ML20082R660

Special Rept:On 950404,discovered That Manual Isolation Valves for 'A' Channel in Closed Position.Cause of Failure to Correctly Position Valves Will Be Assessed.Valves Placed in Required Position & Demonstrated Operability

ML20082R660
Person / Time
Site:	Monticello
Issue date:	04/19/1995
From:	Hill W NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9505020160
Download: ML20082R660 (2)

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Northem States Power Company Monticello Nuclear Generating Plant ,

2807 West hwy 75 l

Monticello. Minnesota 55362-9637 j 1

April 19,1995 Technical Specification 3.14 l Operations Manual B.S.18 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 ,

1 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 l Special Report Required by Monticello Technical Specification 3.14 and Monticello Operations Manual Section B.5.18 Monticello Technical Specifications, Section 3.14, " Accident Monitoring Instrumentation" specifies limiting conditions for operation for instrumentation which does not perform a protective function, but which does provide information to monitor and assess important parameters during and following an accident. Technical Specification Section 3.14 requires two channels of Drywell and Suppression Pool Hydrogen and Oxygen (H2/02) Monitors to be operable. With one channel operable, Technical Specifications require that the inoperable channel be restored to operable status within seven cap, or prepare and submit a special report within the next 30 days outlining the actions taken, ihe cause of the inoperability and the plans and schedule for restoring the system to operable status. Also. Manticello Operations Manual Section B.5.18, Pos+ Accident Sampling System, states that if the system is out of service for greater than 7 days a voluntary report shall be written to the NRC within the following 30 days. This letter provides the above specified reports. l l

On March M,1995, the Post Accident Sampling System (PASS) and the 'A' channel of the Drywell and Suppression Pool H2/02 Monitors were isolated from service to perfonn l maintenance on a PASS excess flow check "alve (PAS-59-3). On March 15,1995, the work  !

was completed on the excess flow check valve and the isolation valves were to be returned to their normal open position, however, this did not occur. Consequently, the 'A' Channel of the l Drywell and Suppression Pool H2/02 Monitors and PASS remained inoperable, j On April 4,1995, during a calibration test of the Drywell and Suppression Pool H2/02 Monitors, l it was discovered that manual isolation valves for the 'A' channel were in the closed position.

Operations personnelinitiated a Nonconformance Report (NCR No: N95-053) to address this nonconformance. Immediate considerations regarding operability and reportability were assessed. The following immediate actions were taken:

• The valves were placed in the required position for PASS and H2/02 Monitor operability

• It was demonstrated that PASS and H2/02 Monitor flow operability requirements were met

• Appropriate personnel were notified including the NRC Resident inspector and the Plant Manager pl D 9505020160 950419 (,l/ i PDR ADOCK 05000263 nie: J:\DOO60\MONTIUi!\NRCCORR\TS3-14SR.0DC S PDR

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USNRC NORTHERN STATES POWER COMPANY April 19,1995 Page 2 l

1 As part of the NCR process the root cause of the failure to correctly position the isolation valves will be assessed and further corrective actions will be initiated if required. j This letter contains no new NRC commitments, nor does it modify any prior commitments.  !

Please contact Mel Opstad, Sr Licensing Engineer, at (612) 295-1653 if you require further information.

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William J Hill Plant Manager Monticello Nuclear Generating Plant c: Regional Administrator-Ill, NRC NRR Projcct Manager, NRC Sr Resident inspector, NRC  ;

State of Minnesota l Attn: Kris Sanda J E Silberg l

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