IR 05000277/1981029
| ML20041A197 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/26/1982 |
| From: | Blumberg N, Caphton D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20041A194 | List: |
| References | |
| 50-277-81-29, 50-278-81-33, NUDOCS 8202190256 | |
| Download: ML20041A197 (6) | |
Text
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' _,.} U.S. NUCLEAR REGULATORY COMMISSION _I -
.-, a 0FFICE OF INS,PECTION'AND ENFORCEMENT -- ,I Region 1 2 -
' _ 50-277/81-29 '~ L ' ' . . , s Report No.
50-278/81-33 50-277 - , , Docket No.
50-278 m DPR-44 . .. License No.
DPR-56 Prior.ity -- ~ Category,, 'C, y C,
', - ! Licensee: Philadelphia Electric Company - - ' " . ' i ' 2301 Market Street - - - , Philadelphia, Pennsylvania 19101 - - . ' Facility Name: Peach Bottom Atomic Power Station, Units 2'and 3 ._ Inspection at: Delta, Pennsylvania . Inspection co ucted: December 21-24, 1981 - ? Inspectors: i,. //,ff 87 - U - N.J. BlumB#g, Reactof' Inspector . d6te signFd .. ' , , -
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- Approved by: 44, Of d 1 / / - D~.E. 'C'aphton', Chief, Management date ' signed , - Programs Section, Division of - - Engineering and Technical Inspection -
s Inspection Summary: Inspection on December 21-24,1981 (Combined Report Nos. 56-277/01-29-and 50-278/81-33): Routine unannounced inspection by one ' region-hased inspector ~ of licensee action on previous inspection findii.gs; administrative controls of surveillance tests and calibraticns; and 'surveillar.ce test and calibration i program and implementation.
This inspection-involved 24 inspector hours on-
site by one region-based inspector.
' Results: No violations were identified.
' Region I Form 12 (Rev. April 77) ' 8202190256 820202 ' DR ADOCK 05000 _ _ _ _ _ _.
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Persons Contacted , > 7' . J. daw's.or - Instrument and Control (I&C) Engineer '
'~' R. Fleischmann II Assistant Station Superintendent
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. : : H. Gficher - Assistant Surveillance Test Coordinator A -_ K. Geetz Surveillance Test Coordinator i;, t w 's ' J.,Mitman f Results Engineer S.~ Spitco Quality Assurance Engineer - Site -* e ..
- J.~Wirenried Engineer - Technical
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USNRC. - , , ~ - - .-. 7' k R. Blough ~ Resident Inspector i q ' ~ ' ' C..Cowgill Senior Resident Inspector ' - .
, , . - ? JDenote.s those present 'at the exit interview.
?. Licensee Action on Previous Inspection Findings ._' ~ (Closed) Unresolved Item (277/78-20-02, 278/78-25-02): ' . DiffJculty in ach.ieving acceptable ISI test data during performance of tests' ST 6.8., "RHR "A" Pump, Valve, Flow and Unit Cooler Functional", and n , ~ ST _6110, "HPSW Pump and Valve Operability and Flow Rate Test"; and needed - licensee implementation of an acceptable ISI program.
The licensee ISI orogram was evaluated.and determined to be acceptable during combined ~ - ' jnspection 277/80-21 and 278/80-15. -During this inspection (277/81-29, 278/81-33), the inspector reviewed recent test data for ST 6.8 and 6.10 for - both Units 2 and 3 and observed that the data was within acceptable ranges as specified'in the procedures.
Based on the above, this item is closed.
3.
Adtr.inistr'ative Controls for Safety Related Calibrations and Surve111ances
Administrative controls governing performance of safety related calibrations ' and surveillances were inspected to determine conformance with requirements of 10 CFR 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants..."; Technical Specification Section 6, " Administrative Controls"; Regulatory Guide 1.33-1972, " Quality Assurance Program Requirements (Operation)" and ANSI N18.7, " Administrative Controls for the Operational Phase of Nuclear Power Plants". The following procedures were reviewed: Peach Bottom Atomic Power Station Quality Assurance Plan, Volume III, -- Operations Phase, Revision 4, January, 1980; Plant Procedure A-43, Surveillance Testing System, Revision 14, April -- 28, 1980; Plant Procedure A-47, Procedure for Generation of Surveillance Tests, -- Revision 2, April 28, 1980; and, ' _ - f" -- - _ _ _ - _ _ _... _ _ _ _ - _ _ - -. _. -. - - _ - -. - - - - -. - - -.. -
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-- ~ PECO Administrative Procedure, No. RT-12-50008, Control and Calibration of Pertable Test Equipment, Revision 0, June 16,1980.
No violstions were identified; however, one unresolved item was identified and is detailed in paragraph 4 below.
4.
Inspection of Program and Imp _lementation for Surveillance Tests, Calibrations, Calibration Checks, and Instrument Functional Tests: A sampling inspection was' conducted of the program and its imple-a.
mentation for surveillance tests, calibrations, calibration checks, and instrument functional tests required by the Technical Specifications and calibration of plant installed instrumentation which are used to verify satisfactory performance of Technical Specification Surveillance Tests or Inservice Tests. -The program and implementation was inspected for confor. nance to the requirements of the Technical Specifications, Regulatory Guide 1.33-1972, ANSI N18.7-1972, and the appropriate procedures detailed in paragraph 3.
The following areas were verified: -- A master schedule has been established for surveillance and calibration testing; Responsibilities have been assigned for performance of tests and -- to assure that test schedules are satisfied; Methods and responsibilities have been established for review and -- evaluation of data, for reporting deficiencies and failures, and for verification that LCO requirements have been satisfied; -- Applicable system status during component testing was in conformance with Technical Specification limiting condition for operations, ~ where applicable; -- Procedure format provided detailed stepwise instructions in the degree of detail necessary for performing the tests; -- Procedure review and approval were as required by Technical Specifications; -- The technical content of procedures was sufficient to result in satisfactory component tests and Technical Specification li_mits and setpoints were complied with; and -- Test data was adequately and accurately recorded and was within established tolerances.
b.
The following completed tests were reviewed: -- ST 13.21, " Emergency Cooling Water, Pump Emergency Cooling Tower Fans, and ESW Booster Pump Operability", Revision 6.
Data reviewed for test performed September 13, 1981;
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-- ST 8.1.1, " Diesel Fuel Quality Report", Revision 3.
Data reviewed for test performed November 30, 1981; ST 2.4.24, " Calibration of LIS-6530 A & B, CAD Liquid Nitrogen -- Tank Level Gages and Alarms", Revision 0.
Data reviewed for test performed July 23, 1981; ST 2.9.23A, " Calibration Check of Torus Narrow Range Level Loop -- "A", Revision 1.
Data reviewed for test performed August 25, 1981; -- S1 9.19, " CAD 0xygen and Hydrogen Analyzer (Calibration)", Rev-ision 5.
Data reviewed for tests performed on November 29, 1981; December 8, 1981; and December 17, 1981; ST 2.8.17, " Calibration Check of TI 3445 (Torus Temperature -- Indicator)", Revision 2.
Data reviewed for test performed on October 28, 1981.
ST 2.25.5, " Calibration of LT-2-11-45, LS-2-11-47, TS-2-11-50, -- PT-2-11-52, TS-2-11-59 A, B, C, 0, TS-2796 A, B, LS-2-11-70 (Standby Liquid Control System Pressure, Level and Temperature Indicators)", Revision 2.
Data reviewed for test performed June 9, 1980; ST 2.8.03, " Calibration Check of TE/TR 3501-5805 (Drywell Tempera- -- ture Indicator)", Revision 1.
Data reviewed for test performed October 27, 1981; -- ST 6.8 "RHR "A" Pump, Valve, and Unit Cooler Functional (Test)".
Data reviewed for tests performed November 22, 1981 and December 19, 1981; and, -- ST 6.10, "HPSW Pump and Valve Operability and Flow Rate Test".
Data reviewed for tests performed November 20, 1981 and December 18, 1981.
c.
Findings No violations were identified, however, the following unresolved item was identified: The plant installed instruments used to determine adequacy of sur/eil-lance and in-service testing are identified by the licensee as "NRC Commitment Instruments".
These instruments included all instruments for which a commitment to the NRC had been made to perform calibrations.
An individual calibration procedure had been established for each instrumen. ,
The ifcensee st'ated that procedure A-43, " Surveillance Testing System", provided overall administrative controls for these instruments.
The inspector observed the following concerning "NRC Commitment Instru-ments": Procedure A-43 did not refer to them; -- Susquehanna Test Group (STG) data sheets used in calibrations, -- were attached to the calibration procedures but were not considered part of the approved procedure. These data sheets were reviewed by the STG General Foreman but were removed prior to the I&C Engineer review; and, Test data was not always recorded in station surveillance tests.
' -- Based on the above observations and discussions with the licensee, the inspector determined that procedure A-43 needed revision in order to more adequately address "NRC Commitment Instruments". The licensee concurred with the inspector and stated that procedure A-43 would be revised or a new administrative procedure written which would define and/or address the following: (1) "NRC Commitment Instruments"; (2) Use of Susquehanna Test Group (STG) data sheets and their relation-ship to the surveillance test procedure; (3) STG General Foreman review of data and its method of documen-tation; (4) Assurance that essential data is recorded in the test procedure or provision is made for a mechanism by which STG data sheets or copies remain with the procedure; (5) Cognizant engineer review; and, (6) Assurance that new procedures conform to the administrative controls and that existing procedures be revised to conform during periodic reviews or subsequent revisions.
The licensee stated that' A-43 would be revised or a new procedure established by June 30, 1982.
This item is unresolved pending licensee action and subsequent NRC:RI review (277/81-29-01, 227/81-33-01).
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5.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable, deviations, or violations.
One unresolved item was identified during this inspection and is detailed.
in paragraph 4.c.
6.
Management Meetings Licensee Management was informed of the scope and purpose of the inspection at the entrance interview condacted on December 21, 1981. The findings of the inspection were periodically discussed with licensee representatives during the course of the inspection. An exit interview was conducted on December 24, 1981 (see paragraph I for attendees) at which time the findings of the inspection were presented.
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