ML20210L081

Notice of Violation from Insp on 970414-0608.Violation Noted:Ist Requirements of 10CFR50.55a(f) Were Implemented Without Authorization of Director of NRR as Listed

ML20210L081
Person / Time
Site:	Maine Yankee
Issue date:	07/11/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20210L065	List: IR 05000309/1997005 ML20210L059 ML20210L081
References
50-309-97-05, 50-309-97-5, NUDOCS 9708200214
Download: ML20210L081 (4)

Text

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NOTICE OF VIOLATION M:ine Yankee Atomic Power Company Docket No. 50 309 Brunswick, Maine 04011  : License No. DPR - 36

-During an inspection conducted between April 14,1997 and June 8,1997, violations of NRC r:quirements were identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violations are listed below:

-A. Technical specification 3.13, Refueling and Fuel Consolidation Operations, requires in part, "A.

Prior to each refueling a complete checkout shall be conducted on fuel handling cranes that will be used to handle irradiated fuel assemblies "-

Contrary to the above, from May 19,1997, through May 26,1997, there were three instances of inadequato checkouts performed on fuel handling cranes by Maine Yankee as follows:

On May-19,1997, Maine Yankee identified that a previously untested spent fuel pool crane interlock failed to function. The interlock was designed to protect fuel from-inadvertent raising or lowering during trolley or bridge operation.

On May 25,1097, the mechanical stops to limit crane travel in the north direction were ,

- found mis positioned during fuel movement. The stops were designed to prevent fuel damage due to running into the side of the pool.

On May 26, 2997, Indicator lights for the load indicator of the fuel transfer machine were not functioning properly and had not been tested prior to use. The lights were designed to indicate the proper load indicator scale to be monitored ta prevent damage to a fuel bundle during transport through the refueling canal.

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This is a Severity LevelIV violation (Supplement 1).

B. 10 CFR 50, Appendix B, Criteria XVI Corrective Actions, requires in part, that in the caso of significant conditions adverse to quality, measures shall assure the cause of the condition is t

determined and corrective action is taken to preclude repetition.

Contrary to the above, on May 18,1997, damage to a 480 volt electrical cable during fuel movement with the spent fuel pool crane, a significant condition adverse to quality, was identified that should have been prevented by corrective actions taken for a March 4,1997, event involving running the spent fuel pool crane into a safety rail stanchion.

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

C. .10 CFR 50.55a(a)(3) requires, in part, that proposed alternatives to the inservice test (IST) requirements of paragraph (f) must be authorized by the Director of the Office of Nuclear Reactor Regulation. Paragraph (f)(4)(ii) requires that inservice tests to verify operational readiness of pumps and valves whose function is required for safety must comply with the requirements of the latest edition of _the Code incorporated by reference in paragraph (b). The Maine Yankee IST program utilizes the 1986 Edition of Section XI of the American Society of Mechanical Engineers

-(ASME) Boiler and Pressure Vessel Code.

9708200214 970711

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10 CFR 50.55a(f)(4)(lv) states that inservice tests of valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met. On September 8,1992, the Commission incorporated the 1989 Edition of the ASME Code in paragraph (b), including Part 6 (OM 6) and Part 10 (OM 10) of the ASME/ ANSI OMa 1988 Addenda to ASME/ ANSI OM-1987.

OM-6, paragraph 6.1 requires that if pump performance deviations fall within the alert range of Table 3, the frequency of testing shall be doubled until the cause of the deviation is determined and the condition corrected. Table 3a specifies that the maximum vibration alert limit for verticalline shaft pumps is greater than 0.325 inches per second.

The NRC Safety Evaluation Report for the Maine Yankee third 10-year interval IST program, dated June 30,1994, approve the use of reference values to evaluate power operated valve stroke time measurements pursuant to OM-10 in lieu of the methods prescribed in Section XI, Article IWV 3417(a) of the Code (1986 Edition),

provided all related test method and corrective action requirements of paragraphs 4.2.1.3 through 4.2.1.9 of OM 10 were implemented.

Contrary to the above, alternatives to the IST requirements of 10 CFR 50.55a(f) were implemented without the authorization of the Director of the Office of Nuclear Reactor Regulation as follows:

(1) Since December 28,1992, reference values were used to evaluate power-operated valve stroke time measurements pursuant to OM 10 in lieu of the methods prescribed in Section XI, Article IWV 3417(a) of the Code (1986 Edition), and the related test method and corrective actions requirements of paragraphs 4.2.1.3 through 4.2.1.9 of OM-10 were not implemented.

(2) In June 1996, an alternative maximum vibration alert limit in excess of the limit specified in Table 3a of OM 6 was implemented for containment spray pump P 61S, and the frequency of testing was not doubled, the cause of the deviation was not determined, and the condition was not corrected.

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

D. 10 CFR 50.5Salf) requires in part that inservice testing of certain ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda. 10 CFR 50.55a(f)(4)(iv) permits portions of subsequent editions or addenda, incorporated by reference in 10 CFR 50.55a(b), to be used provided that all related requirements of the respectiva editions or addenda are met.

Part 6 (OM 6) of the ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM 1987, paragraph 4.4, requires that when a reference value may have been affected by repair, replacement, or routine servicing of a pump, a new reference value shall be

-3 determined or the previous value reconfirmed b'y an inservice test run prior to '

- declaring the pump operable. Verification that the new values represent acceptable

pump operation shall be placed in the record of tests.-

- Contrary to the above, on April 9,1992, following repair of service water pump P 29D, new vibration reference values were not determined and previous values -

y were not reconfirmed by an inservice test run prior to declaring the pump operable, and the verification that the new values represent acceptable pump operation was not placed in the record of tests, y This is a Severity Level IV violation (Supplement 1). -

- E. 10 CFR 50, Appendix B, Criterion XI, Test Control, requires that a test program 4

i shall be established to assure that all testing required to derhonstrate that

components will perform satisfactorily in service is performed in accordance with written test procedures which incorporate acceptance limits contained in applicable design documents. Part 6 (OM 6) of the ASME/ ANSI OMa 1988 Addenda to ASME/ ANSI OM-1987, Table 3a, requires pump vibration alert and required action acceptance criteria to be established at the more conservative range of greater than

(>) 2.5Vr to 6Vr (where Vr is the vibration reference value) or >0.325 inches per i: second (ips) and >0Vr or >0.70 ips, respectively.

Contrary to the above, since December 28.1992, testing required to demonstrate that components will perform satisfactorily in service was not performed in accordance with written test procedures which incorporate acceptance limits contained in applicable design documents in that the more conservative range of 4

pump vibration alert and required action acceptance criteria prescribed in OM-6, Table 3a were not established.

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

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_ Pursuant to the provisions of 10 CFR 2.201, Maine Yankee Atomic Power Company is horeby required to submit a written statement or explanation to the U.S. Nuclear

- __ 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 f acility 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, (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 the Notice, an order or a Demand for Information may

'.be issued as to why the license should not be modified, suspended, or revoked, or why 4 -'-

- 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.

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Because your resoonse will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or scieguards information so that it can be placed in the PDR without reduction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.

Dated at King of Prussia, PA on 11th day of July,1997