ML20211C478

From kanterella
Revision as of 21:25, 1 December 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Notice of Violation from Insp on 861209-870114
ML20211C478
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/10/1987
From: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211C439 List:
References
50-281-86-42, NUDOCS 8702200105
Download: ML20211C478 (2)


Text

-..- ... - - - - - . - . - - =

ENCLOSURE 1 NOTICE OF VIOLATION l Virginia Electric \and Power Company Docket No. 50-281 1 Surry Unit 2 License No. DPR-37 i
During the Nuclear Regulatory Commission (NRC) inspection conducted between the period of December 9, 1986, to January 14, 1987, a violation of NRC require-ments was identified. The violation, which was identified during the licensee's i evaluation of the cause of the failure of the main steam trip valve, involved failure to provide detailed instructions in maintenance procedures for correc-4 tive maintenance of safety-related equipment. In accordance with the " General '

Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2,

! Appendix C (1986), the violation is listed below:

i i Technical Specification 6.4.A requires that detailed written procedures

with appropriate check-off lists and instructions shall be provided for i

preventive or corrective maintenance operations which would have an effect on the safety of the reactor. Corrective Maintenance Procedure MMP-C-MS-002, " Corrective Maintenance Procedure for Inspection of Main Steam Trip Valve TV-MS " provides instructions for the overhaul / repair of the main steam trip valves.

. Contrary to the above, in the instances cited below, the maintenance l

! procedure used to overhaul main steam trip valve 2-MS-TV-201C during the period of October 23-28, 1986, lacked detailed instructions, was not fully followed, and did not provide adequate documentation to show that the work i associated with the repair of a safety-related component was accomplished in a quality manner, j 1. Step 5.4.8 of MMP-C-MS-002 requires installation of two radius levers

to the rock shaft without proper control to assure correct alignment during reassembly. During valve disassembly after the event, the '
radius levers were determined to be misaligned on the rock shaft.  ;

l 2. Step 5.4.12 of MMP-C-MS-002 verifies that Qe arc opening of the valve after reassembly was 80 degrees. During valve disassembly after the event, the arc opening was checked and was determined to be 75 degrees.

3. Step 5.4.15 of MMP-C-MS-002 requires that the valve cover be rein-stalled, but it does not specify adequate control to assure correct I alignment during reassembly. During valve disassembly after the event, j the cover was determined to be misaligned preventing full opening of i the trip valve during plant operation.

t I .

4--

g22%$ Ee [

o .  :

a r , . . . - _ . . , . ,. ,..-_,.__,_,_.._,_,y,,,.,__._,--_,_,,,_m._. my _.._ w-__._. .f. . , , ., -r**we----'---vnew'm+ ' ' " * = wm-e-Ne'**t

O e

Virginia Electric and Power Company 2 Docket No.96-281 Surry Unit 2 License No. DPR-37

4. Step 6.3 of MMP-C-MS-002 requires that appropriate post maintenance testing be. identified to establish acceptability of the equipment; however, no testing was specified which would have identified the deficient reassembly of the trip valve.

ThisisaSeherityLevelIVviolation(Supplement 1).

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: (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. <

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.

FOR THE NUCLEAR REGULATORY COP 94ISSION

.  : M J. Nelson Grace .

Regional Administrator Dated at Atlanta, Georgia this 10th day of February 1987 g

.