ML20236T160

Notice of Violation from Insp on 980517-0627.Violation Noted:As of Oct 1997,chemistry Technicians Did Not Sample & Analyze Diesel Fuel Oil Deliveries for Particulates & Did Not Report Results by Written Notification within 14 Days

ML20236T160
Person / Time
Site:	Hope Creek
Issue date:	07/21/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20236T152	List: ML20236T150 ML20236T160
References
50-354-98-06, 50-354-98-6, NUDOCS 9807270468
Download: ML20236T160 (3)

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ENCLOSURE 1 NOTICE OF VIOLATION Public Service Electric and Gas Company Docket No:

50-354 Hope Creek Generating Station License No: NPF 57 During an NRC inspection conducted between May 17,1998, through June 27,1998, violations of NRC requirements were identified. In accordance with the " General l

Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, Revision j

1, the violations are listed below:

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'A.

Technical Specification 6.8.1 requires, in part, that written procedures shall be established, implemented, and maintained for applicable activities recommended in Appendix.A of NRC Regulatory Guide 1.33, Revision 2, February 1978.

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l Appendix A of NRC Regulatory Guide 1.33, Revision 2, February 1978 (Section 10) recommends that chemical control procedures be written to prescribe the nature and frequency of sampling and analyses, i

Hope Creek chemistry procedure HC.CH-AP.ZZ-0014(Q), Hope Creek Generating l

Station Diese/ Fuel Oi/ Testing Program, Revision 2, Section 5.1, requires that all diesel fuel oil deliveries (via tank truck) will be sampled and analyzed for particulate, and results reported by written notification within 14 days of sample receipt to ths Hope Creek System Manager and the Fuel Oil Program Manager.

Contrary to the above, as of October 1997, chemistry technicians did not sample and analyze diesel fuel oil deliveries for particulate, and did not report results by L

written notification within 14 days of sample receipt to the Hope Creek System L

Manager and the Fuel Oil Program Manager.

This is a Severity Level IV violation (Supplement 1).

B.

10 CFR Part 50, Appendix B, Criterion lli (Design Control), requires, in part, that measures shall be established to assure that applicable regulatory requirements and the design bases are correctly translated into specifications, drawings, procedures, and instructions. The design control measures shall provide for verifying or l

checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.

Contrary to the above, during the RFO7 refueling outage (Fall-Winter 1997),

l design change package (DCP) 4EC-3638 incorrectly changed the design basis of the -

reactor core isolation cooling (RCIC) system by removing a timing sequence feature for the RCIC turbine steam line stop valve (F045). In addition, a design review of DCP 4EC-3638 and post-modification testing for DCP 4EC-3638 failed to identify the design error.

This is a Severity Level IV violation (Supplement 1).

l 9907270468 990721 P

l PDR ADOCK 05000354 E l

0 PDR 1,

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2 Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit a written statement or explanation to the U.S. Nuclear l

Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a

" Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation or severity level, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response if an adequate reply is not received within the time specified in this Notice, an order or a Demand for information i

may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, i

Washington, DC 20555-0001.

1 Because your response will be placed in the NRC Public Document Room (DDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withhold-ing (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at King of Prussia, Pennsylvania this 21st day of July 1998 l

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Mr. Harold W. Keiser 3

Distribution w/encis:

Region I Docket Room (with concurrences)

Nuclear Safety Information Center (NSIC)

NRC Resident inspector FUBLIC H. Miller, RA/W. Axelson, DRA D. Screnci, PAO (1)

J. Linville, DRP S. Barber, DRP L. Harrison, DRP C. O'Daniell, DRP Distribution w/encis: (Via E-Mail)

B. McCabe, OEDO R. Ennis, Project Manager, NRR R. Capra, PDI-2, NRR inspection Program Branch, NRR (IPAS)

R. Correia, NRR D. Talbot, NRR DOCDESK DOCUMENT NAME: G:\\ BRANCH 3\\1-HC\\lR9806.HC

' T0 receive a copy of this document. Indicato in the box: *C" = Copy without attachment / enclosure

• E" = Copy with attachment / enclosure "N" = No COPY-OFFICE RI/DRP l

RI/DRP m,gl

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Pindale/meo Linvi)le%f f DATE 07/21/98 07/JJ/9W 07/

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