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{{#Wiki_filter: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:
{{#Wiki_filter: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.
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.
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 these cases we statused the item using the descriptive text of the TMI associated NUREGs (i.e., NUREG-0737, -0660, -0645, etc.),
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.
as indicated in our response.
Verifications were performed to assure that this correspondence is as accurate as possible.
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.
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Document Control Desk NLR-N89079 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 
Document Control Desk                              APR 18 1900 NLR-N89079 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.
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Sincerely, Enclosure c  Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector 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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Revision as of 11:16, 21 October 2019

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)
v • d • e


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.

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Document Control Desk APR 18 1900 NLR-N89079 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.

Sincerely, Enclosure c Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector 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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I. A. 1. l. 3.A REVISE SCOPE &. CRIT. FOR UC. EXAMS - SUIJLATOR PLANTS WITH SIMULATORS *****.*. -~ *.*****..*.**..**.**.***.**.**.****.**<.

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

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  • 11. K.1. 21 IE BULLETIN IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP ..........................

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PROMPT MANUAL RE.ACTOR TRIP *.**.........*...*.*******.***.*****. A**********.**.***....*****.** *. t ...... .

        • /A 10
  • 11. K. l. 22
  • II. K. 1.23 IE BULLETINS - AUX. HEAT REM SYSTEM, PROC .................................... "f/ A..... ****************************** .. **

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

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  • II.K.2.2 ORDERS OM B&W PLANTS - PROCEDURES TO CONTROL AFW IND OF ICS *.**.**.***.**..*** Ni A"'.*....................................

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I *Il.K.2.8 ORDERS ON B&W PLANTS - UPGRADE AFW SYSTEM ..................................... *rr A................................... .

11.K.2.9 F027 ORDERS ON B&W PLANTS - FEMA ON ICS ***.*..*.*.**.*........*.***.****.****...**** /. **..***...**.****...*******.****..*..

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ll.K.2.10 F028 ORDERS ON 8&W PLANTS - SAFETY-GRADE TRIP .***....****.....**.**.***.*********** N,LA ********************.*********..*****.*

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  • II.K.2.11 F029 ORDERS ON B&W PLANTS - OPERATOR TRAINING ******.****...*....***************.** -~,LA *********.****.*****.****************..

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II.K.2.13 F030 ORDERS Oii B&W PLANTS - THERMAL MECHANICAL REPORT (CE & WPLANTS ALSO) *..******..*****.*****.***.*.***.******..*..*......

"'~ ll.K.2.14 II.K.2.15 F031 ORDERS ON B&W PLANTS - LIFT FREQUENCY OF PORV' S & SV's .**.**..*.**.***..****** ~/.I;\ ..*...*.***.**.....*.**.***............

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

(1 I II.K.2.16 F032 ORDERS ON B&W PLANTS - RCP SEAL DAMAGE ******.*...*....**.*..*********.******** ~/.I;\ ....*******..*....*....**...........*..

ll ll.K.2.17 F033 ORDERS ON B&W PLANTS - VOIDING IN RCS (CE & W PLANTS ALSO) ..********..******.* C: *****.***********************************

II: II.K.2.19 BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR ******* ~/.I;\ ******.*....*.......*..***.............

z *Jl.K.2.20 F035 ORDERS ON B&W PLAllTS - SYSUM RESPONSE TO SB LOCA ..***.***..*****.**.********* ~/.I;\ *.*...*****..***...**..... : ...*........

r UI *I I. K. 3 ..1. A F036 B&o TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN .**..*.*...*..*****.******.*** ~/.I;\ *.**...*.*...**.......**....*..........

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i *II.K.3.1.B FINAL RECOlttEHDATIDNS, 8&D TASK FORCE - AUTO PORV ISO TEST/INSTALL ****.****.** ~/.I;\ *........*.*...........................

I) 0 Jl.K.3.2 F037 B&O TASK FORCE - REPORT ON PORV FAILURES ****....**..*..*..*...*****.**.**.***. ~ ******.***..*******.*****..***..*.*......

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

11.K.3.3 F038

,:; 11.K.3.5.A F039 B&o TASK FORCE - AUTO TRIP OF RCP' S PROPOSED l<<JOIFJCATIONS ****..*.* , *.******** ~ ........................................ .

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~ II.K.3.5.B F039 B&0 TASK FORCE - AUTO TRIP OF RCP' S l<<IDJFlCATlONS .*.**..**.**.******.*****..** ~ ***.**.******.***...****..**....*.**.....

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11.K.3.1 8&0 TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES ..**.*****.***.****** ~/.I;\ .**.**.**...*.. ; ...................... .

II. K. 3. 9 F040 B&0 TASK FORCE - PID CONTROLLER MODIFICATION .**..**.*.***..****.******.**.*** -~ ******.***.****.****.*..*....**..........

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

U) ll.K.3.10 F041 ll.K.3.11 B&O TASK FORCE - JUSTIFY USE OF CERTAIN PORV*.**.***..*.**..**.*************** ~/.~ ******.**********..*.*..***...***......

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il n 0 11.K.3.12.A B&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED llJDS *******.*****. ~ ***********..****.****..*.**.*.........**

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

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Ol CD 11.K.3.12.B ll.K.3.13.A Il.K.3.13.B F042 F043 F043 B&O TASK FORCE - HPCI & RCIC SYSTEM INITIATION LEVELS ANALYSIS *.**.*********** ~/.~................................

B&0 TASK FORCE - HPCI & RCIC INITIATION LEVELS MODIFICATION ***..************.* ~/. ****************.****..**..******. **** 9 ***

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.. I ,_,LTI-PLANT 1(1 [l ISSUL NlJolBER ACTION NO. ISSUE TITLE LICEHSEE IMPLEMENTATION STATUS

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,,,"'"' *ll.K.3.14 F044

  • B&O TASK FORCE - ISO CONDENSER ISOLAHOH ON HIGH RAD .**.**.**.************. NI.A. *.*.****.**..**.....**......*******..... _

c:o U) Jl.K.3.15 F045 B&O TASK FORCE - tEOIFY HPCI & RCIC BRK DETECTJON CIRCUITRY **.*...**.****.* NI.A. **..**....*.*...........*............*..

ll.K.3.16A F046 -B&O TASK FORCE - CffALLEHGE & FAILURE OF RELIEF VALVES STUDY .*****.*.**.**** NIA .*.***.....****..****......*.****....... _

ll. K. 3.16. 8 F046 B&O TAS<< FORCE - CHALLENGE & FAILURE OF RELIEF VALVES tllDIFICATIONS ****..** NIA *.......*.*.**......**.**..******........

Jl.K.3.17 F047 B&O TASK FORCE .,. ECC SYSTEM OUTAGES *****..*...*.......*.....*..*...*****.** ~- *..**.************...**.***..***..**...*.. _

Ill JI. K. 3.18.A F048 B&O TASK FORCE - ADS ACTUATION STIJDY *****.**......*.....*...*..*.***.***.** NIA .*..**.........*..*.*...**...*..........

(~ TI.K.3.18.8 F048 B&O TASK FORCE - ADS ACTUATION PROPOSED llJDIFICATIONS ..**..****.*.********* WA ....................................... .

.,. I I. K. 3.18. C F048 e&o TASl FORCE - ADS ACTUATION MOOIFICATIONS .*.... ; .*.***********.***.***** NIA *....**....*...............*..**........ -

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tD ... *ll.K.3.19 F049 B&O TASK FORCE - INTERLOCK RECIRCULATORY PUMP tllDIFICATIONS ******.******.** NIA *.*..............................~ ... .

N 0 fl, *II. K. 3.20 B&O TASK FORCE - LOSS OF SVC WATER AT BRP .*..**.....*.*..*.*.*.**..*..***** N/A ..................................- .. .

C\I ,_I f LK. 3.21. A F050 B&O TASK FORCE - RESTART OF CSS & LPCI LOGIC DESlGfL .*..**.*****.********* NIA ..............*...*..*..................

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11.K. 3.21.8 F050 B&O TASK FORCE - RESTART OF CSS & LPCI LOGIC DESIGN llJDIFICATIONS ********.* NIA .......*................................

IL K.3. 22.A F051 B&O TASK FORCE - RCIC SUCTIOH VERIFICATION PROCEDURES .**.. - ..**.**.**.***.* NIA ...*...............**.................. - -

~ JLK.3.22.8 F051 B&O TASK FORCE - RCIC SUCTION MODIFICATION *...*.......**.*****.************ N/A ......*.................................

(1 I I. K. 3. 24 F052 8&0 TASK FORCE - SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER *************** N/A ..............*......................*...

I B&0 TASK FORCE - POWER OH PtllP SEALS PROPOSED lllDIFICATIONS .********.****** .C************************.*.*******.**......

ll ILK. 3.25.A p; ll.K.3.25.B F053 B&O TASK FORCE - POWER ON PllfP SEALS llJDIFICATIONS ....**.**..****...*****.* NIA .........*.......................*......

B&O TASK FORCE - COMMON REFERENCE LEVEL FOR BWRS ***.*************.*******.* NIA ......****.. -..........*.. : ............ .

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.{fl ILK. 3.27 ll.K.3.28 F054 F055 B&O TASK FORCE - QUALIFICATION OF ADS ACCtl4ULATORS ..*....******..*****.**** NIA .....**..................*..............

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i *l I.K.3.29 F056 BIO TASK FORCE - PERFORMANCE OF ISOLATION CONDENSERS *....**..**.*********** NIA ....*..*................................ -

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Ill II.K.3.30.A 8&0 TASK FORCE - SCHEDULE FOR OUTLINE OF SB LOCA MODEL .................... .C.......................................... .

(") )- Jl.K.3.30.8 F057 BIO TASK FORCE - SB LOCA lllDEL, JUSTIFICATION **..**.**.**.**..*****.******* .C********....***.****........*.***.*........

ll.K.3.30.C B&O TASK FORCE - SB LOCA METHODS NEW ANALYSES .**.*..**.**.**.**.*********.* ~- ......................................... .

C1J ID ~ 11. K. 3. 31 F058 B&D TASK FORCE - COMPLIANCE WITH CFR 50. 46 *.*....*..**.*..*..*...*****.***.*C**.************.*****.*..***.*.*. ~ ...*.....

...I p,... *JLK.3.40 B&O TASK FORCE - RCP SEAL DAMAGE - COVERED BY l I. K. 2. 16 AND II. K. 3. 25 *.***.*C*.**********.**..***.***....**.*.*...*.....

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

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  • I I. K. 3.43 B&O TASK FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE ****.***..*****.**** JV.A *****.*****.***.****...*.*.**.*...*..*..

Il.K.3.44 f059 I I. K. 3-45 FOGO B&O TASK FORCE - ANALYSES TO SUPPORT .******.*******.****.*************.**** JV.I\. * * *.** * ** * * * * * * * . * * * * * * * * * * * * * * * * * * * * * * *

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F061 RESPONSE TO LIST OF CONCEHftS FROM ACRS CONSULTANT ****.*..*.**************** JV.I\. ....................................... .

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II. K. 3.46 Ill C1J C\I 0

  • I I. K. 3. 57 F062 IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS ****.*.***.******** tt(l\....................................... ..

ex m JIJ.A.1.1 EMERGENCY PREPAREDNESS~ SHORT TERM******. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * ******..***..

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  • 11 ()

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0 II l. A. 1. 2 . 1 'UPGRADE EMERGENCY SUPPORT FACILITIES - INTERIM TSC OSC & EOF ****.********.*** C......................................... .

lll.A.1.2.2 UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/F064/F065 ****.* ~~~-~9t~~---*******************************

(SEE F063, F064, f065)

II I. A. l. 2. 3 UPGRADE EMER SUPPORT FACILITIES - tlJDS INCORPOR. INTO F063, F064 &F065 ****** ~~~-~9t~~ .....*...............*..* :;'. ...... .

(SlE F063, F064, F065)

Ill Ill.A.2.1 F067 UPGRADE PREPAREDNESS - UPGRADE EMERGENCY PLANS TO APP. E. 10 CFR 50 .........* ~ .......*..................................

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111.A.2.2 F068 UPGRADE PREPAREDNESS - METEOROLOGICAL DATA ................................... C*..****...**.****.********..**.........*..

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1' I *lll.0.1.1.1 PRIMARY COOLANT OUTSIDE CONTAINMENT - LEAK REDUCTION ......................... C**********..**.*******************.*......

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

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  • llL0.1.1.2 IJI.0.3.3.1 INPLANT RAD. l<<JNIT. - PROVIDE MEANS TO DETER. PRESENCE OF RADIOIOOINE .******
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    • III.0.3.3.2 F069 IMPLANT AADIATIOH MONIT. - tl>DIFICATIONS TO ACCURATELY MEAS. IODINE ******.*************************..*.***..**..* 9- .. .

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

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Jt, 111.0.3.4.1 F070

~ *lll.D.3.4.2 F070 CONTROL ROOl'I HABITABILITY - SCHEDULE MODIFICATIONS ........................... C c*************.*****************.********..

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(1 *IIl.0.3.4.3 CONTROL ROOM HABITABILITY - IMPLEMENT llH>IFICATIONS .***..***********.*******.**. ~~- ****.**********************..*..*....*

I MPA-fOOB F008 1t I. 0.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN ...........*.....*.. -~~~ .~9t~~- rn.. J... Q.J .................... r **

(I MPA-F063 F063 III.A. I. 2 TECHNICAL SUPPORT CENTER ......................................*....~Etet .fiQt~~ ................................. .

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HPA-F064 MPA-F065 F064 F065 111. A. 1. Z OPERATIONAL SUPPORT CENTER ****.**..*.*..**.****.**..*.***.**.****** C......................................... .

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

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) MPA-F07l F071 *I. D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWP TO f-8) ..... ~ ................ -~~(;!. ~9t~~- !'~.*. J...Q** L ..................... .

MPA-8072 8072 lllJREG-0737 TECH SPECS (GENERIC LETTERS 82-16 & 83-02) ........................ C......................................... .

ID tO MPA-8083 8083 i'-TECH SPEC COVERED BY GENERIC LETTERS 83-26 & 83-37 FOR NlJREG-0737 ............ $~~-~9t~?................................. .

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

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

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

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