ML18152A589

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Notice of Violation from Insp on 870928-1002.Violation Noted:Inservice Tests Not Performed as Required by ASME B&PV Code Section XI to Verify Operational Readiness of Pumps & Valves,Whose Function Required for Safety
ML18152A589
Person / Time
Site: Surry  Dominion icon.png
Issue date: 10/28/1987
From: Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18152A588 List:
References
50-280-87-30, 50-281-87-30, NUDOCS 8711130250
Download: ML18152A589 (2)


Text

ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Company Surry Units 1 and 2 Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 During the Nuclear Regulatory CoR1Tiission (NRC) inspection conducted on September 28 - October 2, 1987; violations of NRC requirements were identified.

The viol a tions involved the 1 i censee fa i 1 ure to perform or ask relief from performing valve i nservi ce tests required by the ASME code and the use of superseded test procedures. In accordance with the 0 General Statement of Policy and Procedure for NRC Enforcement Actions, 11 10 CFR Part 2, Appendix C ( 1987),

the violations are listed below:

A.

10 CFR 50. 55a(g)(4}(ii) requires the performance of inservice tests to verify opera ti anal readiness of pumps and valves, whose function is.

required for safety, in accordance with the American Society of Mechanical Engineers Boil er and Pressure Vessel (ASME B&PV) Code Section XI.

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

ASME B&PV Code,Section XI, 80W80 paragraph IWV-3411, states in part:

"If only limited operation is practical during plant operation, the valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns."

Contrary to the above, inservice tests are not performed as required by ASME B&PV Code Section XI to verify operational readiness of pumps and valves, whose function is required for safety, in that approximately 56 valves which are only full-stroke exercise tested at cold shutdown or refueling shutdown outages have not been part-stroke exercise tested during plant operations.

In addition relief from the part-stroke exercise testing has not been requested for these valves.

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

B.

10 CFR 50 Appendix B, Criterion V requires that activities affecting quality be accomplished in accordance with procedures.

Procedures No. SUADM-ADM-18 of July 17, 1987, 0 Document Control" paragraph 5.1.l(l){b) states in part"

" *.* New and revised procedures will be implemented not later then seven days after approval *by the Station Nuclear Safety and Operating Committee.

11 (SNS&OC)

Contrary to the above, procedures were not followed in that two inservice valve test procedures {1-PT-25.1, "Quarterly Testing of CW and SW System Valves" and 2-PT-18.6A, Quarterly Testing of Safety Injection MOV' s and HCV's) were performec using superceded procedure revisions 22 and 16 days,

~711130250 871028 8DR ADOCK 05000280 PDR

Virginia Electric and Power Company Surry Units 1 and 2 2

Docket Nos. 50-280, 50-281 License Nos. DPR-32,_ DPR-37 respectively, after the seven day grace period following the approval of the new procedure revisions by the SNS&OC.

This is a Severity Level V violation {Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including (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.

Dated at Atlanta, Georgia this~day of October 1987 FOR THE.NUCLEAR REGULATORY COMMISSION tlr/jiMi. Si9nd bjj

r. '&.oJ::e Alan R. Herdt, Chief Engineering Branch Division of Reactor Safety