ML20212R307

Amend 128 to License NPF-1,changing Tech Specs by Redefining & Clarifying Review Responsibilities of Plant Review Board & Plant General Manager

ML20212R307
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/09/1987
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212R302	List: ML20212R300 ML20212R307 ML20212R319
References
NUDOCS 8704270094
Download: ML20212R307 (12)

Text

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f A s.c.( / g UNITED STATES NUCLEAR REGULATORY COMMISSION

' E. ' j WASHINGTON. D. C. 20555 5

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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC P0k'ER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No. NPF-1

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

A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated September 13, 1985, as superseded and H vised August 7, and December 31, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the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 Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health ar.d safety of the public, and (ii) that such activities will be conducted in complicace 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.

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1 8704270094 870409 4 DR ADOCK 0500 e

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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 Sper.ifications contained in Appendices A and B, as revised through Amer.dment No.128 , are hereby-incorporated in the license. The 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 REGULATORY COMMISSION ar_ ,

PWR Project Direct ibte No. 3 Division of PWR Lic ing-A, NRR

Attachment:

Changes to the Technic 61 g

Specifications

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Date of Issuance: April 9, 1987

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ATTACHMENT TO LICENSE AMENDMENT N0.128 TO FACILITY CPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages Insert Pages TS 6-6 TS 6-6 6-7 6-7 6-12 6-12

--- 6-12a 6-13 6-13 6-14 6-14 6-14a 6-14a

{ N 6-15 6-15 6-15a 6-156 i

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

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

OUORUM 6.5.1.5 A quorum of the PRB shall consist of the Chairman or his I 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,

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.

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. 47, 128

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 of the safety significance of each violation,

f. Review of all REPORTABLE OCCURRENCES.

g. Review of facility operations to detect potential safety hazards. .

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 and 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 k 6.5.1.7 The Plant Review Board shall: .

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

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above l 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.

Amendment No. f2, 52, $6, 97, 99, 128 TROJAN-UNIT 1 6-7

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ADMINISTRATIVE CONTROLS i

RECORDS l

6.5.2.10 Records of TNOB activities shall be prepared, approved and 1 distributed as indicated below:

a. Minutes of each TN08 meeting shall be prepared, approved and forwarded to the Vice President Nuclear within 14 days l' following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President Nuclear within 14 days following completion of I the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President Nuclear and to the manage-ment positions responsible for the areas audited within L

1 30 days after completion of the audit. ,

I 6.5.3 TECHNICAL REVIEW AND CONTROL

ACTIVITIES i 6.5.3.1 Activities which affeet nuclear safety shall be conducted as l follows:

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a. Proceaures regrired by Specifitation 6.8.1 and other procedurcs I which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure o proce- .

dure change shall be reviewed by a qualified individual other l than the individual who prepared the procedure or procedure i

change, but who may be from the same organization as the l individual who prepared the procedure or procedure change.

Procedures shall be approved by the appropriate Responsible 4

Manager as designated in writing by the General Manager, Trojan I

Nuclear Plant. The General Man.ger, Trojan, shall approve Administrative Procedures, Security Plan implementing procedures I

and Radiological Emergency Response Plan implementing procedures.

b. Proposed changes or modifications to plant nuclear safety-related I

j structures, systems and components shall be reviewed oy a quali-fied individual / group other than the individual / group which designed the modification, but who may be from the same organiza-I tion as the individual / group which designed the modifications.

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Proposed modifications to plant nuclear safety-related I

structures, systems and components shall be approvea prior to

' implementation by the General Manager, Trojan Nuclear Plant.

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i i 6-12 Amendment No. JS, 52,97,128 l TROJAN-UNIT 1 i

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ADMINISTRATIVE CONTROLS

c. Procedures for proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications shall be prepared, reviewed, and approved. Each such test or experiment shall be reviewed by a qualified individual other than the individual who prepared the procedures for the proposed test or experiment. Procedures for proposed test and experiments shall be approved before implementation.

d. Individuals responsible for reviews performed in accordance with Specifications 6.5.3.la., 6.5.3.lb., and 6.5.3.lc., shall be members of the groups designated by approved written procedures.

Each such review shall be performed by qualified personnel of the appropriate discipline.

e. Each review shall include determination of whether or not an unreviewed safety question is involved. Pursuant to Sec-tion 50.59, 10 CFR, NRC approval of items involving unreviewed safety questions shall be obtained prior to the General Manager, Trojan Nuclear Plant, approval for implementation.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission siioil oe notified and a report submitted g pursuant to the requirements of Section 50.73 of 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PRB. The results of this review shall be submitted to the Vice President Nuclear and the TNOB.

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TROJAN-UNIT 1 6-12a Amendment No. 128

ADMINISTRATIVE CONTROLS _

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be ple:sd in at least HOT STANDBY within one hour.

b. The Safety Limit violation shall be reported to the Commission, the Vice President Nuclear and to the TN08 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 PRB. This report shall 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 PROGRAMS 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities ref erenced below:

i I a. The applicable proteoures recommended in Appendix "A" of I 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.

g. 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, including temporary changes, shall be reviewed and approved prior to implementation as set forth in Specification 6.5.3.

l 6-13 Amendment No. 42, 52, 97, 97, 706, TROJAN-UNIT 1

. 128

ADMINISTRATIVE CONTROLS 6 '

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, 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 i reviewed and approved in accordance with the Nuclear Projects 4 Quality Assurance Program for Operations.

, 6.8.4 The following programs shall be established, implemented, and 4 maintained:

a. Primary Coolant Sources Outside Containment i A program to reduce leakage from systems outside Containment that j would or could contain highly radioactive fluids during a serious 7

transient or accident to as low as practical levels. This program i shall include the followina:

fI (i) Provisions establishing preventive maintenance and periodic i

visual inspection requirements, and I

(ii) Leak test surveillance requirements for each system at

refueling cycle intervals (18 months).

j b. In-Plant Radiation Monitorino

! .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:

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

c. Secondarv Water Chemistry 1

i A secondary water chemistry monitoring program to inhibit steam

generator tube degradation. This program shall include

l (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.

I 1RO.1AN-UNIT 1 6-14 Amendment No. 75, 27, 42, 97, if, 70f 128

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l ADMINISTRATIVE CONTROLS (iii)

Identification of the various sampling points. *

(iv) Procedures for recording and management of data.

(v) Procedures defining corrective actions for off control point chemistry conditions.

(vi) A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of the administrative events required to initiate corrective action,

d. Post-Accident Samplino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and Containment atmosphere samples under accident conditions. The program shall include the following:

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

6.8.5 Procedures for radiological environmental monitoring shall be approved and implemented in accordance with the PGE Nuclear Quality Assurance Program.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be subinitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a dif ferent 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 predications and specifica-tions. Any corrective actions that were required to obtain satisfactory 6-14a Amendment No. 78, 27, #2, 97, 99, 70 TROlAN-UNil 1 128

ADMINISTRATIVE CONTROLS operation shall also be described. Any additional specific detiils required in license conditions based on other commitments 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 commencement of commercial 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 commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure ,

according to work and job f unctions *, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, specisi . air.tcr.ar.cc (describe maintenance), waste processing, and g refueling. The dose assessment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measure- ~

ments. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

c. Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was

-! exceeded and results of one analysis after the radiciodine l

activity was reduced to less than limit. Each result should i

include date and time of sampling and the radioiodine concentra-I tions; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to 6-15 Amendment No. 27, 97, ff, 796, 777 1ROJAN-UNil 1 128 l

ADMINISTRATIVE CONTROLS the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration l in microcuries per gram as a function of time for the duration of 1 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 Monitoring Reports shall include r suiTnarized arid uto* ulated results in the format of laDie b.9-1 of all

!$ radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the

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report, the report shall be submitted noting and explaining the reasons 1 for the missing results. The missing data shall be submitted as soon as 4

possible in a supplementary report, i The reports shall also include the following: a summary description of f the Radiological Environmental Monitoring Program including sampling j methods for each sample type, size and physical characteristics of each

! sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a

table giving distances and directions from one reactor; the result of

! land use censuses required by the Specification 3.12.2; and the results j of licensee participation in the Interlaboratory CompaHsons Program required by Specification 3.12.3.

j 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 f submitted within 60 days after January 1 and July 1 of each other.

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TROJAN-UNil 1 6-15a Amendment No. 59,/MS, 128 f

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