ML20005D745
| ML20005D745 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/04/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005D746 | List: |
| References | |
| NUDOCS 8912140411 | |
| Download: ML20005D745 (13) | |
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N>o, UNITED STATES
. ' 'n NUCLE AR REGULATORY COMMISSION y
WASHINGTON, D. C. 20555
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 47 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee)datedSeptember 25, 1989, as modified by letter dated
-October 16,.1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will o>erate in conformity with the ap)11 cation, the provisions of tie Act, and the regulations of tie Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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;
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of(the'Comaission's regulations and all applicable requirements have been; satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-80 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained-in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.47, 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 conditions.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f 43.${/
f George W'0irectorate V/Knighton, Director Project Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Chances to the Technical i
Specifications Date of Issuance: December 4, 1989
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. -i NUCLEAR REGULATORY COMMISSION UNITED STATES j
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6 PACIFIC GAS AND ELECTRIC COMPANY 1
i DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 1
AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.46 License No. DPR-82 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee)datedSeptember 25, 1989, as modified by letter dated October 16, 1989, complies with the standards and requirements of the-Atomic Energy Act of 1954, 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 regulations of the Commission; C.
There is reasonable assurance (i) 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 Connission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and')
E.
Tile.js'suance of this amendment is in accordance with 10 CFR Part 51 be(enpsatisfied.
o Ge Commission's regulations and all applicable requirements have
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No ' 46, 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 conditions.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE. NUCLEAR REGULATORY COMMISSION N /
Geo'ge W ighton, Di r
r Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
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. Specifications I
Date of Issuance: December.4, 1989 l
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ATTACHMENT TO LICENSE AMENDMENT NOS. 47 AND46 FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. Overleaf pages are also included, as appropriate.
i Remove Page Insert Page 6-f 6-6 6-9 6-9 6-10 6-10 6-12 6-12 6-13 6-13 1
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16' A M :STRA?:VE CONTROLS C3'.' S W : (Continued)
All CORE ALTERATIONS shall be observed and directly supervised by either c.
i a licensed Senior Operator or Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during th'is operation; A site Fire Brigade of at least five members' shall be maintained e.
onsite at all times.. The Fire Brigade shall not include the Shift Supervisor and the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; f.
Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators Health Physicists, auxiliary operators, and key maintenance personnel.
Ade::uate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a nominal 40-hour week while the unit is operating. However, l
in the ever.t that unforeseen problems require substantial amounts of.
overtirre to be used, or during extended periods of shutdown for L
l refueling, major maintenance or major plant modifications, on a l
temporary basis, the following guidelines shall be followed:
1 1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time; 2)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any (8-hour l
period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time; 2)
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work l
periods, including shift turnover time; and 4)
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the L
entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Manager or his designee, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant-Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized; and g.
The Operations Manager shall hold a senior reactor operator license.
'The Health Physics Technician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence provided immediate action is taken to fill the recuired positions.
DIABLO CANYON - UNITS 1 & 2 6-5 Amendment Nos. 43 and 42
ADMINISTRATIVE CONTROLS 6.2.3 ONSITE SAFETY REVIEW GROUP (OSRGJ FUNCTION A>"'
6.2.3.1 The OSRG shall function to examine plant operating characteristics, NRC issuances, industry advisories, REPORTABLE EVENTS. and other sources of plant design and-operating experience information, including plants of similar
. design, which may indicate areas for improving plant safety.
The OSRG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the Manager, Nuclear Safety Assessment and Regulatory Affairs.
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, COMPOSITION.
6.2.3.2 The OSRG shall be composed of at least five engineers located on site.
RESPONSIBILITIES 6.2.3.3 The OSRG shall be responsible for maintaining surveillance of plant j
activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4 'The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the plant.
-1 6.3 PLANT STAFF QUALIFICATIONS 6.3 Each member of the plant staff shall meet or exceed the minimum qualifi-i cations of ANSI /ANS 3.1-1978 for comparable positions, except for the Radiation
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Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 2, April 1987 for Radiation Protection Manager.
The licensed j
Operators and Senior Operators shall also meet or exceed the minimum qualifica-tions of 10 CFR Part 55 and the supplemental requirements specified in Section i
A of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, i
- Not responsible for sign-off function.
DIABLO CANYON - UNITS 1 & 2 6-6 Amendment Nos.47 and 46
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m RESPONSIBILITIES'(Continued) 6.5.2.7 The Plant Staff Review Committee shall:
i Recommend to the Plant Manager written approval or disapproval of i
a.-
items considered under Specification 6.5.2.6a. through d. above; 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
~ 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 Vice Paesident, c.
Nuclear Power Generation and the General Office Nuclear Plant Review and Audit Committee of disagreement between the PSRC and the Plant Manager; however, the Plant Manager shall have responsibility for l
resolution of such disagreements pursuant to Specification 6.1.1 above.
RECORDS 6.5.2.8 The Plant Staff Rev'ew Committee 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 Specifications.
Copies shall be provided to the Vice President, Nuclear Power Generation and the General Office Nuclear Plant Review and Audit Committee.
6.5.3 GENERAL OFFICE NUCLEAR PLANT REVIEW AND AUDIT COMMITTEE (GONPRAC)
FUNCTION 6.5.3.1 The General Office Nuclear Plant Review and Audit Committee shall function to provide independent review and audit of designated activities in the areas of.
i l
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, i,
d.
Metallurgy, i
e.
Instrumentation and control, f.
Radiological safety, i
g.
Mechanical and electrical engineering, and h.
Quality assurance practices.
GONPRAC shall report to and advi,se the Vice President, Nuclear Power Generation on those areas of responsibility specified in Specifications 6.5.3.7 and 6.5.3.8.
DIABLO CANYON - UNITS 1 & 2 6-9 Amendment Nos.47 and 46
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t ADMINISTRATIVE CONTROLS COMPOSITION 6.5.3.2 GONPRAC shall be composed of the following:
Chairman:
Manager, Nuclear Safety Assessment and Regulatory Affairs Vice Chairman:
Manager, Nuclear Operations Support Member:
Assistant-to the Vice President, Nuclear Power Generation Member:
Manager, Nuclear Engineering and Construction Services Member:
Manager, Quality Assurance Member:
Chief Mechanicai and Nuclear Engineer Member:
Manager, Station Construction Member:
Director, Nuclear Regulatory Affairs Member:
Plant Manager, Diablo Canyon Power Plant ALTERNATES 6.5.3.3 All alternate members shall be appointed in writing by the GONPRAC Chairran to serve on a temporary basis; however, no more than two alternates shall participate as voting members in GONPRAC activities at any one time.
CONSULTANTS 6.5.3.4 Consultants shall be utilized as determined by the GONPRAC Chairman to provide expert advice to GONPRAC.
MEETING FREQUENCY 6.5.3.5 GONPRAC shall meet at least once per calendar quarter during the ini-tial year of plant operation following fuel loading and at least once per 6 months thereafter.
QUORUM 6.5.3.6 A quorum of GONPRAC necessary for the performance of the GONPRAC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four GONPRAC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the plant.
REVIEW 6.5.3.7 GONPRAC shall review:
a.
The safety evaluations for:
(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.47 and 46 r.'.-
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b.
Prcpesed changes to procedures equipment or systems which involve an unreviewed safety question a,s defined in 10 CFR 50.59; Preposed tests or experiments which involve an unreviewed safety c.
question as defined in 10 CFR 50.59; Proposed changes to Technical Specifications or this Operating d.
License; Violations of Codes, regulations, orders, Technical Specifications, l
e.
license re:;uirements, or of internal procedures or instructions ha,in; nuclear safety significance; Sig" ficant operating abnormalities or deviations from normal and e gectec perfermance of plant equipment that affect nuclear safety; 5
Ali RE:DETABLE EVENTS; h.
All recog-i2e: indications of an unanticipated deficiency in some as ect cf desig*. or operation of safety related structures, systems, i
c cetponents that could affect nuclear safety; and i.
Recerts and meetings rrinutes of the Plant Staff Review Committee and tre Onsite Safety Review Group.
C :~5 5.5.3.E A.::its cf plant activities shall be performed under the cognizance of l
G;'i:RA*.
7nese audits shall encompass:
Tnt cenformance of plant operation to provisions contained within the a.
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 8,10 CFR Part 50, at least once per 24 months; The fire prctection program and implementing procedures at least e.
once per 24 months by qualified personnel; f
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c.'.
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 i
be used at least every third year; g.
Any other area of plant operation considered appropriate by GONPRAC or the Vice President, Nuclear Power Generation; h.
The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; i.
The ODCP 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 GONPRAC activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each GONPRAC meeting shall be prepared, approved and y
forwarded to the Vice President, Nuclear Power Generation within'14 l
l working days following each meeting; b.
Reports of reviews encompassed by Specification 6.5.3.7 above, shall l
be prepared,' approved and forwarded to the Vice President, Nuclear l'
Power Generation within 14 working days following completion of the I
review; and c.
Audit reports encompassed by Specification 6.5.3.8 above, shall be forwarded to the Vice President, Nuclear Power Generation and to the l
1 management positions responsible for the areas audited within 30 days after completion of the audit.
l 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.47 and 46
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ADMINISTRATIVE CONTROLS-REPORTABLE EVENT ACTION (Continued) b.
Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review submitted to GONPRAC and the Vice President, Nuclear Power Generation.
6.7 SAFETY LIMIT VIOLATION
- 6. 7 The following actions shall be taken in the event a Safety Limit is violated:
The NRC Operations Center shall be notified by telephone as soon as a.
possible and in all cases within I hour.
The Vice President, Nuclear Power Generation and GONPRAC shall be 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 describe:
(1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence; c.
The Safety Limit Violation Report shall be submitted to the Commis-sion, GONPRAC and the Vice President, Nuclear Power Generation within l
l 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 l
covering the activities referenced below; The applicable procedures recommended in Appendix A of Regulatory a.
Guide 1.33, Revision 2, February 1978; b.
The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter No. 82-33; c.
Security Plan implementation; d.
Emergency Plan implementation; e.
PROCESS CONTROL PROGRAM implementation; 1
f.
ODCP and ERMP implementation; and g.
Quality Assurance Program for effluent and environmental monitoring.
DIABLO CANYON - UNITS 1 & 2 6-13 Amendment Nos. 47 and 46 E
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cc:',: P W v! CONTEDL5 5:::!D' !5 AC PRD'iRAMS (Continued)
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- f. E. 2 Each p*ocedure of Specification 6.8.1 above, and changes thereto, and r
all proposed tests and experiments that affect nuclear safety shall be appresed prior to implementation by the Plant Manager or by a technically qualified manager who reports directly to the Plant Manager, as previously oesignated by the Plant Manager.
Prior to approval the Plant Manager or cesignated manager shall ensure that all necessary r,eviews and cress-disciplinary reviews, if appropriate, have been completed.
If deemed necessary, such cross disciplinary reviews shall be performed by the apprepriate designated plant review personnel.
Administrative procedures, procedures implementing the Security Plan, Emergency Plan, and Process Control Program, the OSCP and ERMP, and changes thereto, shall be reviewed by the PSRC and appreved t;/ the Plant Manager prior to implementation.
Each procedure of Specificatier 6.6.1 aoove shall be reviewed periodically as set forth in a:ministrative procedures.
E.E.3 Tem;o a y changes to procedures of Specification 6.8.1 above may be ma:e crevice::
The intent cf the original procedure is not altered; a.
Tne chan;e is approved by two members of the plant management staff, t.
at least one of whom holds a Senior Operator license on the unit affecte:; and The change is documented, reviewed and approved by the Plant Manager, c.
o* py a technically qualified manager who reports directly to the Fiar.t Manager as previousl 14 cays of implementation.y designated by the Plant Manager, within
- f. E. 4 ine fo11o*ing programs shall be established, implemented, and maintained:
a.
Reacter Coelant Sources Outside Containment A program te 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 lnjection System, Chemical and Volume Control System, Residual Heat Removal System, RCS Sample $ystem, and Liquid and Gaseous Radweste Treatment Systems.
The progree shall include the following:
1)
Preventive maintenance aM periodic visual inspection requirements, and 2)
Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
In Plant Radiation Monitoring 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.
DIAELO CANYON - UNITS 1 & 2 6-14 Amendment Nos.41 and 40
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