ML19250C561
| ML19250C561 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/08/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19250C559 | List: |
| References | |
| NUDOCS 7911280210 | |
| Download: ML19250C561 (17) | |
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY D0CKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. NPF-1 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated August 13, 1979, as supplemented August 22 and September 12, 1979, complies with the standards and requirements of the Atomic EneiJy Act of 1954, as amended (the Act), and the Comission's rules and 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 at;d all applicable requirements have been satisfied.
1404
?86 7911280 M
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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. NPF-1 is hereby amended to read as follows:
"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications, except as noted in paragraph 2.C. (10) below".
3.
This license amendment is effective 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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/ A. Schwencer, Chief Q
Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: November 8,1979 1404 187
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0. 42 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
Remove Pages Insert Pages 6-1/6-2 6-1/6-2 6-3 6-4 6-3/6-4 6-5 6-6 6-5/6-6 6-7/6-8 6-7/6-8 6-9/6-10 6-9/6-10 6-13 6-14 6-13/6-14 Revise Appendix B as follows:
Remove Pages Insert Pages Figure 5.1 Figure 5.1 Figure 5.2 Figure 5.2 1404
?88;
6.0 ADMIN'3TRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility dur,ing his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Fiqure 6.2-2 and:
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 Operator shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
All CORE ALTERATIONS after the initial fuel loading shall be 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.
f.
A Fire Brigade of at least 5 members shall be maintained onsite at all times.
The Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
1404 189 c
TROJAN-UNIT 1 6-1
/rendment No. JS, 42
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,i TROJAN-UNIT 1 6-2 Amendment No. J2, JE,42
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i-TROJAN-UNIT 1 6-3 Amendment No. 78, 23, 37, 42 1404
?91
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITICN LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SQL 1
1*
1 OL Non-Licensed 2
1
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handlir.g supervising CORE ALTERATIONS af ter the initial fuel loading.
- Shif t crew 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 accommodate unexpected absence of on duty shift crew members provided inmediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
1404
?92 TROJAN-UNIT 1 6-4
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N10.1-1971 for comparable positions, except for the Radiation Protection Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING 6.4.'
A retraining and replacement training program for the facility sta'- shall be maintained under the direction of the General Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Genera. Manager and shall meet or exceed the requirements of Section 27 o' the NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)
FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the General Manager on all matters related to nuclear safety.
1404
?93 TROJAN-UNIT 1 6-5 Amendment No. 78, 37,42
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The Plant Review Board shall be composed of the:
Chairman:
Manager, Technical Services Member:
Engineering Supervisor Member:
Maintenance Supervisor Member:
Operations Supervisor Member:
Quality Assurance Supervisor Member:
Radiation Protection Supervisor ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate.
000 RUM 6.5.1.5 A quorum of the PRB shall consist of the Chairman or his designated alternate and at least four members includino alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Review Board shall be responsible for:
a.
Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the General Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
1404
?94 TROJAN-UNIT 1 6-6 Amendment No. 42
ADMINISTRATIVE CONTROLS Review of all proposed char.ges to Appendix "A" Technical c.
Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Executive Vice President and to the Chairman of the Nuclear Operations Board.
f.
Review of those REPORTABLE OCCURRENCES 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.
Review of facility operations to detect potential safety g.
hazards.
h.
Per'ormance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Operations Board.
i.
Revies of the Plant Security Plan and implementing procedures and shall submit recommended changes to Cha rman of the i
Nuclear Operations Board.
j.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Operations doard.
AUTHORITY 6.5.1.7 The Plant Review 30ard shall:
Recommend to the General Manager written approval or a.
disapproval of items considered under 6.5.1.6(a) through (d)
- above, b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
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 Executive c.
Vice President and the Nuclear Operations Board of disagreement between the PRE and the General Manager; however, the General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
TROJAN-UNIT 1 6-7 Amendment No. 72, 42 1404
?95
ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The Plant Review Board shall maintain written minutes'of each meeting and copies shall be provided to the Executive Vice President and Chairman of the Nuclear Operations Board.
6.5.2 NUCLEAR OPERATIONS BOARD (NOB)
FUNCTION 6.5.2.1 The Nuclear Operations 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 d.
metallurgy e.
instrumentation and control f.
radiological safety mechanical and electrical engineering g.
h.
quality assurance practices i404
).96 TROJAN-UNIT 1 6-8 Amendment No. 12
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The N0B shall be composed of the:
Chairman:
Assistant Vice President, Thermal Plant Operation and Maintenance Member:
Designated Mechanical Engineer, Generation i
Engineering Member:
Designated Electrical Engineer, Generation Engineering Member:
Designated Nuclear Engineer, Generation Licensing and Analysis Member:
Manager of Nuclear Projects Quality Assurance Member:
Manager of Environmental Services Member:
Designated Representative of the Office of Environmental and Analytical Services Member:
Environmental Services Health Physicist.
Designated members shall be appointed in writing by the Executive Vice President.
Designated members (and alternates) shall have an academic degree in an engineering or science field and in addition shall have a minimum of 5 years technical experience of which a minimum of 3 years shall be in one or more areas given above.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the Executive Vice President to serve on a temporary basis; however, no more than two alternates shall participate as voting members in N0B activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the N0B Chairman to provide expert advice to the N0B.
MEETING FRE00ENCY 6.5.2.5 The N0B shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
i404
.?97 OUORUM 6.5.2.6 A quorum of N0B shall consist of the Chairman or his designated alternate and at least three members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the facility.
TROJAN-UNIT 1 6-9 Amendment No. JZ, 42
ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The N08 shall review:
The safety evaluations for 1) changes to procedures, equipment a.
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.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
ln Proposed tests or experiments which involve an unreviewed c.
safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or licenses.
Violations of applicable statutes, codes, regulations, orders, e.
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.
REPORTABLE OCCURRENCES requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the g.
Commission.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
i.
Reports and meetings minutes of the Plant Review Board.
1404
!98 TROJAN-UNIT 1 6-10
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The facility shall be placed in at least HOT STANDBY within a.
one hour.
b.
The Safety Limit violation shall be reported to the Commission, the Executive.Vice President and to the NOB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety Limit Violation Report shall be prepared.
The report c.
shall be reviewed by the PRB. 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 oubnitted to the Commission, the NOB and the Executive Vice President within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of a.
Regulatory Guide 1.33, November,1972.
b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Security Plan implementation.
Radiological Emergency Response Plan implementation.
e.
f.
Fire Protection Program implementation.
P 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRB and approved by the General Manager prior to ;mplementation and reviewed periodically as set forth in adminstrative procedures.
1404 299 TROJAN-UNIT 1 6-13 Amendment No. 72, 78, 33, 42 l'e
ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PRB and approved by the General Manager within 14 days of implementation.
6.9 REPORTING REOUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In additic to the applicable reporting requirements of Title 10, Code of Federal R gulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement'unless othemise noted.
STARTUP REPORT 6.9.1.1 A sumary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendrr.cnt to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have.significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other comitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or comencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup.. test program, and resumption or commencement of commerical TROJAN-UNIT 1 6-14 Amendment No. JE, gJ, 4 1404 500
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