ML18153B525

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Notice of Violation from Insp on 880801-05.Violation Noted:Licensee Discovered That Relief Valve 2-CH-RV-2209 Not Tested During 1985 Refueling Outage as Required
ML18153B525
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/29/1988
From: Gibson A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18153B524 List:
References
50-280-88-30, 50-281-88-30, NUDOCS 8810120222
Download: ML18153B525 (2)


Text

ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Company Surry Docket Nos. 50-280,281 License Nos. DRP-32,37 During. the Nuclear Regulatory Commission (NRG) inspection conducted on August 1-5, 1988, a violation of NRG requirements was identified.

In accordance with the 11General Statement of Policy and Procedure for NRC Enforcement Actions, 11 10 CFR Part 2, Appendix C (1987), the violation is listed below:

10 CFR 50.55a(g)(4)(ii) requires the performance of inservice tests to verify operational readiness of pumps and valves, whose function is required for safety, in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV) Code Section XI.

  • B&PV Code,Section XI, 1980 Edition Winter 1980 Addenda (80W80)~ has been identified as the applicable code for inservice testing of pumps and valves.
1)
2)

ASME B&PV Code,Section XI, 80W80 Paragraph IWV-3510 as implemented by Administrative Procedure SUADM-M-18, dated March 15, 1988, requires that..* at each refueling all valves (safety and relief) which have not been tested during the preceding five year period shall be tested.

Administrative Procedure SUADM-M-18 dated December 14, 1987, requires that all deviation reports be presented to the Station Nuclear Safet) and Operating Committee (SNSOC), for their review and concurrence with the corrective actions completed or planned, in a timely manner.

Contrary to* the above, 1) on February 23, 1988, in response to an NRC request for records of completed valve tests, the licensee discovered thai, relief valve 2-CH-RV-2209 had not been tested during the 1985 refueling outage as required.

2) As of August 5, 1988~ Deviation Report SZ
  • 0099, which was initiated on February 23, 1988, had not been *presented to SNSOC for review and concurrence of planned corrective actions.

Ther.~-

fore, opportunities to test the valve since the finding were ignored and no effort.was made to evaluate the valve's capability to perform its

  • intended function until such an evaluation was specifically requested* by the inspector.

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

8810120222 880929 PDR ADDCK 05000280 i.*

Q PNU

Virginia Electric and Power Company Surry 2

Docket Nos. 50-280,281 License Nos. DRP-32,37 Pursuant to the prov1s1ons of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATIN:

Document Control Desk, Washington, DC

20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Surry, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation" and should include [for each violation]:

(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the* results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance wi 11 be achieved.

Where good cause is shown, consideration will be given to extending the response time.

If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73. 21.

Dated at Atlanta, Georgia this ~

day of ~~~88 FOR THE NUCLEAR REGULATORY COMMISSION

~ f\\\\1s ~)cho~

Albert F. Gibson, Director Division of Reactor Safety