ML19344E778
| ML19344E778 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/09/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19344E762 | List: |
| References | |
| 50-333-80-05, 50-333-80-5, NUDOCS 8009110303 | |
| Download: ML19344E778 (3) | |
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APPENDIX A NOTICE OF VIOLATION Power Authority of the State of New York Docket No. 50-333 Based on the results of an NRC inspection conducted April 7 through April 11, 1980, it appears that certain of your activities were not conducted in full compliance with conditions of your NRC Facility License No. DPR-59 as indicated below.
Item A is an infraction and items B and C are deficiencies.
A.
Technical Specification 6.8(A) states in part, " Written Procedures and administrative policies shall be established, implemented and maintati.ad that meet or exceed the requirements and recomendations of Section 5
" Facility Administrative Policies and Procedures" of ANSI N18.7-1972..."
ANSI N18.7-1972 paragraph 5.3.6 states in part, " Procedures shall be pro-vided for periodic calibration and testing of safety. related plant instru-mentation..."
Contrary to the above, it appears that your program for establishment and implementation of calibration procedures has not been adequately imple-mented in that:
The procedure established for calibration of Reactor Core Isolation Cooling System instrumentation, F-IMP-13.3, "RCIC Flow Indication",
was not followed for calibration of RCIC flow indication instrumenta-tion; and further this procedure is inadequate in that during a review of 1977 and 1978 data the following was observed:
(.1) Applied input pressures to flow transmitter 13-FT-58 on the data sheets do not correspond to that established by the procedure.
In addition,'the input pressures between data sheets did not correspond.
(2) The procedure establishes a calibration for RCIC pump discharge flow switch, 13-F3-57; however, no data was available to docu-ment that this switch had ever been celibrated.
(35 1977 and 1978 data sheets show a calibration for flow indicator, 13F1-91-1; however, there is no calibration procedure established for this instrument.
The procedure established for calibration of Jet Pump Flow, F-IMP-2-3.1,
" Reactor Vessel Instrumentation - Jet Pump Flow Loop", was not followed for calibration of jet pump flow instrumentation and further this procedure is inadequate in that during a review of 1977 and 1978 data 8009 1103o3
2 it was observed that applied input pressure and expected output current for flow transmitter, 02-3-FT-64 and square rooter, 02-3-SQRT-74, were different than that established by the procedure.
The Control Rod Drive accumulator pressure and level alanns are neither functionally tested nor calibrated; nor, is there any procedure esta-blished for testing these alarms.
No procedures have been established for the calibration of the contain-ment leak rate monitor or for the calibration of Standby Liquid Con-trol System pressure indicator,11-PI-53, which is used to verify the testing of Standby Liquid Control System relief valve testing. How-ever, in each instance, it was observed that these instruments are being calibrated.
B.
Technical Specification 6.8(A) states in part, " Written procedures and administrative policies shall be established, implemented, and maintained..."
Procedure No. 4.1, " Procedure for Department Surveillance Tests", paragraph 7.0 states in part:
"As a minimum each surveillance test shall include...
sign-off notification insuring department review and evaluations of the test results".
Procedure No. 1.4, " Control of Plant Procedures", paragraph 7.3 states in part, " Revisions to procedures shall receive the same review and appro-val as the original... Revisions will also include a completed approval cover sheet listing the effective pages and revisions".
Procedure No. 4.2, " Control of Measuring and Test Equipment", paragraph 6.4 states in part:
"Each test and measuring instrument...shall have some form of a log... showing when and where...the instrument...was used and the initials of the user".
Contrary to the above, it was observed that:
Supervisory review of completed data for F-ISP-85, " Control Room Ven-4 tilation Temperature and Differential Pressure Instrument Calibration",
was inadequate in that two of five data points for two control tem-perature instruments, TIC-105 and TIC-107, were out of tolerance to the requirements of the procedure; but, test results were signed off as acceptable during supervisory review.
In addition, during perfor-mance of F-ST-6A, " Standby Liquid Control Pump Functional Test (ISI)",
the Standby Liquid Control Pump Flow was calculated as 50.88 gpm rather than 52.8 gpm as would be indicated by the data.
This error was not observed during supervisory review.
The miscalculated' data, although in error, was well above Technical Specification requirements.
Instrument surveillance procedure cover sheets do not list the effec-tive pages and latest revisions of sign-off and data sheets which are associated with and integral to each procedure.
3 Test gage No. 2003 which was used for F-ISP-46, " Main Steam Line High Flow Instrument Functional Test / Calibration" performed on March 28, 1980 was not entered in the Instrument and Control Department traceabil-ity log for that instrument; and digital thermometer No. 01 which was used for F-ISP-82-1, " Standby Liquid Control System Temperature Instrument Calibration" performed on October 12, 1979 was not entered on the Instrument and Control Department traceability log for that instrument.
C.
Technical specification 6.8(A) states in part:
" Written procedures and administrative policies shall be established, implemented and maintained..."
Procedure 1.4, " Control of Plant Procedures", Paragraph' 7.2.4 states in part:
" Procedures concerned with nuclear... safety shall be reviewed at approximately two year intervals (not to exceed 21/2 years) by the depart-ment superintendent or designee.
Review of procedures which have been revised within the two year period may be deferred and the review accom-plished approximately two years after the last revision..."
Contrary to the above, one hundred and thirty-one of one hundred and sixty instrument and control maintenance procedures have not been reviewed or revised within the last twc and one half years.
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