ML20036A746
| ML20036A746 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/06/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036A745 | List: |
| References | |
| NUDOCS 9305140110 | |
| Download: ML20036A746 (9) | |
Text
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE. OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.191 License No. NPF-1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Portland General Electric Company, et al. (PGE or licensee) dated January 27, 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 t:. < 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.
9305140110 930506 PDR ADOCK 05000344 P
2.
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 and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.191, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance. This amendment shall be fully implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION e
SeymburH. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1993
ATTACHMENT TO LICENSE AMENDMENT NO.191
(
FACILITY OPERATING LICENSE NO. NPF-1 DOCKET N0. 50-344 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.
Remove Insert 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-14 6-14 i
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t ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The Facility organization shall be subject to the following:
{
a.
Each on duty sh;ft shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
l b.
At least one individual qualified to stand watch in the control room (non-certified operator or a certified fuel handler) shall be in the control room when fuel is in the spent fuel pool.
c.
(deleted) l d.
An individual qualified in radiation protection procedures shall be onsite during fuel handling operations.
All fuel handling operations shall be directly supervised by a e.
certified fuel handler.
f.
A Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the certified fuel handler on shift or any personnel required for other essential func-tions during a fire emergency.
Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 d
hours in order to accommodate unexpected absences of onduty members provided immediate action is taken to restore the Fire Brigade composition to within the minimum requirement of 5.
i g.
Adminis.trative procedures shall be developed and implemented to limit the working hours of shift personnel who perform functions important t
to the safe storage of irradiated fuel assemblies (i.e., certified fuel handlers, radiation protection personnel, non-certified operators), and key maintenance personnel of the unit staff.
Key maintenance personnel of the unit staff are those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of structures, systems or components important to the safe storage of irradiated fuel assemblies, and who i
are personnel performing or immediately supervising the performance of such activities. This applies to key maintenance personnel whether on shift or not.
Adequate shift coverage shall be maintained without routine heavy use of overtime. The baseline for determining overtime use will' be a 40-hour work week. However, in the event that unforeseen problems TROJAN-UNIT 1 6-2 Amendment No. 181, 187
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191 wnw
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require substantial amounts of overtime to be used, or during major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
a.
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.
b.
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 48-hour 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 seven day period, all excluding shift turnover time.
c.
A break of at least eight hours should be allowed between work periods, including shift turnover time.
d.
The use of overtime should be considered on an individual basis l
and not for the entire staff on a shift.
Any deviation from the above guidelines must be authorized by the Plant General Manager or, in his absence, Duty Plant Manager, or higher levels of management, in accordance with established proce-dures and with documentation of the basis for granting the deviation.
Routine deviation from the above guidelines is not authorized.
h.
The Shift Manager shall be a certified fuel handler.
An operator holding a license as a Senior Reactor Operator in accordance with 10 CFR 55 is a certified fuel handler.
TROJAN-UNIT 1 6-3 Amendment No. W 191 5 06 1993
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
Position Number for Permanently Defueled Mode Shift Manager 1
Non-Certified Operator 1
Total 2
- Shift 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 immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming crewman being late or absent.
i i
2 TROJAN-UNIT I 6-4 Amendment No. 50, 56, 66, 100, 191 Vll 9: ":
A_DMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Rev. 2, April 1987.
6.4 TRAINING 6.4.1 A NRC-approved retraining and replacement training program for the certified fuel handlers shall be maintained under the direction of a General Manager.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of a General Manager and shall meet or exceed the requirements of Section 27 of 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 Plant General Manager on all matters related to nuclear safety.
l TROJAN-UNIT 1 6-5 Amend.aent No. 48, 31, 42, 56, 446, 149, 445, 4M,181, -4M 191 U.S 00 93J
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The PRB shall be composed of six designated members, including the Chairman. Members and the Chairman shall be designated in writing by the Plant General Manager.
The members shall represent plant engineering, operations, maintenance, radiation protection / health physics and quality assurance.
The Chairman shall have an academic degree in an engineering or science field or equivalent, and, in addition, shall have 10 years of power plant experience of which 3 years shall be nuclear power plant experience.
The other members (and any alternates) shall have an academic degree in an engineering or science field or equivalent 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 of the areas listed above. Members without an applicable academic degree shall have a mini-mum of 10 years technical experience, of which a minimum of 3 years shall be in one or more of the areas listed above.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the Plant General Manager to serve on a temporary basis; however, no more than two alter-nates shall participate as voting members in PRB activities at any one time.
I MEETING FRE0VENCY i
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.
l OUORUM l
6.5.1.5 A quorum of the PRB shall consist of the Chairman or his designated alternate and at least four members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Review Board shall be responsible for:
a.
Review of the safety evaluations for:
(1) procedures, (2) change to procedures, equipment, systems or facilities, and (3) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
i b.
Review of proposed procedures and changes to procedures, equipment, systems or facilities which may involve an unreviewed safety question as defined in 10 CFR 50.59 or involves a change in -Technical Specifications.
TROJAN-UNIT 1 6-6 Amendment No. 42, 448, 445, 440, 447 191
- p. t n m e, v v n;
ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 may be made provided:
a.
The intent of the original procedure is not altered.
b.
For procedures covering activities performed by the Facility Staff, I
the change is approved by two members of the Plant Management Staff, at least one of whom is a certified fuel handler, and the change is documented, reviewed, and approved by the Responsible Manager within fourteen (14) days of implementation.
c.
For procedures covering activities performed by Company organizations other than the facility Staff, the change is reviewed and approved in accordance with the Nuclear Quality Assurance Program.
l 6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from systems outside Containment that would or could contain highly radioactive fluids during a serious j
transient or accident to as low as practical-levels.
This program i
shall include the following:
(i)
Provisions establishing preventive maintenance and periodic l
visual inspection requirements, and (ii)
Leak test surveillance requirements for each system at refueling cycle intervals (18 months).
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:
(i) Training of personnel, I
(ii)
Procedures for monitoring, and (iii)
Provisions for maintenance of sampling and analysis equipment. -
c.
Secondary Water Chemistry A secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
(i) A sample schedule and control points for critical parameters.
(ii) Use of commonly accepted industrial procedures for quantifica-tion of parameters that are critical to control points.
j TROJAN-UNIT 1 6-14 Amendment No. M, 24, 42, 97, 99, MO, +24, MS 191
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