ML20235V607

Amend 135 to License NPF-1,revising Tech Spec Section 6 Re Review & Approval of Temporary Changes to Procedures & Correcting Typos

ML20235V607
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/02/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235V600	List: ML20235V596 ML20235V607 ML20235V612
References
NUDOCS 8710150235
Download: ML20235V607 (8)

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1. 'o,, UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION g j WA5mNGTON, D. C. 20556

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PORT. LAND 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. 135 License No. NPF-1

1. The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Portland General Electric Company, e_t al. (thelicensee)datedApril 29, 1987 complies with the staiidar,ds 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; i i

B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; 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 l conducted in compliance with the Comission'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; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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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 The Technical Specifications contained in Appendices A q

and B, as revised through Amendment No.135, are hereby incorporated in the license. %e licensee shall operate '

- the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

3.

This license amendment is effective as of the date of its issuance. '

FOR THE NUCLEAR REGULA ORY COMMISSION

, Au

' George Knighton., rector Project Directora Division of Reactor Projects ~ III, IV, V and Special Projects  !

Attachment:

Changes to the Technical

' Specifications 4

Date of Issuance: October 2, 1987 j

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October 2, 1987' ATTACHMENT TO LICENSE AMENDVENT N0. 135 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages 6-6 6-6 6-7 6-7 6-13 6-13 6-14 6-14 6-15a 6-15a '

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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 one time. shall participate as voting members in PRB activities at any ,

_ MEETING FRE0VENCY 6.4.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairnan or his designated alternate.

OUORUM 6.5.1.5 A quorum of the PRB shall consist of the Chairnen 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 question, such actions did not constitute an unreviewed safety b.

Review of proposed procedures and changes to procedures, '

equipment, systems or f acilities which may involve an unreviewed safety question as defined in 10 CFR 50.59 or involves a change in Technical Specifications.

c. Review of proposed test or experiments which may involve an unreviewed safety question as defined in 10 CFR 50.59 or requires a change in Technical Specifications, d.

Review of proposed changes to Technical Specifications or the Operating License.

TROJAN-UNIT 1 6-6 Amendment No. #2, dgg , 135 October 2, 1987

ADMINISTRATIVE CONTROLS

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President Nuclear and to the Chairman of the Trojan Nuclear Operations Board. The investigation shall include an assessment i of the safety significance of each violation.

f. Review of all REPORTABLE EVENTS.

g. Review of facility operations to detect potential safety ha za rds .

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Trojan Nuclear Operations Board.

i. Review of the Plant Security Plan a7d implementing procedures.

J. Review of the Emergency Plan and implementing procedures.

k. Review of the Offsite Dose Calculation Manual.

1. Review of the Process Control Program for Solid Radioactive Waste.

AUTHORITY 6.5.1.7 The Plant Review Board shall:

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a. Recommend to the General Manager written approval or disapproval of items considered under 6.5.1.6(a) through (c) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above constitutes an unreviewed safety question.

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 Vice Presi-dent Nuclear and the Trojan Nuclear Operations Board of disagreement between the PRB and the General Manager; however, the General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

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TROJAN-UNil 1 6-7 Amendment No. #2 52.66,97,99,Idd I$5 October 2, 1987 1

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ADMINISTRATIVE CONTROLS

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l 67 1 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is vio'ated:

a. The facility shall be placed in at least HOT STAND 8Y within one hour.

b.

The Safety Limic violation shall be reported to the Commission, the Vice President Nuclear and to the TNOB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PR8. This report shall l

describe (1) applicable circumstances preceding the viola-tion, (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 TNOB and the Vice President Nuclear within 14 days of the violation.

6.8 PROCEDURES AND PROGRAMF 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972,

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Radiological Emergency Plan implementation,

f. Fire Protection Program implementation.

9 Offsite Dose Calculation Manual implementation,

h. Radiological effluent monitoring.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in Specification 6.5.3. l TROJAN-UN11 1 6-13 Amendment No. #2, 52, 97, 97, 708, 721 135 October 2,1987

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ADMINISTRATIVE CONTROLS-L..

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 Terformed by the Facility Staff, 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 Trojan, 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.

6.8.4 The following programs shall be established, implemented, and '

s maintained:

a .. Primary Coolant Sources Outside Containment A program to reduce leakage ~from systems outside_ Containment that would or could .contajn highly radioactive fluids during a serious transient or accident to as low as practical-levels. This ' program shall include the following:

(i) Provisions establishing preventive maintenance and perioo'ic

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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:

(1) Training of personnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.

c. Secondarv Water Chemistry I 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 quantifi-cation of parameters that are critical to control points.

TROJANJ' NIT 1 6-14 Amendment No. 78, 27, #2, 97, 99, 795

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ADMINISTRATIVE CONTROLS the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

6. 9 .1. 5.1 Routine Radiological Environmental Monitoring Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.1.5.2 The Annual Radiological Environmental Monitoring Reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the ,

report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses required by Specification 3.12.2. If harmful ef fects of evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Hositoring Reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In i the event that some results are not available for inclusion with the 1 report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program including sampling methods for each sample type, size and physical characteristics of each i sample type, sample preparation methods, analytical methods, and l measuring equipment used; a map of all sampling locations keyed to a 1 table giving distances and directions from one reactor; the result of land use censuses required by the Specification 3.12.2; and the results of licensee participation in the Interlaboratory Comparisons Program required by Specification 3.12.3.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.5.3 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be  !

submitted within 60 days af ter Januacy 1 and July 1 of each year.

l l TROJAN-UNIT 1 6-15a Amendment No. 99, 0 8, 778 , 135 Octuoer 2, 1987

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