ML20246N757

Notice of Violation from Insp on 890710-14.Violations Noted: Verification of Remote Position Indicators at Remote Shut Down Panel Not Being Performed & Record of Results for Relief Valve BSV-19 Vacuum Function Testing Did Not Exist

ML20246N757
Person / Time
Site:	Crystal River
Issue date:	08/21/1989
From:	Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20246N755	List: IR 05000302/1989018 ML20246N750 ML20246N757
References
50-302-89-18, NUDOCS 8909080256
Download: ML20246N757 (2)

Text

_

,. a ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River License No. DPR-72 During the . Nuclear Regulatory Commission (NRC) inspection conducted on July 10-14, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C (1989), the violations are listed below:

-A. Technical Specification 4.0.5 requires inservice testing of ASME Code Classes 1, 2, and 3 pumps and valvn in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. The licensee is committed to inservice testing in accordance with the 1983 Edition of the Code and ~ Addenda subsequent to January 10, 1988; prior to this date the 1974 Code and Addenda was in effect.

a.Section II, Subsection IWV-3520 of the 1974 Code, requires check valves to be full-stroke exercised to the position required to fulfill their function. Full-stroke exercising is required at least once every three months, or during cold shutdown if such operation is not practical during plant operation, unless relief from Code requirements is granted.

Contrary to the above, check vaives BSV-150 and BSV-151 were not full-stroke exercised at least every three months or during cold shutdown following a denial of a relief request, dated May 29, 1987, that proposed alternate testing during five year intervals. '

b.Section XI, Subsection IWV-3300 of- the 1983 Code, requires valves with remote position indicators to be observed at least once every two years to verify that valve operation is accurately indicated.

Contrary to the above, verification of remote position indicators at the remote shutdown panel was not being performed.

c. Section.XI Subsection IWV-6200 of the 1974 Code, requires the Owner to develop and maintain a system of documentation defining all test procedures, including records of the results of such tests.

l Contrary to the above, records of results for relief valve BSV-19 vacuum function testing did not exist.

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

1 spo90802g$$$$$bo2 PDC PDR ADO O

i ___ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ i

Florida Power Corporation 2 Docket No. 50-302 Crystal River License No. DPR-72 B. 10 CFR S0, Appendix J Paragraphs II.G and II.G.1 requires that Type B tests be performed on primary containment penetrations which are pressure-containing or leakage-limiting boundaries whose design incorporates sealant compounds or flexible metal seal assemblies.

Technical Specification 4.6.1.2.d states that Type B tests shall be conducted with gas at Pa, 49.6 psig at intervals no greater than 24 months.

Contrary to the above, Conax electrical penetrations which are pressure-contai ning, leakage-limiting boundaries whose design incorporates sealant compounds and flexible metal seals are not Type B local leak rate tested.

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

Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Crystal River, 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 will 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 enay 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.

FOR THE NUCLEAR REGULATORY CCMMISSION A-Caudle A. Julian, Chief Engineering Branch Division of Reactor Safety Dated at Atlanta, Georgia this21st day of August 1989 l

l l

1 C_____.._