ML20235P859

Notice of Violation from Insp on 870420-23 & 0507-0618. Violations Noted:Weld Not Hydrostatically Tested,No Channel Calibr Performed on Reactor Pressure & Water Level & Annual Repts for CY85 & 86 Not Submitted

ML20235P859
Person / Time
Site:	Oyster Creek
Issue date:	07/10/1987
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20235P833	List: IR 05000219/1987013 ML20235P830 ML20235P859
References
50-219-87-13, NUDOCS 8707200647
Download: ML20235P859 (2)

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I APPENDIX A i

NOTICE OF VIOLATION

{

GPU Nuclear Corporation Docket No. 50-219 )

Oyster Creek Nuclear Generating Station License No. DPR-16 As a result of the inspection conducted April 20-23 and May 7 - June 18,1987 and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), the following violations were identified: '

A. For components,10 CFR 50.55a (g)(4) requires that throughout the service life of the plant the licensee meet the requirements set forth in Section XI of the ASME Boiler and Pressure Vessel Code. For Oyster Creek, the licensee uses the 1980 Edition of Section XI with Winter of 1981 Addenda.

Subarticle IWA-4400, Pressure Test, under Article . IWA-4000, Repair Pro-cedure, in the above edition of the Section XI Code, requires that after l repairs by welding on the pressure retaining boundary, a system hydro-  !

static test . be performed. (There are exceptions specified to this requirement but none that apply to this violation.)

1 Contrary to the above, as of May 21, 1987, weld RF-2-191X (the downstream I weld of feedwater isolation valve V-2-11) was determined not to have been hydrostatically tested following completion of the weld and required post maintenance testing and prior to plant operation.

This is a Severity Level IV Violation (Supplement I).

B. Technical Specification Amendment 114 dated March 20, 1987 implemented requirements for the alternate shutdown monitoring instruments. Technical Specification 3.12.1.1 of this Amendment requires that the alternate shut-down monitoring instruments listed in Table 3.12-6 be operable during reactor power operations and when reactor coolant temperature exceeds 212 F. Technical Specification 4.12.I.1 states "Each of the alternate shut-down monitoring channels shall be demonstrated operable by performance of the channel check and channel calibration operations at the frequencies shown in Table 4.12-1." Table 4.12-1 requires quarterly channel calibra-tions to be performed on reactor pressure and reactor water level (fuel zone).

Q72006A7070710 G ADUCK 05000219 PDR OFFICIAL RECORD COPY IR OC 87 0003.0.0 07/08/87

e Appendix A 2 Contrary to the above, as of June 7,1987, while the reactor was operating at power and the reactor coolant temperature was above 212 F, no channel calibration had been performed on reactor pressure and reactor water level (fuel zone) since November 1986 when the instruments were placed in service nor were calibrations performed on or about March 20, 1987 to demonstrate instrument operability prior to considering the instrument operable in accordance with Amendment 114.

This is a Severity Level IV Violation (Supplement I).

C. 10 CFR 50.59, Changes, Tests, and Experiments, paragraph (b)(2) requires, "The licensee shall submit, as specified in 50.4, a report containing a brief description of any changes, tests, and experiments, including a summary of the safety evaluation of each. The report must be submitted annually or at such shorter intervals as may be specified in the license."

Contrary to the above, as of June 7,1987 the licensee had not submitted the annual reports required for the calender years 1985 and 1986. Also, the reports for the calender years 1983 and 1984 were submitted on March 1, 1985 and March 30, 1987, respectively.

This is a Severity Level IV Violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby required to submit to this of fice, within 30 days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

OFFICIAL RECORD COPY IR OC 87 0004.0.0 07/08/87