ML20212Q750
| ML20212Q750 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/09/1987 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20212Q700 | List: |
| References | |
| JEW-87-001, JEW-87-1, NUDOCS 8702020352 | |
| Download: ML20212Q750 (4) | |
Text
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$)SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. o. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 87-001 U5 SS January 9, 1987 j,;;;
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am J. B. Martin, Regional Administrator
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"I6 U.S. Nuclear Regulatory Commission 3E Region V, Office of Inspection & Enforcement g
m 1450 Maria Lane, Suite 210 m
Walnut Creek, CA 94596 co Docket No. 50-312 Rancho Seco Nuclear Generating Station Unit #1 License No. DPR-54 Response to Notice of Violation (NRC Inspection Reports No.
50-312/86-37)
Dear Mr. Martin:
By letter dated December 12, 1986, the Sacramento Municipal Utility District was transmitted a Notice of Violation concerning the lack of surveillance tests, inspection and calibrations for a radiation monitoring system.
In accordance with 10 CFR 2.201, the District provides the enclosed response to the Notice of Violation.
This letter acknowledges the violation cited and describes our intended corrective actions for each specific item listed in your Notice.
Sincerely,
/ **
,y
' W ohn E. Ward Deputy General Manager, Nuclear Attachment l
cc:
INPO G702020352 8701 l
PDR ADOCK 050 2
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PDR RANCHO SECO NUCLEAR GENERATING STATION E: 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
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ATTACHMENT 1 DISTRICT RESPONSE TO NRC INSPECTION 86-37 NOTICE OF VIOLATION NRC Violation Item B Technical Specifications (TS), Section 6.8.1, reads in part:
" Written procedures shall be established, implemented and maintained covering the activities referenced below: (a) The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, November 1972."
Regulatory Guide 1.33, Appendix A, Item H (1) & (2) lists examples of equipment for which procedures shall be provided to insure measuring and testing devices are properly controlled, calibrated, and adjusted at specific periods to maintain accuracy.
Item H (1) & (2)(a):(28), (29), and (30) includes equipment such as area, process, and environmental 4
radiation monitoring instruments.
l Contrary to the above, procedures for surveillance tests, inspection and calibrations have not been established for radiation monitoring systems R15701 and R15702.
These monitors are used to initiate the Control Room / Technical Support Center emergency filtering system on a high radiation signal.
4 This is a Severity Level IV Violation (Supplement I).
District Response to Violation B 1)
Admission or denial of the alleged violation.
l The District acknowledges and admits that this item occurred as stated.
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2)
Reasons for the violation Radiation monitors R15701 and R15702 were installed per ECN A-3920C.
These monitors would isolate the normal Control Room / Technical Support Center (CR/TSC) HVAC System and start the emergency CR/TSC filtering system upon a high radiation signal.
ECN A-3920C was closed on June 11, 1985.
Initial calibration was conducted in accordance with vendor instructions.
The startup test for the emergency CR/TSC filtering including the testing of R15701 and R15702 was completed in June 1985 and the system was declared operable upon completion of the 1985 refueling outage.
Surveillance Procedures (SP) 211.01B and SP 211.01E, "CR/TSC Emergency Filtering Refueling Interval Surveillance Test" were prepared and issued in May 1985.
At that time, the need for a calibration procedure to support the SP was identified, but the procedure was not written.
AP.4 4, " Turnover and Release of Engineering Change Notice (ECN) Work Package" does not procedurally ensure that, upon system turnover to operations, all appropriate plant procedures are written and training is complete.
3)
Corrective actions which have been taken and results achieved.
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The calibration procedure for radiation monitors R15701 and R15702 is being developed and is scheduled for completion by February 6, 1987.
The CR/TSC filtering system has been inoperable since June 1986 due to design modifications.
Therefore, Technical Specification 4.10.1.B which requires surveillance on the CR/TSC filtering system including the radiation monitors, has been delayed until the system modifications are complete, i.e.,
prior to restart.
4)
Corrective steps which will be taken to avoid further violations.
The Technical Specification 4.10.1.B required surveillance on the CR/TSC filtering system including the radiation monitors will be completed prior to restart.
2
a Procedure AP.<44 is being revised to programmatically control system turnover to ensure that all plant procedures are written and approved and that required training is completed.
This procedure revision is scheduled to be complete by February 10, 1986 and will be in place to ensure that procedures and training are completed on modification work.
This includes work performed during the present extended outage.
5)
Date full compliance will be achieved.
The calibration procedure will be completed by February 6,
1987.
All additional corrective action will be completed prior to restart.
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