ML20149H922

Notice of Violation from Insp on 970528-0707.Violation Noted:Reactor Bldg Closed Cooling Water Valve 2-2 & Associated Piping Removed from Pump,However,Safety Tag on Valve Had Not Been Properly Released

ML20149H922
Person / Time
Site:	Monticello
Issue date:	07/17/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20149H920	List: ML20149H918 ML20149H922 ML20149H929
References
50-263-97-08, 50-263-97-8, NUDOCS 9707250251
Download: ML20149H922 (2)

Text

,

i NOTICE OF VIOLATION I

Northern States Power Company Docket No. 50-263 1

Monticello Station License No. DPR-22 During an NRC inspection conducted on May 28 through July 7,1997, a violation of NRC requirements was identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600 (60 FR 34381; June 30,1995),

the violation is listed below:

1 10 CFR 50 Appendix B, Criterion V, " Instructions, Procedures, and Drawings," required that activities affecting quality be prescribed by, and accomplished in accordance with,

{

documented instructions, procedures, or drawings.

a.

Administrative Work instruction (AWI) 04.04.01, " Equipment isolation," step 4.2.1, I

stated that safety-tagged equipment shall not be operated until the safety tag has been properly released.

1 Contrary to the above, on May 29,1997, the inspectors identified that reactor building closed cooling water (RBCCW) valve 2-2 and its associated piping were l

removed from the RBCCW pump; however, a safety tag (a hold-and-secure card) on the valve had not been properly released.

Also, on June 6,1997, the inspectors identified that the refueling bridge air compressor blowdown valve was repositioned from the OPEN position to the i

CLOSED position: however, a safety tag on the valve had not been properly released.

b.

Northern States Power Company Operational Quality Assurance Plan, Revision 20, Section 8.5, " Drawing Control," required that drawings which represent physical and functional aspects of the operating nuclear plant which are critical to safe plant operation shall be maintained in a current status.

Administrative Work Instruction 4 awl-02.04.01, " Drawing Control," Revision 5, section 4.3.2, required that Class 1 and 2 drawings shall be revised to represent current plant status.

Contrary to the above, on June 9,1997, the inspectors identified eight examples where Class 1 and 2 drawings did not represent current plant status. These examples includeo inc+alled fuses different from that specified in drawings, protection fuses not sho un on drawings, and differences between Class 1 and 2 drawings.

Thi.s is a Severity Level IV violation (Supplement 1).

9707250251 970717 PDR ADDCK 05000263 G

pg

. _. ~. ~ -

L l

L l

Notice.of Violation l~

. Pursuant to the provisions of 10 CFR 2.201, NortSern States Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory 1-Commission, ATTN: Document Control Desk,' Washington, D.C. 20555 with a copy to the L l

Regional Administrator, Region 111, and a copy to the NRC Resident inspector at the Monticello Nuclear, Generating Plant, within 30 days of the date of the letter transmitting this Notice of Violatiori (Notice). This reply should be clearly marked as a " Reply to a-Notice'of Violation" and should include: (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 L

results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. if an adequate reply is not received l

~ within the time specified in this Notice, an order may be issued to show cause why the -

i license should not be modified, suspended, or revoked, or why 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.

l Because your response will be placed in the NRC. Pubic Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be'placed in the PDR without redaction. If personal privacy or' proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to l

support a request for withholding confidential commercial or financial information), if safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

j Dated at Lisle, Illinois, l

this 17th day of July 1997 l

l 1

o i

f i

I J