IR 05000213/1980008
| ML19336A397 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/20/1980 |
| From: | Blumberg N, Chung J, Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19336A392 | List: |
| References | |
| 50-213-80-08, 50-213-80-8, NUDOCS 8010220707 | |
| Download: ML19336A397 (19) | |
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- U.S. NUCLEAR REGULATORY COMMISSION
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2 0FFICE'0F INSPECTION AND ENFORCEMENT.
h Region I'
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Report No. :50-213/80-08L
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- Docket No.
50-213.
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Category C
F Licente No..
DPR-61 Priority
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Licensee:'
Co'nnecticut-Yankee Atomic Power Company P. 0. Box 270 Hartford', Connecticut 06101
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hadda g ack Plant g
Facility Name:
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Inspection at:
Hactam Neck, Connecticut Inspection con uctedi Ap 1 21-25,.1980-Inspectors:
b,[ M 542 /.--.
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'._Chu'ng, cto Inspector date signed
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erg 71 tea r pspector date signed
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date signed 4-40-86 j
Approved by:
h E. G. Greenman, Chief,-Nuclear Support date signed 1-Section No. 2,-RO&NS Branch-
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Inspection Summary:-
InspectioW on ' April 21-25,1980 (Report No. 50-213/80-08)
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Areas Inspected; Routine, unannounced inspection by..two regionally based ins'pectors-on previous. inspection findings; administrative controls for facility procedures; con-i formance to TechnicaljSpecifications;L emporary and permanent changes in conformance-t
.i H50.59(a); and (pecifications and licensee procedures; changes..in procedures to 10 CFR to Technical S
b) _ requirements; checklists -and related forms for. currency to latest L
l changes;(administrative controls forssafety-related maintenance; safety-related main-
tenance. activities; ~ maintenance personnel Lqualificat. ins, and control room' and faci--
- lity tours. The inspection involved 59 inspector-hours onsite by two-NRC regionally based inspectors.
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Results: : Of tthe -ten. areas : inspected,' no items of noncompliance were observed in fivez
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tareas and five items _of: noncompliance were identified in the remaining five-areas -
-(Deficiency -ifailure~ to properly approve l
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. meetings-withla'. quorum:(see paragraph 3.b) procedures and ~fai ure to conduct P RC
- . Infraction - failure to'establishiwritten
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procedures for' annunciators and-failure,to change ~ procedures to reflect annunciator
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modifications 5(see paragraph.4.'c(2));; Infraction
. failure to use procedures'-and to -
RegionLI Formil2-(
q(Rev.1AprilJ77)'
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~ perform post maintenance inspections and tests for safety-related maintenance (see-paragraph 10.c(1)); Deficiency failure 'to use latest revision of a procedure ~ and
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- failure to post procedure revisions (see~ paragraph 4.c(1) and 6.b)); and Deficiency -
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failure to maintain' records.of-maintenance activities (see paragraph 10.c(2)).
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~ DETAILS 1.
_P_ersons Contacted
- R. M. Blewett, Quality Assurance Supervisor N. A. Burnett, Operations Supervisor J. Chiarella, Instrument and Control Foreman ~
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- J. H. Ferguson, Station Service Superintendent S. T. Fleming, Training Supervisor R. L. Gracie, Operations Assistant Supervisor R. H. Graves, Station Superintendent W. Kadlec, Production Test Coordinator - NUSCO J. M. Levine, Engineering Supervisor E. Musil, Mechanical Maintenance Foreman
- J. B. Overbaugh, Electrical Maintenance Supervisor
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M. D. Quinn, Chemistry Supervisor M. T. Ronzo, Office Supervisor R. P. Traggio, Unit Superintendent The inspectors also interviewed other licensee emp'ayees during the inspection, l
i including Reactor Operators, Technical Support, Ac',nt'istrative and Clerical personnel.
denutes those present at the exit interview
Acting Plant Manager on exit interview 2.
Licensee Action on Previous-Inspection Findinas (Closed) Infraction (213/79-10-01):
Failure to perfonn the post maintenance and the surveillance tests of the high pressure fire pumps on a 31-day in-
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terval, and performance evaluation as required by Technical Specification.
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The inspector verified by reviewing surveillance test records (SUR 5.1-15)
l that the subsequent functional tests were performed on 31-day intervals, and the procedure was updated to reflect the requirements of TS 4.15.
I (Closed) Deficiency (213/79-10-02):
Failure to follow QA 1.2-11.2, Review
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of Test Data, and to implenent into a plant informaiion report (PIR).
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inspector verified by review of PIR records that the deficiency was identi-
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fied in the PIR and the documented corrective action was taken by the plant management.
(Closed) Unresolved Item (213/79-10-03):
Failure-to establish administrative i
controls-for the review of test data while maintaining a second independent level of review. The inspector confirmed, by review of QA 1.2-11.2, Opera-tional Surveillance Test, and QA audit records conducted on October 26, 1979, that_QA 1.2-11.1 was updated on March 17, 1980 to define the review pro-cedure clearly. maintaining the independent review proces.
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L i-(Closed) Unresolved. Item (213/79-08-03):
Resolve discrepancy between
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j administrative procedure which1 requires a' test equipment history use-log j
and actual practice which requires only recording of test instrument on the
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calibration; data sheet.
Procedure QA 1,2-12.1, " Control.of Measuring and i
Test Equipment" has been revised to require that test equipment calibration
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~ heets to be attached to the applicable work permit.
On a random basis, s
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i the inspector verified - that for test equipment calibrated in house, the
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L calibration sheet is attached to the work permit; and, for equipment sent
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out for calibration, the tes't equipment number is recorded on the calibration
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j data sheet of the instrument being calibrated which.is, in turn, attached
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to the wcrk permit.'. The' inspector also observed that although a history log:is not maintained. for the current method.of filing calibration data.-
j it is feasible to determine usage of a test instrument should it be found
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out of calibration.
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i (Closed) Unresolved Iten (213/78-07-05):
Procedures are required to be 1-established for-Charging Pump and Boric Acid Pump Surveillances.
The in-
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spector verified the following procedures have been established for the
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pump surveillances:
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SUR 5.1-104, Boric Acid Pump Weekly Functional Test, Revision 1,
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October 27. 1978 SUR 5.1-4, Hot Operational Test, Revision 8. February 21, 1980 (ac-
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j complishes charging pump tests)
j (Closed) Deficiency (213/78-07-03):
Instrument and Calibration Department
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not maintaining documentation for calibration of test gages. A licensee representative stated that test gages are calibrated before each use and calibration data is attached to the data record sheet.of the instrument
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which is calibrated by use of test gages.
On a random basis, the inspector 1-selected'several instrument calibration records, which required use of a j
. test gage, and verified: that test gage calibration data was attached j
to the calibration records.
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(Closed) Unresolved Item (213/78-07-01):
" Desired Output" values on cali-bration. data records did not correspond to those values given in associated procedures. The inspector verified that-the following procedures or their
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respective data sheets have been revised to provide consistent " Desire Output" values.
SUR 5.2-34, Boric Acid Storage Tank Level Calibration PIF Converter
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-(LM-118)
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JSUR 5.2-17, ' Boric Acid Control Calibration, Boric Acid Flow Recorder i
.SUR 5.2-17, Boric-. Acid Flow Integrator (F-I-112B) Calibration
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--- SUR 5.2-46, Calibration Safety-Related Instruments Not Specified_-In i
TechnicaliSpecifications (For: Demineralized Water Storage Tank Level Calibration, High Level.(LS'1307H) Alarm).
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(Closed) Unresolved Item (213/78-07-02):
Emergency Generator EG-2B, Load (KW) Meters to be recalibrated to correct apparent out of tolerance readings and Procedure PM 9.5-89, Testing Switchboard Panel Meters and Transducer Calibration, to be revised to more clearly define acceptance criteria.
The inspector observed recalibration data and verified that this data met procedural accuracy requirements.
However, procedure PM 9.5-89 had not been revised and accuracy calculations were being recorded in the " remarks" sections of the data sheet per verbal instructions of the supervisor.
Prior to the completion of the inspection, the inspector observed that PM 9.5-89 had been revised to specify the calculations required for meter accuracy, and to include a meter accuracy column on the data sheet.
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Facility Administrative Control Procedures The inspector reviewed, on a sampling-basis, the following administra-a.
tive procedures and the minutes of PORC meetings for conformance with Technical Specifications, Section 6, ANSI N18.7-1972, and Regulatory Guide 1.33.
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ADM 1.1-42, Periodic Procedure Review, Revision 3, May 12, 1977
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ADM 1.1-8, License Operator Acknowledgement of Changes to Facility
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Procedures and License Document Acknowledgement Sheet, Revision 5, October 25, 1979 QA 1.2-6.1, Document Distribution and Accountability, Revision 7,
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February 15, 1980 QA 1.2-6.4, Temporary Procedure Change, Revision 7 September 30,
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1979 QA 1.2-6.5, Procedure Review and Approval, Revision 5, May 11,
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1979 ODI #73, Control Room Schedule of Routine Activities, Tests and
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Checks, Revision 5, July 25, 1979 Minutes of Plant Operation Review Committee (PORC) Meetings,
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1979 through 1980 b.
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Technical Specifications and Station Administrative Procedure ADM 1.1-1, stated that a quorum of PORC meeting shall' consist of chairman and four members, two of which may be alternates.
The inspector confirmed by review of PORC minutes, that PORC meetings were conducted without the quorum in the following instances:
-February 28, 1980, PORC # 80-7
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. November 28, 1979, PORC #79-91
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February 13, 1979, PORC #79-18
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t A licensee representative stated'that a fourth member indeed attended the meeting on February 28,1980 (#EO-7) but his name was not recorded
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Similarly, the
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j guest attendee of the meeting held on November 28, 1979 was in fact an alternate as designated in ADM 1.1-14, Revision 8. June 22,1979, thus meeting the' required quorum.
Again, clerical errors were blamed
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for the discrepancies found in the minutes.
The licensee acknowledged
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initially that PORC meeting :(#79-18) on February 13.-1979 did not meet-
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the required quorum, and temporary procedure changes as well;as items
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' approved in.that meeting will be reviewed in a subsequent PORC meeting.
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The items approved in the meeting were:
l TPC #625 to NOP 2.4-5, " Draining An Isolation Loop"
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j-TPC #626 to SUR 5.3-24. " Dead Weight. Tested'PC-23C Loop"
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TPC #627 to SUR 5.1-47, "CCW to Neutron Shield Tank"
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i TPC #629 to SPL-10.5-30, " Testing of 0T-2 Switch"
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TPC '#630 to FP-CYW-R8,' " Refueling Procedure"
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TPC #631 to FP-CYW-R8, " Refueling Procedure"
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TPC #632'to FP-CYW-RS, " Refueling Procedure"
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TPC. #633 to M 8/5-11. " Boric Acid Filter"
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TPC #636 to SPL 10.5-155, " Welding and NDE Requirements...."
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Approval of Technical' Specification Change Request #79-2 and 79-3
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However, in subsequent telephone discussions, a licensee representative
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stated that the February 13, 1979 meeting also was attended by a fourth member, meeting the required quorum, and again clerical error
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was bla.ad without substantiating documentation.
Failure to maintain the minutes of PORC meetings properly and the PORC-quorum, and subsequent implementation of the procedures approved in
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the meeting are contrary to Technical Specifications 6.5.1.5 and 6.5.1.8 and ADM 1.1-1, and'is a deficiency level item of noncompliance a
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4.
Facility Procedures
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The inspector reviewed facility procedures and temporary procedure a.
changes, on a random basis to verify the following:
Procedures and changes, if any, were reviewed and approved in
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accordance with the requirements of the Technical Specifications
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and the licensee's administrative controls
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The overall procedure format and content were in conformance with-
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the requirements of the Technical Specifications and-ANSI N18.7-
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1479 " Administrative. Controls for Nuclear Power Plants"
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. _ ace and Operability Criteria were in conformance with the
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- requirements 'of ~ the Technical specifications
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Procedt.res, checklists and related forms in Plant Working Files are current with respect to revision and change in conformance with the requirements of the Technical Specifications Appropriate Technical Specification limitations had been included
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in the procedure The applicable checklists were compatible with step-wise instruc-
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tions in the procedures Temporary changes were made in conformance with Technical Speciff-
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cation requirements and the licensee's administrative controls b.
The following procedures were randomly selected and reviewed:
(1) General Operating Procedures
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N0P 2.1-3, Operation at Hot Standby - Reactor Critical, Revision 2, April 6, 1978
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NOP 2.7-5, Purification of Refueling. Cavity Water, Revision 1, April 17,1980
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N0P 2.9-3, Refueling Cavity Filling and Dewatering, Revision 2, May 18, 1978
- Procedures reviewed for technical adequacy (2) System Operating Procedures
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NOP 2.7-1, Processing Letdown Liquid, Revision 2, April 17, 1980
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NOP 2.13-1, Reactor Containment Atmosphere Control System Air Recirculation, Revision 1, June 16,1977
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N0P 2.13-2, Reactor Containment Internal Filtration and l
Purging, Revision 3, May 27, 1977 N0P 2.18-1, Startup - Filling and Venting Feedwater System,
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Original, February 14, 1975 NOP 2.7-6, Purification of Volume Control Tank, Original,
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January 1,1976
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- NOP 2.12-1, Core Cooling System Lineup for Shutdown and Air
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Power Operation, Pevision 9, September 28, 1979
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NOP 2.23-3, Demineralizer' Regeneration.- Manual, Revision 2, March 7, 1978'
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N0P 2.16-2, Generator Phasing and Unloading, Revision 2,
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October 27, 1978 NOP 2.2-2, Steady State Operation and Surveillance, Revision
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8, March 28, 1980
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N0P 2.14-13, Waste Evaporator Bottom Drumming, Revision 6,
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April 6, 1978 (3) Off-Normal Procedures
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E0P 3.1-34, Complete Loss of Control Air Supply, Original, February 1,1975 E0P 3.1-35, High Air Activity Level in SIB Exhaust, Original,
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February 1,1975
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E0P 3.1-9, Total Loss of AC, Revision 6, January 31, 1980 E0P 3.1-5, Steam Generator Tube Failure, Revision 4, September
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13, 1979 E0P 3.1-12, Emergency Boration, Original, February 1,1975
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E0P 3.1-31, Loss of A Vital or Semi-Vital Bus, Revision 1,
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September 2, 1975
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E0P 3.1-8, Loss of Condenser Vacuum, Revision 2, April 10, 1980 E0P 3.1-19, Automatic Makeup System Fb1 function, Original,
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February 1,1975 (4)
Emergency Procedures
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E0P 3.1-4, Loss of Coolant, Revision 11 January 18, 1980 E0P 3.1-14, Rod Drop at Power, Original, February 1,1975
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EP 1.5-12, Emergency Procedure for High Levels of Radio-activity in Containment, Revision 2, January 1,1980 EP 1.5-15, Emergency Procedure for Fuel-Storage Area, Revision
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1, January 1,1980, (5)~ Annunciator Response Procedures
' ANN 4.1-32, Letdown Waste Disposal _ - High Temperature, Ori-
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l ginal, February 1,1975.
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9-ANN 4.2-91, Waste Evaporator Level Hi-Hi, Original, February
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14, 1975 ANN 4.4-2, Dropped Rod - Rod Stop, Original, October 1, 1975
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ANN 4.4-11, NIS Power Range Channel Deviation Alarm, Original,
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October 3, 1975
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ANN 4.4-13, Containment Evacuation Alarm, Revision 1, December 8, 1975 ANN 4.4-15, Radiation Monitoring Channel High Activity,
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Original, October 1, 1975 ANN 4.5-2, Volume Control Tank Lo-Lo Level, Revision 1,
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. December 8, 1975
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- ANN 4.5-5, Refueling Water Storage Tank Hi-Lo Level, Original, October 3, 1975 ANN 4.8-2, Low Vacuum Alarm, Original, October 3, 1975
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' ANN 4.9-10, Vital Bus Inverter Off, Original, October 3,
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Findings (1)
Surveillance Procedure of Fire Protection System Tests, SUR 5.1-15, was revised to reflect the acceptance requirements of Technical Specifications and the consequent' performance evaluation of fire pumps, which is effective as of August-21,1979.
Yet, the subse-quent test records showed that the tests were conducted with the
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superseded procedure (Revision 4, October 6,- 1978) on August 23,
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August 31, September 11 and September 13 of 1979.
Also, the inspector confirmed, by a selected review of procedures in.the control room file and the library, that several outdated procedures were not replaced with the revised ones. The following are a few samnles:
Revision In Revision In
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Procedure Effect
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NOP 2.7-5, Original Revision 1-
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N0P 2.12-1, Revision 9 Revision 10
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Revision 7 Revision 8
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Failure to use the latest procedure revision while performing a test; failure to incorporate latest revisions to procedure; and failure to remove and discard a superseded procedure from con-trolled files is contrary to Technical Specification 6.8.1; ANSI N18.7, paragraph 5.1; and procedure OA 1.2-6.1, paragraph 7.1 constitute a deficiency level item of noncompliance (213/80-08-02).
(2) The inspector examined the Main Control Annunciator Board (MCB),
on a random sampling basis, to verify that the changes were accurately reflected in the appropriate corresponding procedure.
The inspector identified that the following examples of annunci-ator additions / changes were not reflected in the appropriate procedures and that the plant had been operating in the interim.
An " Axial Offset, Plus-Minus Alarm" was installed on MCB
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B-1-3-4 but the corresponding procedure had not been established The "High Volts Per Hz Alarm" was replaced and unit annunciators
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EG-2A and EG-28 were moved from MCB G-1-1-6 to a new 345 KV switching board. However, an appropriate procedure was not established for the first alarm and annunciator response pro-cedures. ANN 4.9-1 and 4.9-2 did not reflect the changes to the latter two annunciators There was no procedure established for the "Steamline Trip
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Valve Air Reservoir Low Pressure Alam" The inspector determined that the above examples were only a few l
. instances where procedures were not established for new annunciators or established procedures did not reflect changes to correspond'.ng annunciator alarms. With respect to the 'first example, a licensee representative stated that a written procedure would be established prior to restart from this scheduled refueling outage.
Further, the licensee representative stated that procedures associated with alarms that have undergone changes / modifications will be reviewed to assure that the response procedures reflect the current status and requirements of the alam.
The failure to establish appropriate alarm response procedures, as described above,-is contrary to Tech-nical Specifications 6.8; Regulatory Guide 1.33-1972, Appendix A, Paragraph E; and, ANSI N18.7-1972, Paragraph 5.3.3.
The foregoing constitutes an infraction level item of noncompliance (213/80-08-03).
(3) The inspector confirmed, by review of three on-site controlled copies of Technical Specifications, that substantial parts of Technical Specifications were changed administratively without
'the Commission approval.
For instance, the following is a part of changes used as per memorandum dated November 2,1979 (EN-M0-1793) and subsequent PORC approved:
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4.3 Core' Cooling System Periodic Testing
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3 liter /HR in. paragraphs 4.4 and 3.14. of Technical Specifications.
Contrc! Copy.#107 (Control-Room) and only paragraph 3.14 of the control room copies #133 (Operation Supervisor) and #133 (QA supervisor) was changed contradicting the changes in #107.
The use of unapproved' administrative-Technical Epecifications,
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although providing more conservatiw requirements,. requires.
further review and clarification.
This item is unresolved pending i-further NRC review during a subsequent NRC:RI inspection (213/80 -
08-04).
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(4) While reviewing the operating procedures, the inspector raised the safety. concern on prevailing. conditions of radiation limits
for the ion exchanger and the demineralizer services.
The opera-
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ting procedures N0P_2.7-5 and 2.7-1 were' revised to eliminate the radiation and DF limits for. resin replacement services, leaving
the decision to the-discretion of site chemists and/or health
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physicists. The inspector.was informed that in using the new
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procedures the ion exchanger and the demineralizer were taken
out-for services with contact radiation levels of 1000 R/hr, or
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greater as compared with 200-300 R/hr limits imposed in earlier procedures. A licensee representative stated that the procedure
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will be reviewed and a realistic limit will be implemented.
i This-. item will be reviewed during a s'ubsequent NRC:RI inspection.
5.
Technical Content of Facility Procedures
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The inspector reviewed facility procedures-on sampling basis, using facility
systems-' descriptions, diagrams and technical specifications, to verify that-procedures were sufficiently detailed and contained sufficient technical information.to control the operation or evolution as described in Technical
- SpecificationsL and the requirements.
The procedures reviewed with respect
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.to this~ are marked with an asterisk (*) in paragraph 4 (Facility Procedures)
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'One item of noncompliance was; identified and is detailed in paragraph 4.c.(2)..
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'6.
Procedure Changes 'Resulting From License Amendment-F, La..
The~1icense. amendments-(Nos. 31 and;32) issued during the past thirteen
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months, were reviewed to verify the applicable changes in Technical:
Specifications and associated procedures 'as necessary to reflect the
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amendments'.
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' Findings
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- Amendment 31,-dated March 26, 1979, addressed the replacement of eight feedwater hydraulic snubbers with mechanical-snubbers, which did not require ~. the normal surveillance of hydraulic snubbers.
The inspector verified that Technical ~ Specifications 3.19 and 4.13 were updated to
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reflect' the amendment, and the corresponding. Surveillance Procedure, SUR. 5.5-11, was revised in accordance with the changes.
However, the
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' superseded Surveillance Procedure, SUR 5.5-14, Feedwater Snubber Sur-
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veillance, was not discarded from the station procedure files until the inspector verified the existence of the invalid procedures. -Subsequently, a special PORC meeting was conducted on April 24,1980.to invalidate the procedure, SUR'5.5-14.
This is an example of an item of noncompliance which is detailed in para-graph 4.c.(1)above.
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Checklists and Related Forms Checklists, data sheets, acknowledgement forms, and other forms related to facility operating procedures were reviewed to.see that current revisions and on-the-spot changes were posted.
No items of noncompliance were identified.
.8.
Changes to Procedures Pursuant to 10 CFR 50.59(a) and (b)
Inspector verified, on a random sampling basis, that changes made to faci-lity prc,'dures 'during the past thirteen month period were in compliance with 10 CFR 50.59(a) requirements and that records of these changes were maintained-in compliance with 10'CFR 50.59(b)..
No items of noncompliance were identified.
9.
Administrative Controls for Safety-Related Maintenance Administrative controls,were reviewed to determine the licensee's program for implementin'g requirements associated with the conduct of. safety-related maintenance as specified in Technical Specification Section 6; Regulatory
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- Guide 1.33; Quality. Assurance Program Requirements; and ANSI N18.7,~ Administra-tive Controls' for Nuclear Power Plants.
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The following documents ~ were' reviewed:
u QA 1.2-2.4, Housekeeping Requirements, Revision 6, Septerter 13, 1979
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. A 1.2-5.1, Maintenance Work Requests and Work Permits, Revision,10, Q
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April. 7,- 1980
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QA 1,2-5.2, Procedure Format, Revision 3, September 13, 1979
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QA 1.2-6.1, Document Distribution and Accountability, Revision 7,
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February 15, 1980 QA 1.2-6.4, Temporary Procedure Change (TPC), Revision 7, September 13,
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1979 QA 1.2-6.5, Procedure Review and Approval, Revision 5, May 11,1979
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QA 1.2-7.1, Material Receipt and Inspection, Revision 6, January 25, 1980
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QA 1.2-8.1, Identification of Materials, Parts and Components, Revision
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4, November 28, 1979 QA 1.2-8.2, Material Issue, Revision 3, May 11,1979
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QA 1.2-8.3, Weld Material Control, Revision 4, January 25, 1980
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QA 1.2-10.1, Installation Inspections, Revision 5, January 25, 1980
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QA 1.2-11.3, Retest / Test Requirements, Revision 7, March 17,1980
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QA 1.2-15.1, Nonconformance Report, Revision 5, January 25, 1980
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ADM 1.1-32, Shutdown Worklists, Revision 1, May 17,1976.
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ADM 1.1-36, Miscellaneous Gas Cylinders in Plant, Revision 2, February
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7, 1980 ADM 1.1-35, Fire Hazards and Housekeeping Committee, Ravision 4, September
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29, 1979 ADM 1.1-37, Radiation Work Permit Completion and Flow Control, Revision
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8, February 7,1980 ADM 1.1-51, Inservice Inspection Program, Revision 1, February 21, 1980
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No items of noncompliance were identified.
10.
Review of Safety-Related Maintenance Activities a.
The inspector reviewed safety-related maintenance conducted by the licensee on a sampling basis to verify that:
Technical Specification Requirements were met while equipment
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was out of service, and a Licensee Event Report was submitted for maintenance associated with a reportable occurrence;
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Required administrative approvals were obtained to perform the
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-work; e
An. approved procedure was used where appropriate;
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Required inspections were performed;. and, L
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Records to substantiate quality of work and parts used were
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'available (this' includes documentation-associated with procure-ment, inspections and test results),
b.
Documentation of the following maintenance activities were reviewed:
Note:
"MA" designator is for mechanical and electrical work permits-and "IC" designator is for instrument and control work per-mi ts.
IC-0305,~ Replace Main Control Board Vibration Recorder, December
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8, 1979 IC-0358, Replace Drive Motor for No. 3 Steam Line Break Indicator,
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' January 21, 1980 MA-0389, Overhaul of "A" Charging Pump Motor, March 21, 1979.
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Procedure M 8.5-28, Maintenance of Charging Pump Motors MA-0390, Repack of Reactor Coolant Loop Stop Valves, March 12,
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1979.
Procedure M 8.5-19, Reactor Coolant Stop Valves.
.MA-0392, Replace No. 2 RCP.. Seal Water Supply Bypass Valve, March
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16, 1979
'IC-0409, Repair Nuclear Instrument System Hi Failure Light "B",
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March 20, 1980 MA-427, Repair Weld Leak on No.1 Feed Sensing Line, May 18, 1979
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MA-0430; Weld Repair Leak on.HP Turbine Gland Heating Steam Line,
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May 25,-1979'
MA-0444, Change Out Boric Acid Filter, June 11, 1979.
Procedure
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M 8.5-11, Replacement of Boric Acid Filter MA-0473, Install New Stack Monitor Flow Meter, June 25, 1979
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MA-0500, Replace' Fuel: Line to Repair Fire Pump Diesel Fuel Oil
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Leak, July 6, 1979
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L MA _0622,' Repair: Main ~ Control Board Annunciator, October 5,1979 -
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1MA-0647, Rebuild Pressurizer Code Safety Valve 584, October 8,
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1979.. Procedure.SUR:5.5-1,1 Test of Pressurizer Safety Valves -
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MA-0654,, Remove No. 2 RCP Motor, October 2,- 1979
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MA-0684,< Rod Drive ~ MG Sets Preventive Maintenance, _0ctobe'r 5,1979.
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Procedure 9.5-15,c Rod Drive Motor: Generator Sets -
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i MA-0709,_ Repair-Weld Pinhole Leak in "B" Component Cooling-Water -
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Heat Exchanger,-October 15,:1979
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. MA-0788,' Align "A" Auxiliary Feed Pump, December 4,1979. - Pro-
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cedure M-8.5-40' Maintenance. of Steam Generator Auxiliary Feed -
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Pumps
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. MA-0812, Repair Boric Acid Heat Trace,- February 23, 1980
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MA-0877, Repair Rod Centrol, Bank B, Group 8, Sluggish Step Counter,
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January 17,.1980. M 8.5-109, Removal and Repair of Facility Slow Cycle While Critical-
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MA-0899, Replaced Auxiliary Feed Pump Flow Control Valve MS-PICV-1206A,
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. January 28, 1980
L MA-0904,: Repair Pulse Generator In '115 KV Service 389SS KWH Meter,
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January 25, 1980
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l MA-0906, Rebuild Fire Pressure' Maintenance Pump, February -7,1980 p
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' MA-0908, Repack No. 3 S_ team Header Steam Flow Isolation' Valve,
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-February -7,1980-C MA-0909; Repair. Spent Fuel Building Crane Loose Pendent Cable,:
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January 29,:1980 i
MA-0926, Replace Diesel'~ Generator 2A Air Start Drain _ Valve, February-
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7,(1980 MA-0954, Connect Diesel Fire Pump Trouble _ Alarm to Main Control'
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Board Annunciator,: February.23,1980
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..MA-0978,- Replace; Valve _ Internals In "C" Control. Air: Isolation Valve,.
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- March 4',
1980
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--I JMA-0983, Replaced."B" Charging Pump Lube- 011 Pump, March 4,1980
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' MA-1006, Semiannual Testing of Heat land Smoke Detectors, April 12,
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-1980.- JProcedure SUR 5.5-13-C, Semiannual Heating-and Smoke _ Detectors
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c MA-1024, Replace. FaultyiTimer Motor,in "C": Control Air Compressor,
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EMarch 24, 1980)
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Findings (1) During the inspection, the inspector _ observed that several maintenance activities did not comply with the requirements of ANSI N18.7 in that certain safety-related maintenance was per-formed without use of a procedure and without performance of post maintenance functional testing.
In addition, various re-quirements of plant quality assurance procedures were not followed in that post maintenance installation inspections were not per-formed; quality assurance authorization was not obtained; and, in one instance, the material-control serial number was not recorded.
The following maintenance work permits did not comply with one or more of the above requirements:
Work Permit, MA-0899, Disassemble and Repair 1A Auxiliary
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Feed Pump Valve 1206-A Work Permit, MA-0926, Replaced Emergency Diesel Generator
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2A Air Start Drain Valve Work Permit, MA-0392, Replaced Reactor Coolant Pump Seal
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Bypass Valve
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Work Permit, MA-0444, Change Boric Acid Filter
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Work Permit, MA-0788, Realign "A" Auxiliary Feed Pump
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Work Permit, MA-0983, Replaced Charging Pump Main Lube Oil
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Pump Work Permit, MA-0674, Remove Feedwater Regulation Valve in
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order to facilitate system testing The following chart indicates which maintenance activitf did not comply with a specific requirement:
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Requirement ANSI N18.7 Para. 5.1.6 ANSI N18.7 Para.
QA 1,2-10.1 Para.
QA 1.2-5.1-
'QA 1,2-8:2 No Procedure 5.3.5(3) No 5.1 No Installation Para. 6.2.13 Para. 7.1 and Functional Test Inspection No QA Authori-7.2 No
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zation Material ID:-
No. Recorded Work' Permit Nunber MA-0899-X X
X j-MA-0926 X
X X
X
,
MA-0392 X
MA-0444 X
.MA-0788 X
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MA-0983 X-X X
,
MA-0674 X
X X
X
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In addition, the discrepancies noted above indicate that final QA review for Work Permits, to assure com-pleteness, is not adequate.
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Failure to implement procedures for safety-related maintenance; failure to perform post' maintenance functional tests; failure to perform post maintenance installation. inspections;; failure' to-(obtain QA authorization-on work permits; failure to record QA '
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' material identification serial nunber on'the Work, mit; and;
- failure to perform adequate final QA review of Mainmiance Work -
= Permits is contrary to -ANSI N18.7, paragraphs 5.'1.6 and 5.3.5(3);
'
QA 1.2-10.1, paragraph 5.1; QA' 1.2-5.1, paragraph 6.2.13; QA --1.2-5.1,. paragraph 6.2.23'and collectively constitutes' an infraction level = item of noncompliance (50-213/80-08-05).
.(2) The licensee Lwas unable to locate the complete work permits and
- i associated records ~of the following maintenance activities:
,
Work Permit MA-0380, Monthly Electrical PMs, performed
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' January 3,' 1979; Work Permit, MA-0450, Monthly Electrical PMs, performed
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June 1, 1979; and, L Work Permit, MA-0646,- No. 2 Reactor Coolant.(RCP) Seal Re-
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- p1acement, performed September 30, 1979 In addition, although records 'of' Work Permit _ MA-0647, Repair of ~
Pressurizer Code Safety Valve 524, were available,, the safety-valve ' set pressure _ data as required by procedure SUR 5.5-1,." Testing of Pressurizer Valves", Attachment No. :1,.was not maintained with the Work Permit records and could nct be -located.
There was. a sign-off in the procedure indicating 'setpoint Ltesting had=been satisfactorily completed.
Subsequent to 'the inspection, the licensee stated that some docu-
- mentation.concerning the. RCP seal replacement was located; however, theLwork permit still co'uld not be located.
' Failure to maintain Jrecords of maintenance activities and. associated
. data :is contrary to.-Technical Specification 6.10.1 and procedure
'QA 1.2-5.1' paragraphs ~ 6.2.22, 6.2.-25'and 6.2.26 and is considered a deficiency level-item of-noncompliance (50-213/80-08-06).
L(3) Procedure No.: SUR 5.5-1,:" Testing of Pressurizer Safety Valve",
provides a-disassembly and repair procedure in the ~ event the valve indicates: excessive seat leakage'during the' test.. ~The inspector
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observed that the' procedure = does not retest' the safety valve setpoint
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- subsequent to the repair and. queried the licensee about this. ' A licensee 1 representative statedL the valve is.not set' pressure tested Lagain in ordercto prevent rescoring of. the seat.
During the-in-
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Lspection,1the valve' manufacturer was contacted and: stated that:it was
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possible.to repair.the valve without.significantly affecting the
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.setpoint. :The inspector had no further questions.
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L(4) !I' response ~ to a Northeast Utilities Services Company (NUSCO)_
n audit, the. licensee QA Department is ;in the' process. of updating
~ the Category I systems and components listing.
The licensee =has stated in their reply dated February 6,1980 to Audit Q80-017
' that the new listing will be_ issued subsequent to the 1980 re-fueling outage.
The inspector reviewed.the. Category I listing during the inspection and it appeared to be -in the need of up-dating. This item will-be reviewed during~ a subsequent NRC:RI inspection.
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11. Maintenance Personnel Qualifications The inspector reviewed the qualification records of elected technicians and craft personnel who performed maintenance on safety-related systems' and components.to certfy that the individual's experience level and training
.were in accordance with the guidelines of ANSI N18.1-1971, Selection and
,
Training lof Nuclear Power Plant Personnel, Section 4.
I No items of noncompliance were identified.
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12.
Control Room Observations and Facility Tours The inspector ob_ served. Control Room Operations for control room manning,_
shift turnover and log sheets, and facility operation in accordance with the Administrative procedures and. Technical Specification requirements.
Inspection tours of turbine / generator. building and selected protected ~ areas were conducted, and no items of noncompliance-were identified.
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13.
Unresolved. Items
Unresolved items are matters about which more information is required to clarify whether they are acceptable, or items of noncompliance, or deviations.
One-unresolved item was identified'and detailed in 4.c(3).
14.-
Entrance and Exit Interviews Licensee management was informed of the. purpose and scope of the inspection at the entrance interview, and the findings of the inspection were' periodically
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discussed with the. licensee representatives ~as summarized in the following:
Date Reportable Details Covered April' 21,1980
. Entrance Interview
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-April 22,_1980-2 and 6.b
' April 23,'1980 10.c(1),3.b,-4.c(1),4.c(2),4.c(3)
Apri1J24,-1980 10.c(1),210.c(4),4.c(1),4.c(2),4.c(3)
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April 25,l19801 10.c(2),4.c(1), Exit; w ' Th'e inspector con' ducted an ' exit interview-with licensee representatives -
-(denoted in. paragraph li at the; conclusion of the inspection, where the findings of the' inspection.were presented and acknowledged by the licensee.
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