11.l.3

• 11.D.3.1

• I I. D. 3. 2 F009 F009 FOlO FOlO FOll FOU F013 F013 F013 F014

"'J]. f.1.1.1 F015 (SH NOTE 1)

• II.E.1.1.2 F015 (SH NOTE 2)

Il.E.l.1.3 F015

{SEE. NOTE 3)

SALEM GENERATING STATION - UNITS 1 & 2 ISSUE TITLE LICENSEE IMPLEMENTATIOH STATUS

'PLANT-SAFETY PARAMETER DISPLAY CONSOLE., INSTALLED..**....*****.**..**..*.***

• G *s.. 'N:.t.................................

PLANT-SAFETY PAAAMETER DISPLAY CONSOLE - FULL y IMPLEMENTED *..*..**.*********.. G.. ee..0. -~~ *....*.*.....*.......*.*.........

TRAINING DURING LOW-POWER TESTING -

PROPOSE TESTS *....*...*.*..***.**.*******. c; *****************************, *** *, ******

TRAINING DURING LOW-POWER TESTING - SlBIIT ANAL. & PROCS.*.***.******.***.***. G..*.*******.*****....**...******* : ***..*.

TRAINING DURING LOW-POWER TESTING - TRAINING & RESULTS...*.....**..*.********* G *.*..******.**.**.**.******.*********....

REACTOR-COOLANT SYSTEM VENTS - DESIGN VEllTS ***.*.***..*.*..**.******.********* G ***************************************.*

REACTOR-COOLANT SYSTEM VENTS -

INSTALL VENTS (LL CAT B) **...**.*.***.**..***** G ***.***************.********************.

..t' REACTOR-COOLANT SYSTEM VENTS -

PROCEDURES ****.***...**.*****.**.***.**..*****

• G..**.******************..**************.*

PLANT SHIELDING -

REVIEW OESIGMS *.**.*******.*...**.*..*..**..*****.**.******* G *********.*.************* ;..*.*.** a*..

PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS *.**..*.*..******.******* G *******************.****************.*.

PLANT SHIELDING - PLANT MODIFICATIONS (ll CAT B).........*.......***..*....*.* G *****************************************

PL.Alfl SHIELDJllG - EQUIPMENT QUALIFICATION-NOT TRACKED AS A TMI ACTION ITEM *** G.........................................

POSTACCIDENT SAMPLING - INTERIM SYSTEM *.**..**.**...***..*.**************.**** G.**************.*.****.*****...*.......*.

PDSTACCIDENT SAMPLING - CORRECTIVE ACTIONS.***.*..*..**.**.**..*..******..**** G ************************************.*.*.

POST.ACCIDENT SAMPLING -

PROCEDURES *****.**.**.******.*..**....***.**********.. G ** -~ *.************************.****.***.**

POSTACCIDENT SAMPLING - PLANT fllJDIFICATIONS (LL CAT B).....*.***.***.******.* Ji~~.. <?~~~- *......***...**..**.............

TRAINING FOR MITIGATING CORE DAMftGE - DEVELOP TRACNING PROGRAM **.***********.* G.........................................

TRAINING FOR MITIGATING CORE DAHAGE - INIHAL...**..*..*..**.**.*.***********

• G **.....*..**.*.***.******.. *-............

, TRAINING FOR HJTIGATING CORE DAMAGE - COMPLETE *.*.....**.*..**..******.***..* -~ ********.*....****.****.*..*..**.........

/REUEF & SAFETY VALVE TEST REQUIREMENTS - SUBMIT PROGRAM.*.****..****..***.***.***********.**.*************..**.........

.'RELIEF & SAFETY VALVE TEST REqlllREMEllTS - COMPLETE TESTING.*.*.*****.****..*** G ***********.**********.*****.***.*****.**

~RELIEF & SAFETY VALVE TEST REQUIREllENJS - PLANT SPECIFIC REPORT ******.****.*** &ee.Nates.........*.......................

RELIEF & SAFETY VAVLE TEST REQUIREMENTS - BLOCK-VALVE TESTJNG *****.********** *&.........................................

VALVE POSITION INDICATION - INSTALL DIRECT INDICATIONS Of VALVE POS.......... *c........................................

VALVE POSTION INDICATION - TECH SPECS ***. _..*******..*.***.***** * ***** * * * * * * ** *c * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• AFS EVALUATION-ANALYSIS *..*.********....**..*..**...*****..*.**.***.***************** ***********.* ***********************

AFS EVALUATION-SHORT TERM t<<>DS *****.**.*.***...*..*.**.***.******************* c..........................................

c AFS -LONG TERM MOOS *******************************.*********** ** ** *******************************************************

NOTE 1 - THE ITEM LISTED IS FROM NUREG-0737, ENCLOSURE 2 IUIJ IS APPLICABLE TO NTOLS'S ONLY NOlE 2 - THE HEM LISTED IS FOR All PLANTS (OPERATING REACTORS AND NTOL'S)

NOlf 3 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS ANO NTOL'S)

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x MULTI-PLANT ISSUE NUMBER ACTION NO.

11.E.l.2.l.A l 1.E. l.2.1.B F016

11. f..1.2.2.A

• I 1. E.1.2.2.B

• ll.E.1.2.2.C F017

• ll.l.3.1.l

• IJ.E.3.1.2 11.E.4.l.l

• ll.L4.L2

• IL.E.4.1.3 F018 l I. E.4.2.1-4

• IJ.l.4.2.5.A

• II.E.4.2.5.B Jl.E.4.2.6 F019 Il.E.4.2.7 f019 "IL.E.4.2.8

• II.F.1.1 F020

• 11.F.l.2.A F020

• II.F.1.2.B F021

• ILF.1.2.C F022

• ll.F.1.2.0 F023

• Il.F.1.2.E F024

• II.r.1.2.F F025

• II. F. 2. 1

• II.F.2.2

• II.F.2.3 F026

• JI.I.2.4 F026 11 11.G. l. l

• Il.G.L2

11. K..I (Op er. Reactors Only)

SALEM GENERATING STATION - UNITS 1 & 2 ISSUE TITLE LICENSEE IMPLEMENTATION STATUS AFS INITIATION & FLOl11-CONTROL GRADE ***.*..*........*........*.**..*..*****.*. -2.........................................

AFS INITIATION & FLOW - SAFETY GRADE ****....*.*.......*....*..*..*..**.*****...*************....*...****..**.**.*.*.....

AFS INITIATION & FLOW -

FLOW INDICATION COIUROL GRADE..*..**.**.**.*..**..**.* C **..*.****.**........****..*****.***.**...

AFS INITIATION & FLOW -

LL CAT It TECH SPECS.**..*..*..*..*..**.**.**.**.*****. C ********.****.***.*****.****..*******.....

AFS INITIATION & FLOW - SAFETY GRADE.**..................*.*..**.**.**..*..*** C ******************************************

EMERGENCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY *..*..**.****** ~ ***.*********.**..****..*...******.**.*...

EMERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS *..*.**.* ~ ***..*********.* C *************************.************..**

DEDICATED HYDROGEN PENETRATIONS - DESIGN ***..*..*..*...*.**.**.**..*.*******.* NJ.A. ***************.**********************.

DEDICATED HYDR<MiEN PENETRATIONS - REVIEW & REVISE HZ CONTROL PROC ***..*.****** ~ ***.***.*.**..****.************.*....*...

DEDICATED HYDROGEN PENETRATION - INSTALL *.**.*..**...*.*.......********.****. NJ.A,. *****.*.*******.****************.A...

CONTAINMENT ISOLATION DEPENDABILITY -

It<P. DIVERSE ISOLATION.**.**.****.**.*.. C ******************** : ************** 9...

CONTAINMENT ISOLAT. DEPENDABILITY - CNTMT PRESS. SETPT. SEECIFIY PRESS **.**** ~ ******.******...**.*********.***...*...**.

CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PRESSURE SETPT. MODS ****.*****.*** C ******************************************

CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PURGE VALVES....*.*.***.**..*..**. C ***********************************.******

CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES ******. ~ ******..***.***.*********.***.*.**.***....

CONTAINMENT ISOLATION DEPENDABLITY - TECH SPECS.*..*...*..*.**.**..*********** C ***.**.*****************.********.****.. ;

• ACCIDENT - MONITORING - PROCEDURES.*****.****..*..*..**.****..*...*****.****** C **************************************.***

ACCIDENT - tllNITORING -

NOBLE GAS MONITOR *.*.**.........*.*..***.**.**.******* C ****************************************.*

ACCIDENT -

MONITORJMG - IODINE/PARTICULATE SAMPLING.*..*..*..**.**.****.****.. C ********************.******** -*************

ACCIDENT - MONITORING - CONTAINMENT HIGH-RANGE MONITOR *..*.***.**..*********** C *********************************.***.....

ACCIDENT - fl)NITORING - CONTAINMENT PRESSURE......*......*..*..**.*****..*.*** C **************************.*****.***.....*

ACCIDENT -

MONITORING - CONTAlrtolENT WATER LEVEL.....**........****..*..***...* C.*********************.**.******.****...*.

ACCIDENT - MONITORING - CONTAINMENT HYDROGEN *..*.*........*.***.*.*.***.*****. C ************************************.*****

INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING - PROCEDURES **.**.***. ~ ***.**..**.*.**..**..***.***........**....

IHSTRUMENTATIDM FOR DETECT. OF INADEQUATE CORE COOLING -

SUBCOOL METER......** S.e.e *.l'{q1;~~ **...*.*..*....*.................

INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING - OESC. OTHER ****..*** $~~ *. ~q1;~~--*******************************

INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE.CLING INSTLL ADD'L INSTRUMENTATION *** ~~~-ijQte~...........................

POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. -

UPGRADE ***.** ~ *.****.**..*****..****.**.*...*.*.........

POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. - TECH SP ****** ~ *****.******.*....**.......****.*.*.......

IE BULLETINS 05. 79-06. 79-08 ***.**.**.*...*..*..*...*..****.*******.* ** ~- **..***.*** * * * * *.. * * * * * * * * * * * * * -* * * * * * * *

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MUL Tl -PLANT l~SUE NUMBER ACTJON NO.

• Il.K.1.5

• ll.K.l.10

"'ILK. 1.20

• 11. K.1. 21

• 11. K. l. 22

• II. K. 1.23

• II.K.2.2

• Il.K.2.8 11.K.2.9 F027 ll.K.2.10 F028

• II.K.2.11 F029 II.K.2.13 F030 ll.K.2.14 F031 II.K.2.15 II.K.2.16 F032 ll.K.2.17 F033 II.K.2.19

• Jl.K.2.20 F035

• I I. K. 3.. 1. A F036

• II.K.3.1.B Jl.K.3.2 F037 11.K.3.3 F038 11.K.3.5.A F039 II.K.3.5.B F039 11.K.3.1 II. K. 3. 9 F040 ll.K.3.10 F041 ll.K.3.11 11.K.3.12.A 11.K.3.12.B F042 ll.K.3.13.A F043 Il.K.3.13.B F043 SALEM GENERATING STATION - UNITS 1 & 2 ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

'IE BULLETINS - REVIEW ESF VALVES ******. : *.*.**..........*.*..**.**.*********.

• l *......................... *. * * *. *.........

IE BULLETIN~ ~ OPERABILITY STATUS ******..*....**.*..*.*......********..*.**** *r:( A............................. *.******..

IE BULLETIN PROMPT MANUAL RE.ACTOR TRIP *.**.........*...*.*******.***.*****. r/ A **********.**.***....*****.** *. t.......

IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP.......................... ****/A..............................,:.-.......

IE BULLETINS - AUX. HEAT REM SYSTEM, PROC.................................... "f/ A..... ******************************.. **

IE BULLETINS - RV LEVEL, PROCEDURES ********..****.......*....**..********.*** -~~A... *.***********************************

ORDERS OM B&W PLANTS - PROCEDURES TO CONTROL AFW IND OF ICS *.**.**.***.**..*** Ni A"'.*....................................

ORDERS ON B&W PLANTS - UPGRADE AFW SYSTEM..................................... *rr A....................................

ORDERS ON B&W PLANTS - FEMA ON ICS ***.*..*.*.**.*........*.***.****.****...**** /. **..***...**.****...*******.****..*..

ORDERS ON 8&W PLANTS - SAFETY-GRADE TRIP.***....****.....**.**.***.*********** N,LA ********************.*********..*****.*

ORDERS ON B&W PLANTS - OPERATOR TRAINING ******.****...*....***************.** -~,LA *********.****.*****.****************..

ORDERS Oii B&W PLANTS - THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO) *..******..*****.*****.***.*.***.******..*..*......

ORDERS ON B&W PLANTS - LIFT FREQUENCY OF PORV' S & SV's.**.**..*.**.***..****** ~/.I;\\..*...*.***.**.....*.**.***............

ORDERS ON B&W PlANTS - EFFECTS Of SLUG FLOW *..**..****.*****.*.*************** ~/.I;\\.......................................

ORDERS ON B&W PLANTS -

RCP SEAL DAMAGE ******.*...*....**.*..*********.******** ~/.I;\\....*******..*....*....**...........*..

ORDERS ON B&W PLANTS - VOIDING IN RCS (CE & W PLANTS ALSO)..********..******.* C: *****.***********************************

BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR ******* ~/.I;\\ ******.*....*.......*..***.............

ORDERS ON B&W PLAllTS - SYSUM RESPONSE TO SB LOCA..***.***..*****.**.********* ~/.I;\\ *.*...*****..***...**..... :...*........

B&o TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN.**..*.*...*..*****.******.*** ~/.I;\\ *.**...*.*...**.......**....*..........

FINAL RECOlttEHDATIDNS, 8&D TASK FORCE - AUTO PORV ISO TEST/INSTALL ****.****.** ~/.I;\\ *........*.*...........................

B&O TASK FORCE -

REPORT ON PORV FAILURES ****....**..*..*..*...*****.**.**.***. ~ ******.***..*******.*****..***..*.*......

B&O TASK FORCE - REPORTING SV & RV FAILURES AND CHALLENGES *.*..****.*****.**** ~ **********.**.*.*******.*.****.**.*......

B&o TASK FORCE - AUTO TRIP OF RCP' S PROPOSED l<<JOIFJCATIONS ****..*.*, *.******** ~.........................................

B&0 TASK FORCE -

AUTO TRIP OF RCP' S l<<IDJFlCATlONS.*.**..**.**.******.*****..** ~ ***.**.******.***...****..**....*.**.....

8&0 TASK FORCE -

EVALUATION OF PORV OPENING PROBABILITIES..**.*****.***.****** ~/.I;\\.**.**.**...*.. ;.......................

B&0 TASK FORCE - PID CONTROLLER MODIFICATION.**..**.*.***..****.******.**.*** -~ ******.***.****.****.*..*....**..........

B&O TASK FORCE - PROPOSED ANTICIPATORY TRIP MODIFICATIONS...******.**.******* -~..********.*********.*.***.***.*.........

B&O TASK FORCE - JUSTIFY USE OF CERTAIN PORV *.**.***..*.**..**.*************** ~/.~ ******.**********..*.*..***...***......

B&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED llJDS *******.*****. ~ ***********..****.****..*.**.*.........**

B&O TASK FORCE - ANTICIPATORY TRIP IHI TURBINE TRIP INSTALL MODS *.*****.******* ~ **.***********.**.*********.*****. 9.....

B&O TASK FORCE - HPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS *.**.*********** ~/.~................................

B&0 TASK FORCE - HPCI & RCIC INITIATION LEVELS MODIFICATION ***..************.* ~/. ****************.****..**..******. ****

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• ll.K.3.14 F044 Jl.K.3.15 F045 ll.K.3.16A F046 ll. K. 3.16. 8 F046 Jl.K.3.17 F047 JI. K. 3.18.A F048 TI.K.3.18.8 F048 I I. K. 3.18. C F048

• ll.K.3.19 F049

• II. K. 3.20 f LK. 3.21. A F050 11.K. 3.21.8 F050 IL K.3. 22.A F051 JLK.3.22.8 F051 I I. K. 3. 24 F052 ILK. 3.25.A ll.K.3.25.B F053 ILK. 3.27 F054 ll.K.3.28 F055

• l I.K.3.29 F056 II.K.3.30.A Jl.K.3.30.8 F057 ll.K.3.30.C

11. K. 3. 31 F058

• JLK.3.40

• I I. K. 3.43 Il.K.3.44 f059 I I. K. 3-45 FOGO II. K. 3.46 F061

• I I. K. 3. 57 F062 JIJ.A.1.1 SALEM GENERATING STATION - UNITS 1 & 2 ISSUE TITLE LICEHSEE IMPLEMENTATION STATUS

• B&O TASK FORCE -

ISO CONDENSER ISOLAHOH ON HIGH RAD.**.**.**.************. NI.A. *.*.****.**..**.....**......*******..... _

B&O TASK FORCE - tEOIFY HPCI & RCIC BRK DETECTJON CIRCUITRY **.*...**.****.* NI.A. **..**....*.*...........*............*..

-B&O TASK FORCE - CffALLEHGE & FAILURE OF RELIEF VALVES STUDY.*****.*.**.**** NIA.*.***.....****..****......*.****....... _

B&O TAS<< FORCE - CHALLENGE & FAILURE OF RELIEF VALVES tllDIFICATIONS ****..** NIA *.......*.*.**......**.**..******........

B&O TASK FORCE.,. ECC SYSTEM OUTAGES *****..*...*.......*.....*..*...*****.** ~- *..**.************...**.***..***..**...*.. _

B&O TASK FORCE - ADS ACTUATION STIJDY *****.**......*.....*...*..*.***.***.** NIA.*..**.........*..*.*...**...*..........

B&O TASK FORCE - ADS ACTUATION PROPOSED llJDIFICATIONS..**..****.*.********* WA........................................

e&o TASl FORCE - ADS ACTUATION MOOIFICATIONS.*.... ;.*.***********.***.***** NIA *....**....*...............*..**........ -

B&O TASK FORCE -

INTERLOCK RECIRCULATORY PUMP tllDIFICATIONS ******.******.** NIA *.*.............................. ~

B&O TASK FORCE -

LOSS OF SVC WATER AT BRP.*..**.....*.*..*.*.*.**..*..***** N/A.................................. -

B&O TASK FORCE - RESTART OF CSS & LPCI LOGIC DESlGfL.*..**.*****.********* NIA..............*...*..*..................

B&O TASK FORCE - RESTART OF CSS & LPCI LOGIC DESIGN llJDIFICATIONS ********.* NIA.......*................................

B&O TASK FORCE - RCIC SUCTIOH VERIFICATION PROCEDURES.**.. -..**.**.**.***.* NIA...*...............**.................. --

B&O TASK FORCE - RCIC SUCTION MODIFICATION *...*.......**.*****.************ N/A......*.................................

8&0 TASK FORCE - SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER *************** N/A..............*......................*...

B&0 TASK FORCE -

POWER OH PtllP SEALS PROPOSED lllDIFICATIONS.********.******.C ************************.*.*******.**......

B&O TASK FORCE -

POWER ON PllfP SEALS llJDIFICATIONS....**.**..****...*****.* NIA.........*.......................*......

B&O TASK FORCE -

COMMON REFERENCE LEVEL FOR BWRS ***.*************.*******.* NIA......****.. -..........*.. :.............

B&O TASK FORCE - QUALIFICATION OF ADS ACCtl4ULATORS..*....******..*****.**** NIA.....**..................*..............

BIO TASK FORCE -

PERFORMANCE OF ISOLATION CONDENSERS *....**..**.*********** NIA....*..*................................ -

8&0 TASK FORCE - SCHEDULE FOR OUTLINE OF SB LOCA MODEL.....................C...........................................

BIO TASK FORCE -

SB LOCA lllDEL, JUSTIFICATION **..**.**.**.**..*****.*******.C ********....***.****........*.***.*........

B&O TASK FORCE -

SB LOCA METHODS NEW ANALYSES.**.*..**.**.**.**.*********.* ~-..........................................

B&D TASK FORCE -

COMPLIANCE WITH CFR 50. 46 *.*....*..**.*..*..*...*****.***.* C **.************.*****.*..***.*.*. ~...*.....

B&O TASK FORCE -

RCP SEAL DAMAGE - COVERED BY l I. K. 2. 16 AND II. K. 3. 25 *.***.* C *.**********.**..***.***....**.*.*...*.....

B&O TASK FORCE - EFFECTS OF SLUG FLOW - COVERED BY ll. K.2.15 **************. IVA.......................................

• B&O TASK FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE ****.***..*****.**** JV.A *****.*****.***.****...*.*.**.*...*..*..

B&O TASK FORCE - ANALYSES TO SUPPORT.******.*******.****.*************.**** JV.I\\. * * *.** * ** * * * * * * *. * * * * * * * * * * * * * * * * * * * * * *

• RESPONSE TO LIST OF CONCEHftS FROM ACRS CONSULTANT ****.*..*.**************** JV.I\\.........................................

IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS ****.*.***.******** tt(l\\.........................................

EMERGENCY PREPAREDNESS~ SHORT TERM ******. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * ******..***.. e*...

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II l. A. 1. 2. 1 lll.A.1.2.2 (SEE F063, F064, f065)

II I. A. l. 2. 3 (SlE F063, F064, F065)

Ill.A.2.1 F067 111.A.2.2 F068

• lll.0.1.1.1

• llL0.1.1.2 IJI.0.3.3.1 III.0.3.3.2 F069 111.0.3.4.1 F070

• lll.D.3.4.2 F070

• IIl.0.3.4.3 MPA-fOOB MPA-F063 HPA-F064 MPA-F065 MPA-F07l MPA-8072 MPA-8083 61.4.1 F008 F063 F064 F065 F071 8072 8083 GOOl SALEM GENERATING STATION - UNITS 1 & 2 ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

'UPGRADE EMERGENCY SUPPORT FACILITIES - INTERIM TSC OSC & EOF ****.********.*** C..........................................

UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/F064/F065 ****.* ~~~-~9t~~---*******************************

UPGRADE EMER SUPPORT FACILITIES - tlJDS INCORPOR. INTO F063, F064 & F065 ****** ~~~-~9t~~.....*...............*..* :;'........

UPGRADE PREPAREDNESS - UPGRADE EMERGENCY PLANS TO APP. E. 10 CFR 50.........* ~.......*..................................

UPGRADE PREPAREDNESS - METEOROLOGICAL DATA................................... C *..****...**.****.********..**.........*..

PRIMARY COOLANT OUTSIDE CONTAINMENT -

LEAK REDUCTION......................... C **********..**.*******************.*......

PRIMMY COOLANT OUTSIDE CONTAINMENT - TECH SPECS............................. C...................................

INPLANT RAD. l<<JNIT. - PROVIDE MEANS TO DETER. PRESENCE OF RADIOIOOINE.******

• l.................................... A...

IMPLANT AADIATIOH MONIT. - tl>DIFICATIONS TO ACCURATELY MEAS. IODINE ******.*************************..*.***..**..* 9-...

CONTROL ROOM HABITABILITY - REVIEW ********.*****.*******..*.***********.***** C. ;.................*......................

CONTROL ROOl'I HABITABILITY - SCHEDULE MODIFICATIONS........................... C *************.*****************.********..

c CONTROL ROOM HABITABILITY -

IMPLEMENT llH>IFICATIONS.***..***********.*******.**. ~~- ****.**********************..*..*....*

1t I. 0.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN...........*.....*.. -~~~.~9t~~- rn.. J... Q.J.................... r **

III.A. I. 2 TECHNICAL SUPPORT CENTER......................................*....

~Etet.fiQt~~..................................

111. A. 1. Z OPERATIONAL SUPPORT CENTER ****.**..*.*..**.****.**..*.***.**.****** C..........................................

111.A. l.2 EMERGENCY OPERATIONS FACILITY ******..*.*..***....****.***.*.******* C.**********.*.****..**.*.......*..........

• I. D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWP TO f-8)..... ~................ -~~(;!. ~9t~~- !'~.*. J... Q ** L......................

lllJREG-0737 TECH SPECS (GENERIC LETTERS 82-16 & 83-02)........................ C..........................................

i'-TECH SPEC COVERED BY GENERIC LETTERS 83-26 & 83-37 FOR NlJREG-0737............ $~~-~9t~?..................................

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)........................*.... C.......................................... -------------------------------

NOTES II.B.3.4 POST ACCIDENT SAMPLING SYSTEM (PASS}

This item was completed by PSE&G and the program was submitted to NRC.

NRC reviewed and approved PSE&G PASS Program in SSER dated 11/4/83.

In 1988, NRC informed PSE&G that the PASS design is deficient in that back-up grab sample capability was not provided.

PSE&G is making modifications to the PASS to provide back-up capability by the first quarter 1990.

I.D.1 CONTROL ROOM DESIGN REVIEW (CRDR}

The control room design review program plan, summary report, and additional required reports were submitted and approved via SSER dated 3/2/87.

Plant design modifications have been developed and the schedule for implementation was discussed at a NRC meeting on 5/21/87.

At that meeting a three outage schedule was presented and agreed to by the NRC Staff.

The results of this meeting are documented in a ~SE&G letter dated 6/4/87.

Salem Unit 1 CRDR is scheduled for completion at the close of the 10th refueling outage and Salem Unit 2 CRDR is scheduled for completion at the close of the 6th refueling outage.

I.D.2.3 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) -

FULLY IMPLEMENTED SPDS is fully implemented; however, additional improvements are scheduled for completion by July l, 1989.

II.D.1.2.B RELIEF AND SAFETY VALVE TESTING -

PLANT SPECIFIC REPORT This item is still open pending NRC review of PSE&Gs response to RAI dated 3/31/89, and further response scheduled for 8/1/89.

II.F.2.2 II.F.2.3 II.F.2.4 INSTRUMENTATION FOR INADEQUATE CORE COOLING Items open against CETs, RVLIS, and SMM awaiting upgrade modifications and/or technical specification amendment approval from NRC.

III.A.1.2.2 III.A.1.2.3 UPGRADE EMERGENCY SUPPORT FACILITIES -

DESIGN UPGRADE EMERGENCY SUPPORT FACILITIES -

MODIFICATIONS Items are still open pending implementation of design improvements and subsequent modification of the TSC.

The scheduled completion date is October 1989.

MPA-B083 TECH SPECS COVERED BY GL 83-26 & 83-37 FOR NUREG 0737 Tech Specs for RVLIS and RCS Vents were submitted to NRC and are currently in the review process.

I