ML18082A859
| ML18082A859 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/21/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18082A855 | List: |
| References | |
| 50-272-80-06, 50-272-80-6, NUDOCS 8008130227 | |
| Download: ML18082A859 (3) | |
Text
.. APPENDIX A NOTICE. OF 'VIOLATION Public Service Electric and Gas Company Docket No. 50-272 Based on the results of an NRC inspection conducted on March 30 through April 30, 1980, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Faci 1 ity License No. DPR-70, as indicated below.
Items A through D are categorized as Infractions.
Item E is a Deficiency.
A.
Technical Specification 6.8.1 states in part: "Written procedures shall be established, implemented and maintained covering... the appltcable procedures recommended in Appendix A of Regulatory Guide 1.33, November 1972!' Regulatory Guide 1.33 included Paragraphs A.3 Equipment Control (e.g. Locking and Tagging), A8 Log Entries and AlO Bypass of Safety Function.
The implementing procedure, Operations Directives Manual Revision 5, states, in Section 2.4.5, 11 *** When a new valve lineup is perfonned, the operator is to position all valves as specified by the valve lineup and initial the appro-priate space... The completed valve lineup will then be used to record valve deviations resulting from tagging or valve manipula-tions for special plant conditions..* When a valve lineup is de-viated from due to tagging or special plant conditions, the on duty control operator.will note in the 11C&T For or Out Of Position Column" the reason..*
11 Section 3.1.5 of the Operations Directives Manual*states, "Operations Log No. 1 - Control Room Daily Log...
- 2) Entries to the narrative portion shall include but not be limited to:... j) Implementation and termination of Technical Specification Action Statements...
11 Contrary to the above, on April 11, 1980, manual isolation valve 14 AF 10 was found to be shut with the locking device locked. This valve is required by operating procedures to be locked open in order to provide auxiliary feedwater flow from the steam-driven auxiliary feedwater pump to #14 steam generator.
No deviation in the valve lineup lists was noted, nor any indication provided in the log that the provisions of Technical Specification Action Statement 3.7.1.2 were in effect.
No administrative control was identified which would have restored this flow-path.* to operable status within the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> required by the Technical Specifications.
B.
Facility Operating License DPR-70 states in paragraph C (1), "Public Service Electric and Gas Company is authorized to operate the facility at a steady state reactor core power level not in excess of 3338 megawatts (one hundred percent of rated core power).
11
Contrary to the above, on April 18, 1980 while operating in steady state, core average nuclear instrument power was recorded in excess of 100% for a period of approximately two and one half hours.
Near the end of this interval a calorimetric heat balance indicated nuclear instrument power (averaged) as 100.6% and calculated power as 100.24%.
An additional one hour period was identified on April 21, 1980 during which steady state operation was conducted in excess of 100% as indicated by the average nuclear instrument recorder.
C.
Technical Specification 4.1.3.1.1 requires that the position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions as least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Technical Specification 4.0.2 extends the above interval by 25% to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Contrary to the above, during the below listed 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> intervals, no record could be identified to demonstrate that the above determination had been made:
--February 2, 1980 1600 to 2400
--February 3, 1980 0000 to 0800
--February 16' 1980 0000 to 0800
--February 16' 1980 2000 to 0400 (2/17)
--March 8, 1980 1600 to 2400
--April 9, 1980 0800 to 1600
--April 10, 1980 1600 to 2400 D.
Title 10 Code of Federal Regulations, Part 50, Appendix B, Criterion XII, Control of Measuring and Test Equipment states:
11Measures shall b~ established to assure that tools, gages, instruments, and other measuring and testing devices used in activities affecting quality are properly controlled, calibrated, and adjusted at specified periods to maintain accuracy within necessary limits.
11 Relative to the feedwater flow instruments, which are used in daily calorimetric power calculations and for setting excore nuclear instruments, as required by Technical Specification 4.3.1.1.1, the above requirement is implemented in part by the following licensee procedures; Administrative Procedure 10 (Inspection Order System, Revision 3, dated 10/2/79) and Perfonnance Department Procedure PD-1.4.005 (Instrument Data Calibration Sheet Instruction, Revision 0).
Inspection Order #402309, issued under the requirements of Administrative Procedure 10, requires a monthly calibration of Rose-mount feedwater flow indicators and Fairchild digital indicators.
Procedure PD-1.4.005 further requires that all blanks on the Instru-men~ Data Calibration Sheet be filled in or marked as not applicable.
Contrary to the above, the fo 11 owing determi nati ans were made re 1 ati ve to the feedwater flow instruments and indicators:
- a.
The feedwater flow measuring and indicating devices were overdue for monthly calibration during the period 12 March 1980 through 16 April 1980 while the plant was operating at power.
When calibrated on April 17, 1980 adjustments were necessary to restore the instruments to the required accuracy recorded on the instrument data card.
- b.
No record of calibration of these indicators within one month of return to power operation in December 1979 was identified. Calibration was not perfonned until February 4, 1980, at which time readjustment was required to restore required accuracy.
- c.
No procedural guidance to maintain required accuracy during calibration intervals was identified.
- d.
Infonnation was missing and no applicability specified on the instrument data cards for feedwater flow instruments.
This included the following; specification sheet number, interconnecting W.D. number, functional diagram number, annunciator number, head correction, instrument serial numbers at each calibration.
E.
Technical Specification 4.2.4 requires that the Quadrant Power Tilt Ratio shall be determined to be within the limit above *503 of Rated Thermal Power by calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the alarm is ino~erable.
Contrary to the above, during the period April 12-13~ 1980, while operating above 50% Rated Thermal Power with the deviation alarm inoperable, quadrant power tilt ratios were computed at 1131 on 4/12 and 0346 on 4/13, an interval exceeding 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> plus the 25%
allowed by Technical Specification 4.0.2.
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