IR 05000259/1981021
| ML18025B627 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/19/1981 |
| From: | Belisle G, Skinner P, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18025B624 | List: |
| References | |
| 50-259-81-21, 50-260-81-21, 50-264181-21, 50-296-81-21, 50296-81-21, NUDOCS 8109090349 | |
| Download: ML18025B627 (29) | |
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NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Repor t Nos. 50-259/81-21, 50-260/81-21 and 50-296/81-21 Licen see:
Tennessee Va1 1 ey Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name:
Browns Ferry 1, 2, and
Docket Nos. 50-259, 50-260 and 50-296 License Nos.
DPR-33, DPR-52 and DPR-68 Inspection at Browns Ferr 1, 2, and 3 near Decatur, Alabama Inspectors:
G. A. Belis e
Date Signed P.
H.
in er t
Approved by:
CD M.,Upright, Sectio Chief Engineering Inspection Branch Engineering and Technical Inspection Division ate Signed D te Signed SUMMARY Inspection on August 3-7, 1981 Areas Inspected This routine, unannounced inspection involved 57 inspector-hours onsite in the areas of licensee action on previous enforcement matters, organization and administration, design, design changes" and modifications, onsite review commit-tee, procedures, calibration, surveillance, test and measurement equipment program, non-routine reporting program, surveillance testing and calibration program, maintenance program,
'and licensee action on previously identified inspection findings.
Results Of the 12 areas inspected,.no violations or-,deviations were identified.
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8i0'F090349 810820 PDR ADOCK 05000259
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
"H. Abercrombie, Plant Superintendent
~R. Battles, Safety Engineering Aide
- P. Border, Nuclear Safety Review Staff
- R. Boyer, Public Information Officer
- T. Chenn, Compliance Staff Supervisor R. Cockrell, Reactor Engineering Unit Supervisor
~R. Cole, Power Quality Assurance
~J. Ferguson, Assistant Outage Director M. Harvey, Mechanical Maintenance Section Supervisor
- G. Jones, Fire Protection Engineering Aide
~T. Keckeisen, Fire Protection Engineer
~J. Norris, Quality Assurance R. Phifer, Safety Supervisor J
~ Pittman, Instrument Maintenance Section Supervisor
~W. Roberts, Jr., Safety Engineer J. Teague, Electrical Maintenance Section Supervisor
"R. Thompson, Supervisor, Fire Protection Engineering Other licensee employees contacted included technician and office personnel.
NRC Resident Inspector
- R. Sullivan, Senior NRC Resident Inspector
"Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on August 7, 1981 with those persons indicated
.in paragraph 1 above.
The licensee acknowledged the inspection findings.
3.
Licensee Action on Previous Enforcement Findings The following abbreviations are defined and used throughout this report.
Accepted QA Program TVA-TR75-1A, Quality Assurance Program Description for Design, Construction and Operations, Revision 4 ASME EMI American Society of Mechanical Engineers Electrical Maintenance Instruction
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IMI ISI LCO M8(TE MMI OQAM PORC QA QC SIL SCI SMI Instrument Maintenance Instruction Inservice Inspection Limiting Conditions for Operations Measurement and Test Equipment Mechanical Maintenance Instruction Operational Quality Assurance Manual Plant Operations Review Committee Quality Assurance Quality Control Section Instruction Letter Standard Calibration Instruction Standard Maintenance Instruction STEAR Special Tests, Experiments or Activities T/S TR Technical Speci ficati ons Trouble Report Violations from Inspection Report Nos.
50-259,260,296/81-02 were reviewed with respect to the licensee's letters dated April 17, May 8 and July 23, 1981.
a.
'Closed)
Violation A (296/81-02-01):
Failure to evaluate results of test.
The inspector reviewed a
memo from J.
E. Swindell to H. L. Abercrombie dated April 13, 1981, Subject:
Review and Evaluation of Reseat Pressure Results on MSRV S/N's 1019, 1020, 1023 and 1061.
This memo provides assurance that the MSRV reseat pressure anomolies were reviewed by the Stationary Equipment Group and also that MMI-107 was being revised.
The inspector also reviewed a
memo from T.
F. Ziegler to T.
G. Campbell ( 1740 CST2-C)
Subject:
Target Rock 2-Stage Valve Reseat Pressures
- Browns Ferry Nuclear Plant.
This memo provides additional information stating that although one or more valves presently now installed may not meet the recommended reseat criteria, this deviation is acceptable if the average for all valves in the unit is within limits.
The inspector reviewed MMI-107, TVA Test Procedure for Pilot Operated Safety Relief Valves Target Rock Model 7567F Units 1, 2 and 3, revised May 1, 198 % ~
(Open)
Violation B (259,260,296/81-02-04):
Failure to take prompt corrective action.
The inspector reviwed BF 16.5, Nonconforming Material, Components, and Spare Parts, dated February 2, 1981.
This finding (A-1 of Audit OPIA-BF-80-01) has been closed.
The inspector reviewed the 0(AM, Part III, Section 6. 1, Select,ion and Training of Personnel for Nuclear Power Plants, dated January 15, 1981.
The revision to DPM No.
N78A13 is in the process of being issued.
This procedure is expected to be issued September 1, 1981.
This item cannot be closed until this procedure is issued and reviewed by NRC.
(Closed)
Violation C
(259,260,296/81-02-03):
Failure to maintain training and retraining.
The inspector reviewed BF 4.5, Plant General Employee Training Program, dated August 8, 1981 and identified that the method of maintaining training records is now documented.
The inspec-tor reviwed a
memo from J.
B. Walker to J.
L. Harness, dated June 19, 1981 stating that two plant personnel had been retrained on April 14, 1981 as required.
(Closed) Violation D (259,260,296/81.-02-05):
Failure to submit
CFR 50.59 report.
The summary of special test and. experiments was sub-mitted to NRC February 19, 1981.
The inspector reviwed DPM N73015 Reporting of Nuclear Plant Operating and Plant Performance Information, dated June 25, 1981 and identified that positive controls had been established for the Annual Operating Report (for NRC).
The inspector also reviewed BF 15. 1, Implementation of Reporting -Requirements for Nuclear Plants dated September 9,
1980.
This procedure implements DPM N73015.
(Cl osed)
Viol ati on E
(259,260,296/81-02-02):
Fai lure to control drawings and failure to control vendor technical manuals.
The inspector reviewed the Information Management Manual,Section X,
Drawing Control and identified that positive controls have now been established on issuance of drawings from the Drawing Control Center.
A review of several drawings issued from the Drawing Control Center verified that drawings were being marked as required.
The inspector reviewed current controls being used for tracking con-trolled. documents and found them to be in accordance with BF 2. 1, Document Control Source and Plant Documents, dated March 25, 1981.
The inspector reviewed a
memo from J.
L.
Harness to File dated August 5, 1981 stating that all.vendor manuals have been purged from plant instructions.
The inspector reviewed a representative sample of MMI's, EMI's and IMI's and verified that none of the procedures reference vendor technical manuals.
The inspector noted that, the committed date for completion of this item was June 15, 1981. At that date a total of 5 procedures were still in process of being reviewed
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(one EMI and four MMI's).
No deviation is assigned this failure to meet the licensee's commitment date since these procedures were in the review process and they were the last of approximately 230 procedures that had been previously reviewed.
'f.
(Closed) Deviation A (259,260,296/81-02-06):
Failure to perform correc-tive action procedure change.
The procedural change to EN DES -
EP 203 was implemented January 8,
1981.
The inspector randomly selected plant modifications from the 1980 Annual Operating Report and deter-mined Unreviewed Safety Question Determinations (USQD) appeared to be adequate.
g.
(Closed)
Deviation B
(259,260, 269/81-02-07):
Failure to perform corrective action - conduct survey.
The inspector reviewed a memo from R. T. Smith to H.
L. Abercrombie dated Apri 1 16, 1981, Subject:
Review of Section Instruction Letters (SIL) on Trouble Reports (Reference Tracking Items 11598 and 12441) that documents and verifies that a
survey was performed on all plant group SIL's.
4.
Unresolved Items Unresolved items were not identified during th'is inspection.
t 5.
Organization and Administration (36700)
References:
(a)
Technical Specifications, Section 6, Administrative Controls.
(b)
TVA-TR75-1, Quality Assurance Program Description for Design, Construction, and Operation, Revision
(c)
OQAM, Part 1, Section 2. 1, TVA Organization for Quality Assurance, dated 1/81.
The inspector reviewed references (b)
and (c) to assure they met the requirements of reference (a) in the area of personnel qualification levels and lines of authority.
The licensee's current organizational structure was reviewed to assure that it met the requirements of reference (a).
Based on this review, one inspector followup item was identified.
Technical Specification 6. 1.C requires the functional organization for the operation of the station be as shown in Figure 6. 1-2.
Discussions with plant per-sonnel identified that recent organizational changes have occurred, conse-quently the current station organization varies from the T/S requirements.
Until the T/S is updated to reflect the current station organization this is identified as inspector followup item (259, 260, 296/81-21-01).
6.
Design, Design Changes and Modification (37700)
References:
(a)
OQAM, Part II, Section 3.2, Plant Modifications After Licensing, revised 7/80 (b)
BF 8. 1, Modification Status, dated 3/81 (c)
BF 8.2, Temporary Alterations, dated 2/81 (d)
BF 8.3, Plant Modifications and Work Plans, dated 4/81 (e)
BF 8.4, Authorization and Work Performance of Plant Modifications, dated 8/80 (f)
BF 8.5, Temporary Structures, dated 2/81 (g)
OQAN, Part I-I, Section 3.2, Core Component Design Change After Licensing, dated 10/80 (h) 'QAN, Part II, Section 5.3, Maintenance and Modification Inspection Program, revised 5/81 The inspector reviewed the references listed to assure they met the requirements of the accepted QA Program and Regulatory Guide 1.64 (Revision 2 - 1976)
as endorsed by that Program.
The inspection was to verify the following aspects of the design change program:
Modifications have been reviewed and approved in accordance with 10 CFR 50.59 Modifications were reviewed and approved in accordance with T/S and established QA/QC controls Modifications.are controlled by established procedures The licensee conducts reviews and evaluations of test results Operating procedures are updated and approved in accordance with T/S if required due to modifications Drawings were changed to reflect modifications Discussion with HRC Resident Inspectors identified that their inspec-tion activities routinely include monitoring of selected plant modifi-cations for the previously mentioned aspects, consequently the inspector performed no inspection activities (other than reference review)
in this area.
The resident inspectors document their inspection activities and findings in their monthly inspection reports'
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Based on this review, no violations or deviations were identified.
7.
Onsite Review Committee (40700)
References:
(a)
Technical Specifications, Section 6.2.B Plant Operations Review Committee (PORC)
(b)
Accepted QA Program, Section 17.2, Quality Assurance Program for Station Operation (c)
OQAM, Part I, Section 6.2, Plant Operations Review Committee Charter, revised 3/80 (d)
BF 1. 10, Plant Operations Review Committee, dated 5/80 The inspector reviewed references (b)-(d) to assure they met the require-ments of reference (a).
Discussions with the NRC Resident Inspectors on site 'identified their occasional attendance at PORC meetings, consequently the inspector did not attend PORC meetings during this inspection.
The inspector reviewed PORC meeting minutes from January July 1981 (Meeting Minutes Nos.
3979-4217)
and determined that the requirements of the refer-ences listed were being adhered to.
Based on this review, one inspector followup item was identified.
Reference (a) requires as a minimum the distribution of PORC minutes to the Director, Power Production; Chief, Nuclear Generation Branch and Chairman, NSRB.
Reference (c) contains a distribution list that does not include all of these members.
Until such time as reference (a)
and reference (c) distri-bution requirements are at least equal this item is identified as an inspector followup item (259,260,296/81-21-02).
8.
Procedures (42700)
References:
(a)
Technical Specifications (b)
Regulatory Guide 1.33, Quality Assurance Program Requirements (Operations),
Revision 2 dated 2/78 Discussions with NRC Resident Inspectors identified that their inspection activities routinely include monitoring of plant procedures associated with the daily operation of plant activities, consequently the inspector performed no inspection activities (other than reference review) in this area.
The resident, inspectors document their inspection activities in their monthly inspection reports.
Based on this review, no violations or deviations were identifie.
Calibration (56700)
References:
(a)
Technical Specifications (b)
OEM, Part 3, Section 3. 1, Control of Measuring and Test Equipment, revised 4/81 (c)
BF 13. 10 Format for Standard Calibration Instruction (Instrumentation),
dated 3/79 (d)
BF 17.9 Surveillance Requirements Program, dated 3/81 (e)
BF 17.5 Control of Measuring and Test Equipment, dated 5/81 (f)
OEM, Part 3, Section 3. 1, Control of Installed Techni-cal Specification Compliance Instrumentation, revised 11/80 (g)
BF IMSIL 10 Measuring and Test Equipment, dated 12/79 (h)
BF IMSI 12, Instrument Maintenance Program, dated 3/81 (i)
BF IMSIL 15, Instrument Maintenance Record System, dated 5/81 The inspector reviewed the references (b)-(i) to assure they met the requirements of the accepted gA Program and Regulatory Guide 1.33 (Revision 2-1978)
as endorsed by that Program.
The inspector reviewed the following aspects of the calibration program:
The frequency of calibration specified in T/S has been met for selected instrumentation That completed test documentation are reviewed for completeness, acceptance criteria are being met, approved procedures are being used and work is being done by qualified individuals That technical content of selected instrument calibration proce-dures are as required That procedures are reviewed and approved and contain controls to insure LCO conditions are met That satisfactory calibration will result and calibration will be to the required accuracy That "as found" and "as left" conditions will be recorded
That calibration equipment used will be traceable and return to service is controlled.
Discussion with NRC Resident Inspectors identified that their inspection activities routinely include monitoring of selected calibration activities for some of the previously mentioned aspects.
The resident inspectors document their inspection activities and findings in their monthly inspection reports.
The inspector selected 15 recently completed calibrations to verify previ-ously mentioned aspects had been completed.
The following calibrations were selected for review:
SURVEILLANCE INSTRUCTION 4.2.B-52 4.2.B-53 4.2;B-54 4.2.B-55 4.2.C.8*
4.2.F.15~
4.7.H 4.2.F.17 4.2.A.3~
4.2.B.8
- Contains Multiple Instrumentation DATE 4/13/81 2/9/81 5/13/81 5/29/81 5/29/81 2/17/81 2/20/81 2/18/81 12/22/81 5/18/81 5/16/81 5/15/81 5/13/81 6/9/81 The inspector also reviewed selected IMI's, SCI's and SMI's associated with the previously listed calibrations and verified the adequacy of procedures.
Based on this review, no violations or deviations were identified.
10.
Surveillance (61700)
References:
(a)
Technical Specifications (b)
BF 13.7, Format for Surveillance Instructions, dated 1/80 (c)
BF 17.9, Surveillance Requirements Program, dated 5/81 (d)
BF 21.4, Schedule System Technical Specifications, dated 1/79
(e)
BF 7.8, Implementation of ASME Section XI, dated 11/80 (f)
BF 7.4, Surveillance Testing, dated 4/81 (g)
OEM, Part II, Section 4.5, Plant Surveillance Test Program, dated 10/80 (h)
0(AM, Part II, Section 5. 1, Inservice Inspection Nuclear Power Plant Components, dated 2/81 (i)
ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Com-ponents 1974 thru Summer 1975 Addenda (j)
BF SI 3, Inservice Testing Required by ASME Section XI Units 1,2,3 dated 10/78 (k)
BF SI 3. 1, Inservice Pump Testing Required by ASME Section XI Units 1,2,3, dated 11/80 ( 1)
BF SI 3.2, Inservice Valve Testing Required by ASME Section XI Units 1,2,3, dated 6/81 (m)
BF SI 1, Surveillance Program Units 1,2,and 3; dated 11/80 (n)
BF SI 2, Instrument Checks and Observations Units 1,2, and 3 dated ll/79 (o)
BF IMSIL 5, Surveillance Testing, dated 8/79 The inspector reviewed references (b)-(h) and (j)-(o) to assure they met the requirements of the accepted QA Program and Regulatory Guide 1.33 (Revision 2-1978)
as endorsed by that Program.
The inspection was to verify the following aspects of the surveillance program:
That T/S related surveillance tests relating to various safety-related systems are covered by approved procedures That surveillance tests for systems identified by the licensee's inservice inspection ( ISI) program for pumps and valves are covered by approved procedures That procedures are prepared according to required format and include acceptance criteria and restoration to normal That technical content of procedures assures compliance with T/S/151 Program requirements
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That completed test are reviewed as required, performed within time frames required, are performed by qualified individuals and appropriate action was taken for items failing acceptance criteria.
Discussions with NRC Resident Inspectors identified that their inspection activities routinely include monitoring of selected surveillance activities for some of the previously mentioned aspects.
The resident inspectors document their inspection activities and findings in their monthly inspec-tion reports.
The inspector reviewed th'e licensee ISI Program for pumps and valves.
The inspector also reviewed complete test data for selected pumps and valves to verify conformance with the ISI Program.
The following are the test selected for review:
SURVEILLANCE INSTRUCTION DATE 3.1.3 3.1.4 3.1.2 4.5.B. l. C 4.5.C.1 4.5.C.2 Pump Al Pump A2 Pump B1 Pump B2 Pump Cl Pump C2 Pump D1 Pump D2 Pump A3 Pump B3 Pump C3 Pump 1A Pump 1C Pump 1B Pump 2A Pump 2C Pump 2B Pump 3A Pump 3C FCV-74-'66 FCV-74-75 FCV-74-72 FCV-74-25 FCV-74-35 FCV-74-36 FCV-67-48 FCV-67-49 23-588 23-591 23-594 23-597 5/16, 6/14/81
'6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 6/26, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 3/16/81 3/16/81 3/16/81 6/29, 7/27/81 6/29, 7/27/81 6/29, 7/27/81 6/8, 7/15/81 6/8, 7/15/81 7/1, 7/20/81 7/1', 7/20/81 7/1, 7/20/81 7/16/81 7/16/81 7/16/81 3/14, 6/14/81 3/14, 6/14/81 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81
4.5.C.3 4.5.C.1 23-580 23-581 23-582 FCV-67-14 FCV-67-18 FCV-67-22 FCV-67-25 6/14, 7/18/81 6/14, 7/18/81 6/14, 7/18/81 3/14, 6/14/81 3/14, 6/14/81 3/14, 6/14/81 3/14, 6/14/81 Based on this review, no violations or deviations were identified'1.
Test and Measurement Equipment Program (61724)
References:
(a)
BF 17.5, Control of Measuring and Test Equipment, dated 5/81 (b)
IMSIL 10, Measuring and Test Equipment, dated 12/79 (c)
TVA-TR75-1, Section 17.2. 12, Control of Measuring and Test Equipment, Revision 4 dated 9/80 The inspector reviewed the test and measurement equipment program in accord-ance with references (a) and (b) to ascertain whether the activities met the commitments of refernce (c).
The following criteria were used during this review:
Criteria and responsibility for assignment of the calibration/adjust-ment frequency have been established An equipment inventory list or equivalent has been prepared which identifies the following:
(1)
All test and measurement equipment which will be used for any reason on safety related structures, systems or components (2)
The calibration/adjustment frequency for each piece of equipment (3)
The calibration standard (national standard(s) if applicable) for each piece of equipment (4)
A calibration procedure to be used for each piece of equipment Formal requirements exist for marking the latest inspection/calibration date on each piece of equipment or otherwise identifying the status of calibration A system has been provided for assuring that each piece of equipment is calibrated and adjusted on or before the date required
A written requirement has been established which prohibits the use of test and measuring equipment which as not beeniinspected and calibrated within the prescribed frequency and describes controls to prevent inadvertent use of such equipment Out-of-calibration controls have been established which require the following:
(1)
when a piece of equipment is found to be out-of-calibration, the acceptability of items previously tested or measured will be evaluated and documented (2)
Evaluation of cause of out-of-calibration A formal system has been established to assure that new test and measurement equipment will be added to the inventory list and cali-brated prior. to being placed in service.
This review indicated that the bulk of M&TE calibration is performed by the TVA calibration facility in Chattanooga, Tennessee.
Some calibrations are performed at the site by the instrument and outage groups.
This calibration is limited primarily to pressure gages and torque wrenches.
t Based on this review, no violations or deviations were identified.
12.
Nonroutine Reporting Program (90714)
References:
(a)
BF 10.2, Licensee Reportable Event Determination, dated 2/81 (b)
BF 12. 14, Operation of Plant-Policy for Adherence to Plant Technical Specification Limiting Conditions for Operations and Reporting Significant Events to the NRC, dated 3/81 (c)
BF 15.2, Operational Event Report, dated 9/80 (d)
BF 16.2, Procurement, dated 5/81 The inspector review the licensee's program to ascertain whether responsi-
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bilitiess had been assigned for review and evaluation of offnormal operating events, planned and unplanned maintenance activities, surveillance testing and outage activities to assure conformance with regulatory requirements.
The inspector also reviewed the program to ascertain whether vendor bulle-tins and circulars are reviewed for applicability.
Based on this review, no violations or deviations were identifie c~
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13.
Surveillance Testing and Calibration Program (61725)
References:
(a)
Technical Specifications (b)
BF 17.8, Implementation of ASME Section XI, dated 11/80 (c)
BF 17.9, Surveillance Requirements Program, dated 5/81 (d)
SI-l, Surveillance Instructions, revision dated 4/81 The inspector reviewed administrative controls and procedures contained in reference (b)-(d) for surveillance testing to ascertain that the licensee
, has developed programs for control and evaluation of surveillance testing as required by reference (a).
The following criteria was used during this review:
Determine that formal methods and responsibilities have been defined for review and evaluation of surveillance test/calibration data including procedures for repor'ting deficiencies, fai lures, malfunc-tions, etc.,
identified during the tests/calibrations or inspections with required verificati'on that LCO requirements were satisfied Verify that responsibility has been assigned for assuring that required schedules for all tests and inspections are satisified Determine that calibration requirements have been established for components associated with safety related systems or functions but which are not specified in the technical specifications as requiring calibration Verify that responsibility has been assigned in writing to maintain the
"master calibration schedule" up-to-date Determine that formal requirements have been established for performing component calibrations in accordance with approved procedures which include acceptance criteria Verify that responsibility for assuring that required component cali-bration schedules are satisified.
Based on this review, no violations or deviations were identified.
14.
Maintenance Program (62702)
References:
(a)
Technical Specifications (b)
BF 2.3, Review and Approval of Instructions, dated 3/81 (c)
BF 2.10, Plant Records Management, dated 2/81
(d)
BF 6. 1, Performance of Maintenance, dated 3/81 (e)
BF 6.2, Special Processes and Non-destructive Examina-tion-Maintenance, dated 4/81 (f)
BF 13. 1, Format for Maintenance Instructions, dated 3/80 (g)
BF 13.4, Instructions and Guidelines, dated 1/80 (h)
IMSIL 3, Preparations of Instructions and Guidelines, dated 7/79 (i)
MMSIL 5, Performance of Maintenance, dated 4/81 (j)
PSIL 21. 1, Scheduled Routine Maintenance Program, dated 3/81 (k)
Information Management Manuel, Document Distribution, Source and Plant Document,Section IV, dated 3/81 The inspector reviewed the maintenance program in accordance with references (b) through ( k) to ascertain whether the activities met the commitments of reference (a) and the accepted gA Program.
The following criteria were used during this review:
A written preventive maintenance program for safety related structures, systems and components has been established Administrative controls for special processes have been established Methods and responsibilities for equipment control have been clearly defined A corrective maintenance program has been established that include written procedures, responsibilities for review and approval of work requests, inspection of work, hold point implementation, and admin-istrative controls.
Based on this, review, no violations or deviations were identified.
15.
Licensee Action on Previously Identified Inspection Findings (9270)
a
(Closed)
Open Item (259,260,296/81-02-09):
Lack of procedure to handle Outage Section TRs.
The inspector reviewed OSIL 59, Handling of Trouble Reports, dated 3/81, which gives detailed instructions on handling of TR's by the Outage Grou \\)
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b.
(Closed)
Open Item (259,260,296/81-02-10):
Document receipt acknowl-edgement.
The inspector reviewed BF 2. 1, Document Control Source and Plant Documents, dated March 25, 1981 and identified that controls had been established for the return of Form BF 92.
The inspector reviewed approximately 25 completed Form BF 92's and verified they were being used as required by BF 2. 1.
c.
(Open)
Open Item (259,260,296/81-02-11):
Training and certification program for gC inspectors into standard practices.
The licensee is in the process of developing increased training for gC inspectors.
The implementation of this program will be inspected during future inspec-tions.
d.
(Closed)
Open Item (259,260,296/81-02-12):
Conflict between audit procedures.
The inspector reviewed OP-gAP-18. 1, Audits, Revision
dated March 26, 1981.
The categorization of audit findings as category A, B, or C has been deleted.
The inspector also reviewed QAAS-gAP-3. 1, (}uality Audit Program, Revision 7 dated March 2, 1981 and identified that both the former and latter procedures are now consistant.
(Closed)
Open Item (259,260,296/81-02-13):
Clarification of STEAR implementing procedures.
The inspector reviewed BF 17. 1, Special Test, dated April 29, 1981 and 0(AM, Part II, Section 4.6, Special Tests, Experiments, or Activities, dated March 20, 1981.
These instructions are now consistent in the manner in which STEAR's are processed.
f.
(Closed)
Inspector Followup Item (296/81-02-14):
Reinstall HPCI line insulation.
Discussions with cognizant personnel identified that the insulation had been reinstalled on.the HPCI line bypass valve FCV 73-8 '
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