ML20092H508

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Amends 68 & 67 to Licenses DPR-80 & DPR-82,respectively, Revising Section 6,administrative Controls,Of Facilities TS to Change Description of Nsoc Membership & Eliminate Use of Alternates on Committee
ML20092H508
Person / Time
Site: Diablo Canyon  
(DPR-80-A-068, DPR-80-A-68, DPR-82-A-067, DPR-82-A-67)
Issue date: 02/06/1992
From: Quay T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20092H511 List:
References
NUDOCS 9202210174
Download: ML20092H508 (16)


Text

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  1. c UNITED STATES
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO 50-275 DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-80 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated August-7,1991, as supplemented by letter dated November 22,1991,- complies with the standards and requirements of the-Atomic Energy Act of 1954, as amended (the Act), and the Comission's

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regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions-of-the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.-

The issuance-of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

iThe issuance of th'is amendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license acendment, i

and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to read as follows:

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2-(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

68 are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specificetions and the Environmental Protection Plan, except where otherwise stated in specific lictnse conditiens.

1 3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Attachrtent:

Changes to the Technical Specifications Date of Issuance:

February 6,1992 4

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  • PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DI ABLO CANYON NUCLEAR POWER PLANT, UNIT NO. 2 AMEhDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. OPR-82 1.

The Nuclear Regclatory Commission (the Comission) has found that:

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated August 7,1991, as supplemented by letter dated Noventer 22, 1991, complies with the standards and requirenents of the Atomic Energy Act of 19E4, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this arendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliar.ce with the Commission's regulatiors; C.

The issuance of this amendment v.'ill not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of th'is armndment is in accordar.ce with 10 CFP Part 51 of the Comission's regulations and all applicable requirenents have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendnent, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby anended to read as follows:

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. 1 (2) Technical Specifications The Technical Specifications contained ir. Appendix A and the Environnental Protection Plan contained in Appendix B, as revised through Amendment No.

67 are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license condi tiens.

3.

This license amendment is effective as of the date of its issuance.

FOR THE huCLEAR REGULATORY C0tNISSION l

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Theodore R. Quay, Director Project Directorate V Division of Reactor Projects Ill/lV/V Office of Nulcear Reactor Regulation Attachnent:

Changes to the' Technical Specifications Date of Issuance:

February 6,1992

v. e.

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 67 TO FACILITY OPERATING ICENSE NO. DPR-82 DOCKET NOS. 50-2'/S AND 50-323 Revise Appendix A Technical Specifications by removing the pages identified

- below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages are also included, as appropriate.

REMOVE-INSERT xxi xxi xxii xxii 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-20 6-20 i

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY....................................................

6-1 6.2 ORGANIZATION 6.2.1 0FFSITE........................................................

6-1 6.2.2 PLANT STAFF.....................................................

6-1 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION............................

6-4 6.2,3 ONSITE SAFETY REVIEW GROUP (OSRG)

Function........................................................

6-6 Composition.....................................................

6-6 Responsibilities................................................

6-6 6.2.4 SHIFT TECHNICAL ADVIS0R.........................................

6-6 6.3 PLANT STAFF QUALIFICATIONS........................................

6-6 6.4 TRAINING..........................................................

6-7 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL Activities..........'............................................

6-7 6.5.2 PLANT STAFF REVIEW COMMITTEE (PSRC)

Function........................................................

6-7 Composition.....................................................

6-7 Alternates................'.

3...................................

6-7 I

Meeting Frequency...............................................

6-7 Quorum..........................................................

6-7 Responsibilities................................................

6-8 Records.........................................................

E-9 1

DIABLO CANYON - UNITS 1 & 2 xxi Amendment Nos. 68 and 67

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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5 REVIEW AND AUDIT (Continued) 6.5.3 NUCLEAR SAFETY OVERSIGHT COMMITTEE (NSOC)

Function........................................................

6-9 Composition....................................................

6-10 Alternates.....................................................

6-10 Consultants....................................................

6-10 Meeting Frequency..............................................

6-10 Quorum.........................................................

6-10 Review.........................................................

6-30 Audits.........................................................

6-11 Records........................................................

6-12 6.6 REPORTABLE EVENT ACTI0N..........................................

6-12 6.7 SAFETY LIMIT VIOLATION...........................................

6-13 6.8 PROCEDURES AND PR0 GRAMS..........................................

6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS................................................

6-16 Startup Reports....'...........................................

6-16 Annual Reports.................................................

6-16 Annual Radiological Environmental Operating Report.............

6-17 Semiannual Radioactive Effluent Release Report.................

6-18 Monthly Operating Report.......................................

6-18 C08E OPERATING LIMITS REP 0RT.'..................................

6-18 6.9.2 SPECIAL REP 0RTS................................................

6-19 6.10 RECORD RETENTION................................................

6;-19 6.11 RADIATION PROTECTION PR0 GRAM....................................

6-21 6.12 HIGH RADIATION AREA.............................................

6-21 DIABLO CANYON - UNITS 1 & 2 xxii Amendment Nos.68 and 67

l ADMINISTRATIVE CONTROLS i

RESPONSIBILITIES-6.5.2.6 The Plant-Staff Review Committee shall be responsible for

1 a.-

Review of - (1)Administrativeprocedures,SecurityPlanimplementing procedures, Emergency Plan implementing procedures, and changes

- thereto (2) the safety evaluations fort (a) changes to. procedures

- and (b) tests or experiments completed under the provision of-10 CFR_50.59, to verify that such actions do not-constitute an 1

- unreviewed safety question and (3) proposed procedures or changes i

thereto that have been initially determined to constitute an

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unreviewed safety question or require a change to the Technical j

Specifications; i

b.

Review of-all proposed changes to Appendix 'A" Technical Specifications; c.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; d.

Investigation of all violations of the Technical' Specifications in-cluding the preparation and forwarding-of reports covering rvaluation and recommendations to' prevent recurrence to t + Senior Vice President and General Manager, Nuclear Power Generation and to the Chairman of-

the Nuclear Safety Oversight Committee (NS00); the investigation shall include an assessment of the safety significance of each violation.

e.-

Review of all REPORTABLE EVENTS; f.

Review of plant operations to detect potential nuclear safety hazards;-

9 Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of NSOC;.

h.

Review of the Security Plan and implementing procedures and shall submit recommended changes to the Chairman of-the_NSOC or the Plant l

Manager, as appropriate; 1.

Review of the Emergency Plan and implementing procedures'and shall submit recommended changes to_the Chairman of the NSOC or the Plant l-Manager, as appropriate; j.

' Review of any accidental, unplanned,-or uncontrolled radioactive release including the preparation and forwarding of reports covering evaluation,. recommendations and disposition of the corrective. action-to prevent recurrence to the Senior Vice President-and General Manager, Nuclear. Power Generation and to NSOC; and l

k.

- Review of. changes to the PROCESS' CONTROL PROGRAM, ODCP, ERMP, and the Radwaste Treatment Systems.

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DIABLO CANYON - UNITS 1 &-2 6-8 Amendment Nos.68 and 67 i

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ADMINISTRATIVE CONTROLS RESPONS!BILITIES (Continued) 6.5.2.7 The Plant Staff Review Committee shall a.

Recommend to the Plant Manager written approval or disapproval of items considered under Specification 6.5.2.6a. through d. above l

b.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.2.6a. through e, above con-stitutes an unreviewed safety question; and c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior Vice Presi-dent and General Manager, Nuclear Power Generation and NSOC of dis-l agreement between the PSRC and the Plant Manager; however, the Plent j

Manager shall have responsibility for resolution of such disagreements 1

pursuant to Specification 6.1.1 above.

RECORDS 6.5.2.8 The Plant Staff Review Comnittee shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activi-ties performed under the responsibility and authority provisions of these Technical Specificctions. Copies shall be provided to the Senior Vice_ President and General Manager, Nuclear Power Generation and NSOC.

6.5.3 NUCLEAR SAFETY OVERSIGHT COMMITTEE (NSOC)

FUNCTION 6.5.3.1 The NSOC shall function to provide independent review and audit of l

designated activities in the areas of:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.-

Chemistry and radiochemistry, d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineering, and h.

Quality assurance practices.

NSOC shall report to and advise the Senior Vice President and General Manager, l

Nuclear Power Generation on those areas of responsibility specified in Specifi-cations 6.5.3.7 and 6.5.3.8.

DIABLO CANYON - UNITS 1 & 2 6-9 Amendment Nos. 68 and 67

ADMINISTRATIVE CONTROLS COMPOSITION 6.5.3.2 NSOC shall be composed of a chairman and a minimum of four members.

The NSOC Chairman and members shall be appointed in writing by the Senior Vice President and General Manager, Nuclear Power Generation. The NSOC Chairman shall have a minimum of six years of professional level managerial experience in the power field and the NSOC members shall have a minimum of five years of professional level experience in the field of their specialty. The NSOC Chairman and all members shall have qualifications that meet or exceed the requirements and recommendations of Section 4.7 of ANSI /ANS 3.1-1978.

ALTERNATES 6.5.3.3 This section deleted.

CONSULTANH 6.5.3.4 Consultants shall be utilized as determined by the NSOC Chairman to l

provide expert advice to NSOC.

MEETING FREQUENCY 6.5.3.5 NSOC shall meet at least once per 6 months.

l QUORUM 6.5.3.6 A quorum of NSOC necessary for the performance of the NSOC functions of these Technical Specifications shall be a majority (one-half or more) of the members, but no less than four.

No more than a minority of the quorum shall have line responsibility for operation of the plant.

REVIEW 6.5.3.7 NSOC shall review:

I a.

The safety evaluations fort (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; DIABLO CANYON - UNITS 1 & 2 6-10 Amendment Nos.68 and 67

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ADMINISTRATIVE CONTROLS i

REvi M (Continued) b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; c.

Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.

Proposed changes to Technical Specifications or this Operating License; i

e.

Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety; i

g.

All REPORTABLE EVENTS; h.

All recog-ized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components that could affect nuclear safety; and 1.

Reports and meetings minutes of the Plant Staff Review Committee and the Onsite Safety Review Group.

AUDITS 6.5.3.8 Audits of plant activities shall be performed under the cognizance of-NSOC.

These audits shall encompass:

l a.

The conformance of plant operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; b.

The performance, training and qualifications of the entire plant staff at least once per 12 months; The results of actions'taken to correct deficiencies occurring in c.

, plant equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months; d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; e.

The fire protection program and implementing procedures at-least once per 24 months by qualified personnel; DIABLO CANYON - UNITS 1 & 2 6-11 Amendment Nos. 68 and 67

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ADMINISTRATIVE CONTROLS AUDITS (Continued) f.

The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year; g.

Any other area of plant operation considered appropriate by NSOC or the Senior Vice President and General Manager, Nuclear Power Generation; h.

The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; i.

The GDCP and ERMP and implementing procedures at least once per 24 months; j.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months; and k.

The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.

RECORDS 6.5.3.9 Records of NSOC activities shall be prepared, approvad and distributed l

as indicated below:

a.

Minutes of each NSOC meeting shall be prepared, approved and l

forwarded to the Senior Vice President and General Manager, Nuclear Power Generation within 14 working days following each meetings b.

Reports of reviews encompassed by Specification 6.5.3.7 above, shall be prepared, approved and forwarded to the Senior Vice President and General Manager, Nuclear Power Generation within 14 working days following completion of the review; and c.

Audit reports encompassed by Specification 6.5.3.8 above, shall be

, forwarded to the Senior Vice President and General Manager, Nuclear Power Generation and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE EVENT ACTION 6.6.

The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73; and DIABLO CANYON - UNITS 1 & 2 6-12 Amendment Nos. 68 and 67

ADMINIS1RATIVE CONTROLS REPORTABLE EVENT ACTION (Continued) b.

Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review submitted to NSOC and the Senior Vice President and General Manager, Nuclear Power Generation.

6.7 SAFETY LIMIT VIOLATION 6.7 The following actions shall be taken in the event a Safety Limit is violateos a.

The NRC Operations Center shall bc notified by_ telephone as soon as possible and in all cases within I hour.

The Senior Vice President and General Manager, Nuclear Power Generation and NSOC shall be l

notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by_the PSRC. This report shall describes (1) applicable circumstancesprocedingtheviolation,(2)effectsoftheviolation upon unit compcncnts, systems or structures, and (3) corrective action taken to prevent recurrence; c.

The Safety Limit Violation Report shall be submitted to the Commis-sion, NSOC and the Senior Vice President and General Manager, Nuclear Power Generation within 14 days of the violation; and d._

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained t

covering the activities referenced belows a.

The applicable procedures recommended in Appendix A of Regulatory

- Guide 1.33, Revision 2, February 1978; b.

The emergency operating procedures required to implement the l

requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Generic Letter No. 82'33; c.

Security Plan implementation; d.-

Emergency Plan implementation; e.

PROCESS CONTROL PROGRAM implementation; f.

ODCP and ERMP implementation; and g.

Quality Assurance Program for effluent and environn. ental monitoring.

DIABLO CANYON - UNITS 1 & 2 6-13 Amendment Nos. 68 and 67 l

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4 e-ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.2 Each procedure of Specification 6.8.1 above, and changes thereto, and all proposed tests and experiments that affect nuclear safety shall be approved prior to implementation by the Plant Manager or by a technically qualified manager who reports directly to the Plant Manager, as previously designated by the Plant Manager.

Prior to a designated manager shall ensure that all ne pproval, the Plant Manager or essary reviews and cross-disciplinary reviews, if appropriate,-have been completed.

If deemed necessary, such cross-disciplinary reviews shall be perfermed by the appropriate designated plant review personnel.

Administrative procedures, procedures implementing the Security Plan, Emergency Plan, and Process Control Program, the ODCP and ERMP, and changes thereto, shall-be reviewed by the PSRC and approved by the Plant Manager prior to implementation.

Each procedure of Specification 6.8.1 above shall be reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 above may bo

-made provided:

The intent of the original procedure is not altered; a.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator -license on the unit affected; and The change is documented, reviewed and approved by the Plant Manager, c.

or by a technically qualified manager who reports directly to the Plant Manager as previously designated by the Plant Manager, within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

Reactor Coolant Sources Outside Containment a.

A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient,or accident to as low as practical levels.

The systems include portions of the Recirculation Spray System, Safety Injection System, Chemical and Volume Control System, Residual Heat Removal System, RCS Sample System, and Liquid and Gaseous Radwaste Treatment Systems. The program shall include the following:

1)

Preventive maintenance end periodic visual inspection requirements, and,

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2)

Integrated' leak te?st requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1)

Training of personnel, 2)

Procedures for monitoring, and 3)

Provisions for maintenance of sampling and analysis equipment.

DIABLO CANYON - UNITS 1 & 2 6-14 Amendment Nos. 41 and40

1 ADMINISTRATIVE CONTROLS 3.

WCAP-8385, Power Distribution Control and Load Following Procedures, September 1974 (Westinghouse Proprietary).

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c..The core operating limits shall be determined so that all applicable limits (e.g.,. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and i

transient and accident analysis limits) of the-safety analysis are

met, d.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS-6.9.2 Special reports shall be ',ubmitted to the NRC in accordance with 10 CFR 50.4 within the time period specified for each report.

6.10 RECORD RETENTION In Addition to the applicable record retention requirements of Title 30, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level;

-b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of-equipment related to nuclear safety; c.

ALL REPORTABLE EVENT 5; i

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l DIABLO CANYON - UNITS 1 & 2 6-19 Amer.dment Nos. 67 and 66 l

ADMINISTRATIVE CONTROLS RECORDRETENTION-(Continued) d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications; e.-

Records of changes made to procedures required by Specification 6.8.1; f.

Records of radioactive shipments; g.

Records of sealed source and fission detector leak tests and results; and h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of tne unit Operating Licenses a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; b.

Records of new and irrtdiated fuel inventory, fuel transfers and assembly burnup histories; Records of radiation exposure for all individuals entering radiation c.

control areas; d.

Records of gasecus and liquid radioactive material released to the environs; Records of transient or operational cycles for those unit components

-e.

-identified in Table 5.7-1; Recordsofreactbrtestsandey.eriments; f.

g.

Records of training and qualification for current members of the unit staff; h.

Records of in-service inspections-performed pursuant to these Technical Specificatiops;

i. ; Records of Quality Assurance activities required by the QA Manual; j.

Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59; k.

Records of meetings of the PSRC and NSOC; DIABLO CANYON - UNITS-1 & 2 6-20 Amendment Nos.68 and 67