ML20065C404
| ML20065C404 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 09/14/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065C408 | List: |
| References | |
| TAC-48049, NUDOCS 8209230398 | |
| Download: ML20065C404 (13) | |
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i DUKE POWER COMPAtlY DOCKET f10. 50-369 ftCGUIRE flVCLEAR STATION, UtilT 1 AMENDMEflT TO FACILITY OPERATING LICEfiSE Amendnent No. 16 License flo. 'iPF-9 1.
The fluclear Regulatory Connission (the Connission) has found that:
A.
The application for anendment to the f4cGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. f!PF-9 filed by the Duke Power Corpany (licensee) dated July 30, 1932, complies with the standards and requirenents of the Atonic Energy Act of 1954, as anended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the application, as anended, the provisions of the Act, and the regulations of the Con-nission; 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 Connission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the conmn defense and security or to the health and safety of the public; E.
The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachnents to this license anendment and paragraph 2.C.(?) of Facility Operating License No. NPF-9 is hereby anended to read as follows:
(2) Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 16, are hereby incorporated ii.to this license. The licensee shall operate the facility in accordance with the Technical Specifications
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This license amendment is effective as of its date of issuance.
FOR T!IE NUCLEAR REGULATORY COM;ilSS10ti 1
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Elinor G. Adensan, Chief Licensing Branch No. 4 Division of Licensing i
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Attachment:
Technical Specification Changes 4
I Date of Issuance: SePtenber 14, 1982 1
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1 ATTACHff tlT TO LICEtlSE AfiEll0MErlT tt0.16 FACILITY OPERATIflG LICEfiSE NO. NPF-9 DOCKET fl0. 50-369
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Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Anendnent nunber and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided to naintain docunent conpleteness.
4 Overleaf Anended Page Page 6-1 6-2 6-4 6-3 6-7 6-8 6-9 6-10 6-11 6-12 I
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4 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function.
A management directive to this effect signed by the Manager of Nuclear Production shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2-1.
UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2-2 and:
f a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
In addition, while the unit is in 4
MODE 1, 2, 3 or 4 at least one licensed Senior Reactor Operator shall be in the Control Room.
1 A health physics technician # shall be on site when fuel is in.the c.
reactor.
d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation-l A site Fire grigade of at least 5 members shall be ruaintained onsite e.
at all times.
The Fire Brigade shall not include 3 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.
/
- 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 t
to accommodate unexpected absence provided immediate action is taken to fill the required positions.
McGUIRE, UNIT 1 6-1 t
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k PRESIDENT F
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y EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT POWER OPERATIONS ENGINEERING & CONSTRUCTION y
VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT CORPORATE VICE PRESIDENT PRODUCTION SUPPORT NUCLEAR PRODUCTION DESIGN ENGINEERING QA MANAGER CONSTRUCTION I
NUCLEAR PRODUCTION GENERAL MANAGER NUCLEAR SAFETY QA MANAGER STAFF NUCLEAR STATIONS
- REVIEW BOARD OPERATIONS h
STATION MANAGER MCGUIRE QA ENGINEER NUCLEAR STATION I
QA/QC PERSONNEL i
9
- CORPORATE RESPONSIBILITY FOR FIRE PROTECTION PROGRAM n
I 5
5 Figure 6.2-1 Offsite Organization A
l r
HANAGER 2,
HCCUIRE NUCLEAR STATION C
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rn a
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-4 ADMINISTRAT!VE OPERATING Hall 4TENANCE SERVICES TECHNICAL SERVICES SUPERINTENDENT **
SUPERINTD4 DENT SUPERINTENDENT SUPERINTENDENT STATION SAFETY PERFORMANCE OPERATING HECllANICAL SUPERVISOR
- ENGINEER ENCINEER HAINTENANCE SRO ENGINEER esa SilIFT INSTRUMENT AND STATION llEALTil SUPERVISORS ELECTRICAL PitySICIST i
SRO ENGINEER i
REACTOR STATION OPERATORS CllEMIST RO l.ECEND:
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RO-REAltf0R OPERATOR I.lCENSE SRO-SENIOR REACTOR OPERATOR I.lCENSE.
UTILITY
- 0NSITE ItESPONSinti.lTY FOR FIRE PROTECTION PROGRAM OPERATORS
$ **0PERATli4C SUPERINTENDENT HUST ll0LD OR llAVE IIELD f,
SRO LICENSE if Figure 6.2-2 Station Org;anization 5
The llealth Physics Supervisor has direct access to the Station Hanager in matters concerning any phase of radiological protection. The llealth Physics Supervisor can also address any problems or concerns to the System flealth Physicist.
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l TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES 5 & 6 SS 1
1 SR0 1
None R0 2
1 A0 2
1 STA 1
None SS - Shift Supervisor with a Sepior Reactor Operator's License on Unit 1 SR0 - Individual with a Senior Reactor Operator's License on Unit 1 RO - Individual with a Reactor Operator's License on Unit 1 A0s - Auxiliary ~0perator STA - Shift Technical Advisor Encept for the Shif t Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the
N minimum requirements of Table 6.2-1.
This provisions does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor *) with a valid SR0 license shall be designated to assume the Control Room command function.
Dueing any absence of the Shift Supervisor from the Control Room while the unit is l
in MODE 5 or 6 an individual with a valid R0 lcense (other than the Shift Technical Advisor *) shall be designated to assume the Control Room Command function.
l 0 On occasions when there is a need for both the Shift Supervisor and the SR0 to be absent from the Control Room, the STA shall be allowed to assume the Control Room command function and serve as the SRO in the Control Room provided that: (1) the Shift Supervisor is available to return to the Control Room within 10 minutes, (2) the assumption of SR0 duties by the STA be limited to periods not in excess of 15 minutes duration and a total time not be exceed one hour during any 8-hour shift, and (3) the STA has an SRO license on the unit.
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i McGUIRE - UNIT 1 6-4
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l ADMINISTRATIVE CONTROLS L
6.5.1.6 Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission and all violations of Technical Specifications shall be investigated and a report I,
prepared which evaluates the occurrence and which provides recommendations to
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prevent recurrence.
Such reports shall be approved by the Station Manager and l
transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
6.5.1.7 The Station Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.
i 6.5.1.8 The station security program, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved i
by the Station Manager and transmitted to the Vice President, Nuclear Production, I 4
I and to the Director of the Nuclear Safety Review Board.
I 6.5.1.9 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, l
and to the Director of the Nuclear Safety Review Board.
6.5.1.10 The Station Manager shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Vice President, Nuclear Production and to l
the Nuclear Safety Review Board.
6.5.1.11 The Station Manager shall assure the performance of a review by a qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.
6.5.1.12 Reports documenting each of the activities performed under Specifications 6.5.1.1 through 6.5.1.11 shall be maintained.
Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1 The Nuclear Safety Review Board 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 McGUIRE - UNIT 1 6-7 Amendment No. 16
1 ADMINISTRATIVE CONTROLS
,t!
,1 FUNCTION (Continued) 4 4 d.
metallurgy e.
instrumentation and control 1
f.
radiological safety g.
mechanical and electrical engineering h.
administrative control and quality assurance practices h
ORGANIZATION 6.5.2.2 The Director, members and alternate members of the NSRB shall be appointed in writing by the Vice President, Nuclear Production, and shall have an academic deg,ee in an engineering or physical science field; and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one e
time.
t 6.5.2.3 The NSRB shall be composed of at least five members, including the Director. Members of the NSRB may be from the Nuclear Production Department, l
from other departments within the Company or from external to the Company.
A maximum of one member of the NSRB may be from the McGuire Nuclear Station staff.
6.5.2.4 Consultants shall be utilized as determined by the NSRB Director to i
provide expert advice to the NSRB.
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l 6.5.2.5 Staff assistance may be provided to the NSRB in order to promote the l
l proper, timely and expeditious performance of its functions.
6.5.2.6 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.-
6.5.2.7 The minimum quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these technical specifications shall consist of the Director, or his designated alternate, and at least 4 other NSRB members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of McGuire Nuclear Station.
2 McGUIRE - UNIT 1 6-8 Amendment No. 16
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gMINISTRATIVECONTROLS l
SUBJECTS REQUIRING REVIEd 6.5.2.8 The following subjects shall be reported to and reviewed by the NSRB:
a.
The safety evaluations for (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question.
l b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or this Operating License.
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 unit equipment that affect nuclear safety.
t g.
Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems or components that could affect nuclear safety.
i.
Quality Assurance Department audits relating to station operations j
and actions taken in response to these audits.
j.
Reports of activities performed under the provisions of Specification 6.5.1.1 through 6.5.1.11.
AUDITS 6.5.2.9 Audits of unit activities shall be performed under the cognizance of the NSRB.
These audits shall encompass:
The conformance of unit operation to provisions contained within the a.
Technical Specifications and applicable license conditions at least once per 12 months.
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b.
The performance, training and qualifications of the entire unit staff at least once per 12 months.
l McGUIRE - UNIT 1 6-9 l
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4 ADMINISTRATIVE CONTROLS l
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AUDITS (Continued) i c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that I
affect nuclear saf,ety 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 50, at at least once per 24 months.
e.
The Emergency Plan and implementing procedures at least once per 24 months.
f.
The Security Plan and implementing procedures at least once per 24 months.
g.
Any other area of unit operation considered appropriate by the NSRB or the Vice President, Nuclear Production.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizfig either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be perforced by an outside qualified fire consultant at intervals no greater than 3 years.
k.
The radiological envirorimental monitoring program and the results thereof at least once per 12 months.-
1.
The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementing procedures for solidifica-tion of radioactive wastes at least once per 24 months.
n.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 at least once per 12 months.
AUTHORITY 6.5.2.10 The NSRB shall report to and advise the Vice President, Nuclear Production, on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9.
McGUIRE - UNIT 1 6-10 Amendment No. 16
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l ADMINISTRATIVE CONTROLS RECORDS 6.5.2.11 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NS'RB meeting shall be prepared, approved and forwarded to the Vice President, Nuclear Production, and to the Executive Vice President, Power Operations, within 14 dayr, following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.8 above, shall be prepared, approved and forwarded to the Vice President, Nuclear Pro-duction, and to the Executive Vice President, Power Operations within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.9 above, shall be forwarded to the Vice President, Steam Production, and to the Executive Vice President, Power Operations, and to the management positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taker, for REPORTABLE OCCURRENCES:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the Station Manager; or by (1) the Operating Superintendent, (2) the Technical Services Superintendent, or (3) the Maintenance Superintendent, as previously designated by the Station Manager; and submitted to the NSRB and the Vice President, Nuclear Production.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
I b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Vice President, Nuclear Production, and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
McGUIRE - UNIT 1 6-11 Amendment No. 16
l ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the Operating Superintendent and the Station Manager.
This report shall describe (1.' applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Vice President, Nuclear Production, within 14 days of the violation.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
1 f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i.
Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, December 1977.
l 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved by the Station Manager; or by (1) the Operating Superintendent, j
(2) the Technical Services Superintendent, or (3) the Maintenance Superintendent, as previously designated by the Station Manager; prior to implementation and i
shall be reviewed periodically as set forth in administrative procedures.
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6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
s a.
The intent of the original procedure is not altered.
l McGUIRE - UNIT 1 6-12 Amendment No. 16
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