ML17290A597
| ML17290A597 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/08/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17290A598 | List: |
| References | |
| NUDOCS 9309150045 | |
| Download: ML17290A597 (10) | |
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UNITEDSTATES t NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
118 License No.
NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated June 2,
- 1993, 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 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 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 common defense and security or to the health and safety of the public; and E.
The issuance of this amendment 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 Specifications as indicated in the attachment to this amendment and paragraph 2.C.(2) of Facility Operating NPF-21 is hereby amended to read as follows:
Technical license License No.
9309>S00OS 93O9OS PDQ ADOCK 05000397 P'DR
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. ii8 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective 15 days from date of 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
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 8, i993
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 118 TO FACILITY OPERATING LICENSE NO.
NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised, pages are identified by amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE 6-10 6-13 INSERT 6-10 6-13
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DMINISTRATIVE CONTRO LLIIOOPO IIBOIILLIITIU 6.5.1.6 at C.
d.
e.
go h.
k.
The POC shall be responsible for:
Review of (I) all proposed procedures required by Specification 6.8 and changes
- thereto, (2) all proposed programs required by Specifica-tion 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety; Review of all proposed tests and experiments that affect nuclear safety; Review of all proposed changes to the Appendix A Technical Specifications; Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Assistant Managing Director for Operations and to the Corporate Nuclear Safety Review Board; Review of all REPORTABLE EVENTS; Review of unit operations to detect potential hazards to nuclear safety; Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Corporate Nuclear Safety Review Board; Review of the Security Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board; Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board; Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition'f the corrective action to prevent recurrence and the forwarding of these reports to the Assistant Managing Director for Operations and to the Corporate Nuclear Safety Review Board; and Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
AUTHORITY 6.5.1.7 a 0 The POC shall:
Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6a.
through d. prior to their implementation.
MASHINGTON NUCLEAR - UNIT 2 6-9 Amendment No.
6
DNINISTRATIVE CONTROLS f~gORIQ (Continued) b.
Render determinations in writing with regard to whether or not each item considered under Specification 6,5.1.6a.
through e. constitutes an unreviewed safety question as defined in 10 CFR 50.59.
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 Assistant Nanaging Director for Operations and the Corporate Nuclear Safety Review Board of disagreement between the POC and the Plant Nanager; however, the Plant Nanager shall have responsibility for resolution of such dis-agreements pursuant to Specification 6.1.1.
QC~O)S 6.5.1.8 The POC shall maintain written minutes of each POC meeting that, at a minimum, document the results of all POC activities performed under the respon-sibility provisions of these Technical Specifications.
Copies shall be provided to the Assistant Nanaging Director for Operations and the Corporate Nuclear Safety Review Board.
6.5.2 CORPORATE NUCLEAR SAFETY REVIEW BOARD CNSRS
~FUNC 10N 6.5.2.1 The CNSRB shall function to provide independent review and audit of 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, 9
Nechanical and electrical engineering, and h.
guality assurance practices.
The CNSRB shall report to and advise the Assistant Nanaging Director for Operations on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.
WASHINGTON NUCLEAR - UNIT 2 6-10 Amendment No. $,118
DNINISTRATIVE CONT
~UPS (Continued)
..h.
The fire protection equipment and program implementation, at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant.
An outside independent fire protection consultant shall be utilized at least once every third year; and i.
Any other area of unit operation considered appropriate by the CNSRB or the Assistant Nanaging Director for Operations.
j.
The radiological environmental monitoring pt ogram and the results thereof at least once per 12 months.
k.
The OFFSITE DOSE CALCULATION NANUAL and implementing procedures at least once per 24 months.
1.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
m.
The performance of activities required by the guality Assurance Program for effluent and environmental monitoring at least once per 12 months.
ECORDS 6.5.2.9 Records of CNSRB activities shall be prepared,
- approved, and distri-buted as indicated below:
a.
Hinutes of each CNSRB meeting shall be prepared,
- approved, and forwarded to the Assistant Nanaging Director for Operations 14 days following each meeting.
b.
Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared,
- approved, and forwarded to the Assistant Nanaging Director for Operations within 14 days following completion of the review.
c.
Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Assistant Nanaging Director for Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE EVENT AC ION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the (POC),
and the results of this review shall be submitted to the CNSRB and the Assistant Nanaging Director for Operations.
MASHINGTON NUCLEAR - UNIT 2 6-13 Amendment No. Jf,118
DMINISTRATIVE CONTROLS
- 6. 7 SAFETY INIT VIOLATION 6.7. 1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Assistant Nanaging Director for Operations and the CNSRB shall be notified.
b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the POC.
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 Commission, the
- CNSRB, and the Assistant Nanaging Director for Operations.
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 covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
b.
The applicable procedures required to implement the requirements of NUREG-0737.
c.
Refueling operations.
E d.
Surveillance and test activities of safety-related equipment.
e.
Security Plan implementation.
f.
Emergency Plan implementation.
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Fire Protection Program implementation.
h.
PROCESS CONTROL PROGRAM implementation.
- i.
OFFSITE DOSE CALCULATION NANUAL implementation.
j.
guality Assurance Program for effluent and environmental monitoring.
k.
Health Physics/Chemistry Support Program.
6.8.2 Each procedure of Specification 6.8. la. through j., and changes
- thereto, shall be reviewed by the POC and shall be approved by the Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
In addition, the review and approval of the implementing procedures supporting item k. in Specification 6.8.1 will be coordinated by the Nanager of Support
- Services, who will provide review and approval control.
The
'WNP-2 Health Physics/Chemistry Support Program procedure will be reviewed by POC and approved by the Plant Nanager.
WASHINGTON NUCLEAR - UNIT 2 6-14 Amendment No. 63