ML20078C084

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Submits Response to Violations Noted in Insp Rept 50-354/94-13.Corrective Actions:Design Change Implemented to Correct Design Deficiency
ML20078C084
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 10/18/1994
From: Hagan J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N94180, NUDOCS 9410280080
Download: ML20078C084 (5)


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Pubhc SeNice Dectnc and Gas Company aoseph J. Hagan Pubhc Service Electnc and Gas Company P O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 vm.,,_,.,m.0 -.

00T 181994 NLR-N94180 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REPLY TO A NOTICE OF VIOLATION INSPECTION REPORT NO. 50-354/94-13 HOPE CREEK GENERATING STATION FAC..ITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Pursuant to the provisions of 10CFR2.201, this letter submits the response of Public Service Electric and Gas Company to Part A of the notice of violation issued to the Hope Creek and Salem Generating Stations in a letter dated September 19, 1994.

Response to Part B of the notice of violation will submitted in a i

t separate letter (NLR-N94184).

As required by the notice of violation and 10CFR2.201, this response includes a written statement or explanation in reply, including, where applicable, the corrective steps which have been taken and the results achieved, the corrective steps which will be taken to avoid further violations, and the date when full compliance will be achieved.

This information is provided in the attachment to this letter.

Should you have any questions or comments on this transmittal, do not hesitate to contact us.

Sincerely, 1

m Attachment

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r' yko QCK05000354 go 94.01a O

f,t/l PDR g

OCT18 3994 Document Control Desk 2

NLR-N94180 C

Mr. T.

T. Martin, Administrator - Region I U. S.

Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr.

D. Moran, Licensing Project Manager - Hope Creek U.

S.

Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. R.

Summers (SOS)

USNRC Senior Resident Inspector Mr.

K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 I

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REF:

NLR-N94180 STATE OF NEW JERSEY

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SS.

COUNTY OF SALEM

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J. J.

Hagan, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief.

c>v Subscribed and Sworn o before me this /8 day of.'$ lrN u A ',

1994 V

YV) l.M A_. L4 10%v\\

Notary Public of New Jersey KIMBERLY JO BROWN NOTABY PUBLIC Of NEW JERSEY My Commissinn Irpires April 21,1998 My commission expires on

ATIN3ME2(f REPLY 'IO A IKTf1CE OF VIDIATIOT Ilcim;nOi REIUG NO. 50-354/94-13 IDPE QEEK GENERATI!G SIATIOT FmT. TTY OPERATIlU LICE 2EE NPF-57 DOCKET 10. 50-354 NIR-N94180 I.

IITITODUCTIGT I

Durity inspection activities conducted between June 26 and August 6, 1994, the l

NRC identified a violation of NRC requirements at Hope Creek which was l

Weently du'ented and cited as part of a notice of violation issual in l

l Inspection Report 354/94-13 dated September 19, 1994. Our response to Part A i

l of the ni ice of violation (the Hope Creek violation) is provided below.

Response to Part B (a Salem violation) will be provided in a separate letter (NIR-N94184). Detailed discussion of the issues associated with the Hope Creek violation are contained in IER 94-009-00 dated August 17, 1994.

II. REPLY 'IO IKTTICE OF VIOIATIOJ 1.

Description of Violation I

" Hope Creek 'Ibchnical Specification 3.3.7.4 requires, in part, that remote I

shutdown system controls shall be operable in Operatirg Cbnditions 1 arxi 2.

I Operability of the Remote Shutdown Panel requires the ability to remotely l

operate valve DC-IN-F004A (the "A" Insidual heat renoval suppression pool suction valve).

n.<.rary to the above from July 25,1986 (issuance of the license for Hope Cruck operation) until July 7,1994, the renote shutdown system control for valve DC-IN-F004A, which effects the remote operation of the valve from its remote shutdown control station, was not operable in that the valve could not be properly controlled frum the remote operating switch in acconiance with plant design."

2.

Response to ViqlatioI)

PSE&G does not deny this violation.

'Ihe root causes and currective actions associated with this violation are provided below arti are consistent with those contained in IER 94-009-00 dated August 17, 1994.

Page 1 of 2

Atthchment NIR-N94180

Root Causes The root causes of the Tedanical Specification non-compliance has been attributed to the follwirg:

j 1.

a design deficiency in the original plant design, I

2.

the subsequent failure to identify the design deficiency tnrough testing as a result of a less than adeqtate surveillance tast procedure that did not specify the proper initial conditions for verifying operability, 3.

inadequate followup by operations personnel when testiry indicated that a problem existed with the valve control circuit, and 4.

a less than adequate retest follwing the troubleshooting of the control circuit.

B, Qprrective Actions Taken and Results Achieved

'Ihe follwing corrective actions have been completed.

1.

A design change has been implemented to correct the design deficiency.

2.

The valve logic for all redundant rumte shutdwn instrumentation was reviewed and the problem was deteanined to be limited to the BC-IN-F004A valve.

L Corrective Actions to Be Take_p The follwing corrective actions will be taken.

1.

The surveillance test procedure for the remote shutdown panel will be reviewed and appropriately revised to ensure control room control switches are set prtperly for test validity.

2.

Operations personnel review of this incident for lessons learned during requalification training will be completed by December 1, 1994.

3.

The surveillance and post maintenance retest program is beirg evaluated to determine if modification is required.

1 D.

Date When Full Compliance Will Be Achieved l

Full compliance has been achieved.

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