ML20135F050

Proposed Changes to Tech Spec 6.8,reflecting More Efficient Review & Approval of Facility Procedures

ML20135F050
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/13/1985
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20135F014	List: ML20135F012 ML20135F039 ML20135F050
References
TAC-60020, NUDOCS 8509170136
Download: ML20135F050 (7)

Text

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LCA 130 Attachment A

- Page 1 of 7 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 6.4.1.4 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 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:

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a. Review of all proposed tests and experiments that affect nuclear safety.

8509170136 850913 PDR ADOCK 05000344 P PDR TROJAN-UNIT 1 6-6 l

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LCA 130 Attachment A Page 2 of 7 ADMINISTRATIVE CONTRGLS

b. Review of all proposed changes to Appendix "A" Technical Specifications,

c. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

d. 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,

e. 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.

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

g. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Trojan '

Nuclear Operations Board.

h. Review of the Plant Security Plan and implementing procedures.

i. Review of the Emergency Plan and implementing procedures.

j. Review of the Offsite Dose Calculation Mar.ual.

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

AUTHORITY 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 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.

TROJAN-UNIT 1 6-7 l

LCA 130 Attachment A Page 3 of 7 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 placed 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 TN0B 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 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.

g. Offsite Dose Calculation Manual implementation.

h. Radiological Effluent Program implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation and reviewed periodically as set forth in Administrative Procedures as follows:

TROJAN-UNIT 1 6-13 Amendment No. #2, 52, 97, if, ISS

LCA 130 Attachment A

- Page 4 of 7 ADMINISTRATIVE CONTROLS

a. For those procedures and Administrative policies covering activities performed by the Facility Staff, review and approval shall be by the Plant General Manager; or by (1) the Manager of Operations and Maintenance, (2) the Manager of Technical Services, (3) the Manager of Plant Services, or (4) the Manager of Plant Modifications.

b. For those procedures and Administrative policies covering activities performed by Company organizations other than the Facility Staff, review and approval shall be in accordance with the Nuclear Quality Assurance Program.

TROJAN-UNIT 1 6-13a 3

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LCA 130 Attachment A '

- Page 5 of 7  ;

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, 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 af fected, and the change is documented by the Responsible Manager within thirty (30) days of implementation.

c. For procedures covering activities performed by Company organizations other than the Facility Staf f, the change is reviewed and approved:in accordance with the Nuclear Projects Quality Assurance Program for Operations.

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

a. Primary Coolant Sources Outside Containment l' A program to reduce leakage from systems outside Containment that ,

would or could contain highly radioactive fluids during a serious i transient or accident to as low as practical levels. This program shall include the following:

(i) Provisions establishing preventive maintenance and periodic visual inspection requirements, and (ii) Leak test surveillance requirements for each system at refueling cycle intervals (18 months).

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b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine I 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 i

(iii) Provisions for maintenance of sampling and analysis equipment. ,

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c. Secondary Water Chemistry '

A secondary water chemistry monitoring program to inhibit steam i generator tube degradation. This program shall include: l i

(i) A sample schedule anfi control points for critical parameters.

(ii) Use of commonly accepted industrial procedures for quantifi- j cation of parameters that are critical to control points. l l

TROJAN-UNIT 1 6-14 Amendment No. 78, 27, #2, 97, if, 198

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LCA 130 Attachment A Page 6 of 7 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 i

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 sunnary report of plant startup and power escalation testing shall be submitted 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 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 predications and specifica-tions. Any corrective actions that were required to obtain satisfactory TROJAN-UNIT 1 6-14a Amendment No. 78, 27, #2, 97, 99, 798

LCA 130 Attachment A Page 7 of 7 ADMINISTRATIVE CONTROLS operation shall also be described. Any additional specific details 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 functions *, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and 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.

TROJAN-UNIT 1 6-15 Amendment No. 27, 97, 99, 198

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