ML20210B624

Proposed Tech Specs Revising Typos & Clarifying Appropriate Process to Be Used for Review & Approval of Temporary Changes to Procedures.Certificate of Svc Encl

ML20210B624
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/29/1987
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20210B587	List: ML20210B580 ML20210B624 ML20210C633
References
TAC-65203, NUDOCS 8705050369
Download: ML20210B624 (6)

Text

.

, ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The Plant Review Board shall be composed'of the:

Chcirman: Manager, Technical Services Member: Engineering Supervisor I 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 PR8 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.

QUORUM 6.5.1.5 A quorum of the PRB shall consist of the Chairman or his l 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. #2, 128 87050500hb9 B70429 PDR ADOCK 05000344 P PDR

ADMINISTRATIVE CONTROLS

e. Investigation of all violations of the-Technical Specifications including the preparation and forwarding lof 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 EVENTS.

d

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.

4

1. 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.

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

l 1 i 4

a d

i TROJAN-UNIT 1 6-7 Amendment No. #2, 52,-~ 88, 97, 99,128 1

l

.,,*e . - - - , - - - - - = = e ,vwn e.,W -- - - , ==1, w - p -m--

nx = - - -

[l

~

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT-VIOLATION 6.7.1 The following actions shall-be taken in the event a_. Safety Limit -t 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 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 shal1 be prepared. The repcrt.shall be reviewed by the PR8. 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. l

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 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 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.

TROJAN-UNIT 1 6-13 Amendment No. #2, 52, 97, if, 188, 728

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 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 Staf f, 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 maintained:

a. Primary Coolant Sources Outside Containment l A program to reduce leakage from systems outside Containment that l would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following: l (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).

b. In-Plant Radiation Monitoring 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, (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 quantifi-cation of parameters that are critical to control points.

TROJAN-UNIT 1 6-14 Amendment No. 78, 27, #2, 97, 99, 796 128 April 9, 1987

'=.*s'

=,.

ADMINISTRATIVE CONTROLS-the first sample in which the limit was exceeded;-(4) Graph of the I-131 concentration and one other radiciodine 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 effects 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.

summarized and tabulated results in the format of Table 6.9-1 of all ,

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

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-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 of licensee participation in the Interlaboratory Comparisons Program required by Specification 3.12.3.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT I

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 after January 1 and July 1 of each year.

l l

TROJAN-UNIT 1 6-15a Amendment No. 99, 778, 128 l l

_ -j

....q W e ,

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION l

(

In the Matter of ) I

) l PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY )

)

(TROJAN NUCLEAR PLANT) )

CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 156 to the Operating License for Trojan Nuclear Plant, dated April 29, 1987, have

, been served on the following by hand delivery or by deposit in the United States mail, first class, this 29th day of April 1986:

{

Mr. David Kish, Director l State of Oregon l Department of Energy 625 Marion St NE I Salem OR 97310 I Mr. Michael J. Sykes Chairman of County Commissioners

• Columbia County Courthouse I

St. Helens OR 97051

, u- - _ _

"GI Zimmerman, Manager Nuc ca'r Regulation Branch Nucl a Safety & Regulation l

]

Subscribed and sworn to before me this 29th day of April 1986.

1 Notary Public of Oreg6n-My Commission Expires: M[ #

M 1

i .

____ . ]