ML20141K832

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Proposed Tech Specs for Proposed Change 7 to License DR-15
ML20141K832
Person / Time
Site: 05000231
Issue date: 10/08/1971
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20140G249 List: ... further results
References
FOIA-97-34 NUDOCS 9705300172
Download: ML20141K832 (15)
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Text

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!- Section 6 l I .

. ADMINISTRATIVE CONTROLS -

l 6.1 Organization,' Review, and Audit ..

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l- This specification applies to the organization for management and for-review and audit of facility operations. Its obj ective is. to delineate responsibility for management of the facility, to assure maintenance of l a high level of staff competence, and to specify an independent program for review and audit of facility operation.

A. Organization l- 1. The organization for management, operation, and audit of SEFOR facility operations shall be as given in Figure 6-1. The over-all full-time responsibility for operation of the SEFOR facility and compliance with these Technical Specifications shall reside in the SEFOR racill;, Site Manager. The Site Manager reports to l

the Manager, SEFOR, who in turn is responsible dir'ectly to the l

BRDO General Manager. The BRDO General Managtr reports to the Nuclear Energy Division General Manager.' As indicated in l Figure 6-1, technical engineering assistance will be provided as necessary through the BRDO Manager of Maui Engiuw ing, end Prejects Design Engineering.

l 2. The minimum functional organization required for operation of j the facility shall be as follows: *

a. An operating shift shall consist of a shift supervisor and at least three additional operators. At least one of the l operators shall be licensed.

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b. When the reactor is secured, a licensed reactor operator l

and two additional persons trained in carrying out emer-gency procedures shall be at the site,

c. A shift supec.1:?r shall be in charge of startup, approach to power, normal operation, recovery from unplanned or unscheduled reductions in power, shutdown, handling or transferring of materials in the reactor vessel, and dur-inA any handling operations within the refueling cell when the reactor vessel head or ports have been removed.

6.1-1 9705300172 970505 pr posed Change No. 7 PDR FOIA October 8, 1971 PDR i

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-fff E 6.1-2 Proposed Change No. 7 October 8,-1971

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d. Personnel requiring Part 55 1icenses shall be as indicated in Figure 6-1.
3. Qudlifications with regard to education and operating experience for key supervisory personnel shall be as follows:
a. Manager, SEFOR ,

B.S. in Engineering or Science, or equivalent in experience.

Five years experience in the management or supervision of the design, construction, installation, operation, development and maintenance of nuclear facilities.

General knowledge of related technical fields, including reactor physics, radiological hazards control, instrumenta-tion and nuclear engineering.

Familiarity with license and Technical S'pecifications, AEC reporting requirements, and Quality Assurance program for SEFOR.

l b.e. GEFelt "ocility Manager, SEFOR Site B.S. in Engineering or Science or equivalent in experience.

Seven years experience in the design, construction, instal-lation, operation, development, and maintenance of nuclear facilities. -

Demonstrated detailed and comprehensive knowledge in related technical ficids, including reactor physics, radiological hazards control, nuclear engineering and instrument engineer-ing.

Five years experience, or one year experience at SEFOR plus two years experience elsewhere, in the supervision and management of the construction and operation of reactor facilities. Demonstrated ability to plan, organize, and direct reactor plant operations.

c.b. Manager, Plant Engineering B.S. in Engineering or Science, or equivalent in experience.

Five years experience or equivalent in the operation and j maintenance of power-generation facilities, including a minimum of one year in responsible supervisory positions in the operation or maintenance of such facilities, and one year of nuclear plant experience. Ability to plan, program, and direct activities of engineering and craft personnel.

6.1-3 Proposed Change No. 7 October 8, 1971 I

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Demonstrated ability in the design and application of equip-ment and devices, with a thorough understanding of process

' equipment such as pumps, fans, heat exchangers and genera-a tors, heaters, etc., as app,11 cable to nuclear facilities.

d.e. Fbnager., Operations .

B.S. in Engineering or Science or equivalent in experience.

Five years experience in the operation and maintenance of reactor or nuclear power facilities, including minimum of one year in supervisory positions in the operation and maintenance of such facilities.

j Demonstrated ability to organize and coordinate plant opera-l tions. Comprehensive knowledge of problems associated with

! startup and initial operation of reactor facilities, includ-ing knowledge of radiological hazards, technica1' aspects of i i

l' reactor operation of control systems, radiation shielding, 1.

l contanination control, etc. Demonstrated good judgment l i

necessary to make correct decisions under rapidly changing conditions. Licensed as a Senior Reactor Operator, c.d. . Manager, Procrams and Analysis B.S. in Engineering or Science or equivalent in experience.

l Five years experience in the design, operation, analysis and.

programming of a variety of reactor types or nuclear power J l

l facilities, including at least one year in responsible super-visory position in such organizations. l Comprehensive knowledge of reactor physics, reactor design, reactor operation, radiation shielding, fluid flow, thermo-dynamics, instrumentation, and related technologies.

Demonstrated capability for directing the efforts of physi-cists and engineers.

Ability to develop techniques and test procedures to carry

l. out a reactor experimental program.

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Demonstrated knowledge of the practical aspects of the i operation of reactors, including their characteristics,

limitations, and safe operating requirements.  ;

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! Proposed Change No. 7

! October 8, 1971

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. f.e. Specialist. Radiation and Industrial Safety B.S.'in Engineering or Science or equivalent in experience. ,

' Three years. experience in analytical chemistry or radio-

.. chemistry and health physics, including one year of exper-

l. ience in radiation protection. -

' Demonstrated ability in evaluation of radiation hazards, design and development-of radiation monitoring equipment, and in conducting health-physics studies.

I Thorough understanding of radiation dosimetry and a working i knowledge of design of radiation facilities, shielding cal-l culations and design of ventilation control, radioactive waste processing, calibration of radiation measuring instru-mentation, maximum permissible radiation exposure levels, and good radiological safety and health protection practices.

l Must be cognizant of local and state industrial safety re-

! quirements. Demonstrated ability in teaching, lecturing, l l and implementing safe practices and procedures.

l g.f. Supervisor, Mechanical Maintenance B.S. in Engineering or Science, or equivalent in experience l

l' with a high' school education and apprenticeship training.  !

l Five years of experience with power generating equipment, including oce' year of nuclear experience and one year of

experience as a supervisor in the maintenance of associated equipment for reactors or power generating equipment.

Familiarity with~non-destructive testing, and understanding of pressure vessel and piping codes.

Knowledge of craft techniques and mechanical maintenance-procedures applicable to nuclear facilities.

Cognizance of radiation and safety procedures and regulations, as applicable to nuclear facilities.

h .g.~ Instrumentation Engineer

B.S. in Engineering or Science, or equivalent in experience.

Three years experience in design, installation, calibration f and maintenance of process instrumentation, including a 4

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. minimum of one year of nuclear instrumentation experience I and an understahding of electrical codes. Cognizance of' j significance of control and instrumentation systems with respect to reactor operation and safety. Demonstrated j

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- ability to analyze systems for adequacy to meet system -

l requirements and to conceive, assemble,'and install neces-sary modifications to meet systems requirements.

l 1.h. Shift Supervisor B.S. in Engineering or Science, or equivalent in experience.

l Three years experience in the operation of reactor or nuclear i

facilities.

Knowledge of reactor startup methods and procedures, includ-ing radiological hazards and their control, plant maintenance,

modern physics and other technical aspects of reactor facil-ities. Ability to plan, coordinate, and direct the efforts of operations personnel as. indicated by previous supervisory experience or satisfactory progression in job positions.

Licensed as a Senior Reactor Operator.

B. Review and Audit Organizational units for the review and audit of plant operations shall be constituted and have the responsibilities and authorities outlined below:

1. SEFOR Site Safety Committee
a. Membership Chairman: Tacility Site Manager or designated alternate. )

Manager, Operations or designated alternate. l Manager, Plant Engineering or designated alternate.

Manager, Program and Analysis or designated alternate.

Specialist, Radiation and Industrial Safety or designated alternate.

b. Meeting Frequency At least every two weeks and more often as deemed neces-l sary by the Chairman.

i l c. Ouorum f Chairman or his designated alternate, plus two other members.

6.1-6 Proposed Change No. 7 October 8, 1971 l

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, d. Responsibilities l

(1) Review all' proposed normal, abnormal,. emergency pro- j cedures, and procedures for maintenance which are significant to reactor. safety and proposed changes to I l

-these procedures. .

j l (2) Review all proposed tests for the planned experimental )i program, and plant tests which may have significance '

to reactor safety. l (3) Review proposed changes to Technical Specifications.

i (4) Review proposed changes and modifications to plant l systems or equipment which would require a change in, or would be covered by procedures in d(1) above.

j. (5) Review plant operation to detect potential safety

-hazards l (6) Review reported violations of Technical Specifications.

l (7) Perform special reviews and investigations and make recommendations thereon as requested by the SEFO'R racility Site Manager.  ;

l. (8) Report to the ra00-Gm.e.al Manager SEFOR and to the I l Chairman of the SEFOR Safety Review Committee on all  ;

i reviews and investigation conducted under items d(6) and d(7) above.

l (9) Make tentative determinations regarding whether propo-sals considered by the committee involve unreviewed j safety questions in accordance with 10 CFR 5'0.59 and recommend the necessary actions or safety analyses to the rocilit., Site Manager.

e. Authority
(1) The SEFOR Site Safety Committee shall be advisory to the recility Site Manager.

(2) The SEFOR Site Safety Committee shall review and recom-l_ mend to the rocility Site Manager approval or disapproval

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[. of proposals under items d(1) through d(5) above.

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a. In the event of disagreement between the recommenda-tions of the SEFOR Site Safety Committee and actions 6.1-7 l Proposed Change No. 7 October 8, 1971 t

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contemplated by the Focility Site Manager on

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safety matters, the decision and action to be taken t

shall be the respo'nsibility of the Teeility Site g Manager.

f.. Records Minutes shall be kept for all meetings of the SEFOR Site Safety Coc ttee. Copies of the minutes shall be forwarded to the titBO-Ce..esel Manager, SEFOR, the Chairman of the SEFOR Safety Review Committee, and to the Manager, Sefaguards Safety and Anal,eie Licensing.

'g. Procedures Committee rules and regulations shall be. prepared and main-tained describing the function of the committee, its meeting schedule, methods for review and approval of evaluations and i

recommendations, or designation of meetings and such other f

l matters as may be appropriate.

2. SEFOR Safety Review Committee
a. Membership (1) Chairman plus five members appointed by the BRDO General Manager.

(2) Manager, Nuclear Safety Appraisal Operation, Nucicar Energy Division, ex-officio member in addition to the appointees in (1) above.

(3) Technical consultants as deemed necessary by 'the BRDO General Manager.

(4) Members of the SEFOR Temility Site Operation (Figure 6-1) shall not serve as members of the Safety Review Committee.

(5) Qualifications of the Safety Review Committee with regard to the combined ~ experience and technical specialties of the individual members shall be maintained at a high level. The Committee as a whole shall have competence in nuclear reactor technology encompassing the basic disciplines of chemistry, physics, engineering, and also safety and health physics. The minimum qualifications 6.1-8 Proposed Change No. 7 October S, 1971 e

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for membership of this Committee shall be determined by the BRDO General Fbnager. The membership of this 1

t Committee shall be selected by the BRDO General Manager I

. 1 with the advice and co.ncurrence of the Manager, Nuclear Safety Appraisal Operation, Nuclear Energy Division. . I The performance of this committee shall be reviewed periodically by both the BRDO General Manager and the Manager, Nuclear Safety Appraisal Operation. Deteriora-tion in its performance shall be avoided by replacement of individuals or a reconstitution of the committee, if l 1

necessary, at the discretion of the BRDO General Mana-ger. Replacement shall be made from the manpower resources of the General Electric C'mpany o as a whole.

b. Meeting Frequency Semi-annually and as required on call of the Chairnan or the i BRDO Ceneral Manager. During the first year of operation, the committee shall meet at least three times.
c. Quorum Chairman or his delegated alternate plus three members.
d. Responsibilities (1) Review proposed changes to the Operating License, including Technical Specifications.

(2) Review matters including proposed changes or modifica-tions to plant systems or equipment as referred to it by the SEFOR Site Safety Committee or by the Tomility Site Manager and review decisions with regard to unre-viewed safety questions.

(3) Audit proposed changes to procedures, tests, experiments, and review those changes which may have safety signifi-cance.

(4) Review reports, minutes, and results of audit inspect-l ions ane < elect for review specific items which may have I

safety implications.

(5) Conduct, or have conducted by a qualified group, audits of plant operation at least semi-annually to assure that emergency procedures are up-to-date and to assure compli-ance with Operating Procedures and Technical Specifications.

l 6.1-9 Proposed Change No. 7 October 8,1971

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r (6) Review reported instances of violations of Technical Specifications and recommend to the BRDO General

. Manager appropriate action to prevent recurrence of 1 i

I i the violations.

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, (7) Review instances of 'significant equipment malfunction's which a;2 of an unusual or 'inexpected type, and perform 1 other special reviews and investigations as requested by the'BRDO General Fbnager.

l l e. Authority l

l The function of the SEFOR Safety Review Committee shall be -!

advisory, and it shall report directly to the BRDO General Manager.

l f. Records ,

! A report on each meeting of the SEFOR Safety Review Commit-tee shall be prepared and forwarded to the BRDO General Manager and to such others as the Chairman or the BRDO General Manager may designate. This report shall contain i

j the findings and recommendations resulting from each meet-ing. The BRDO General Manager shall have documented, within a reasonable period following the receipt of the report, the actions taken on the recommendations. Copies of this respense j i

shall be forwarded to the Chairman and members of the SEFOR 1 i

l Safety Review Committee. j

g. Procedures Procedures for committee operation shall be established by
the Chairman of the committee and the BRDO General Manager. l The BRDO General Manager shall review periodically the per-formance of the committee to assure an independent and compre-hensive review of facility operation.

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Proposed Change No. 7 l October 8, 1971 4

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I 6.2' Plant Operating and Emergency Procedures i

A. ~ Detailed written procedu'res and instructions with check-off' lists,

, approv{d by the SEFOR'Tecility Site' Manager, shall be provided and )

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. used for the following conditions: "

1. Re'ueling and refueling cell operations, nornal startup, opera-f tion, and shutdown of the complete facility and of all systems j and components involving nuclear and radiological safety of the l facility. .

~2. All program tests and experiments.

3. Emergency conditions involving possible or actual releases of radioactive materials.

4'. Preventive or corrective operations that could have an effect on reactor safety or affect nuclear or radiological safety.

j B. Temporary operating procedures which do not decrease plant safety margins, may be used after review by the Manager, Program and Analy-sis, and approval by the Manager, Operations. Use of these procedures.

l shall be documented in the operating records, t

C. Modifications to experimental test procedures, which do not change j the original intent or add to the scope of the test, and which do not reduce safety margins may'be made with the approval of the Mana-t ger, Program and Analysis. Spch changes shall be documented in the operating records.

D. Provisional test procedures which are complementary to experimental test procedures or that are of a diagnostic nature, and do not reduce l plant safety margins, may be used after review by the Manager, Opera- j i

tions and approval by the Manager, Program and Analysis. Such pro-cedures shall be documented in the operating records.

E. Radiation control procedures shall be established and all station l

l personnel shall be instructed in these procedures. These procedures shall show the permissible radiation exposure levels and methods for control of radiation exposure.

l The radiation protection program shall be organized to meet the t

! requirements of 10 CFR 20 with the following exception:(1) f 3

6.2 Proposed Change No. 7 October 8, 1971 i

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. 1 Paragraph 20.203 - caution signs, labels and signals. In lieu

' ' of the " control device" or the " conspicuous visible or audibic

, alarm signal" spe'cified in paragraph 20.203 (c) (2), each High I

. Radiation Area in which the' intensity of radiation is 100 MREM /hr i

i or more shall be barricaded and physically posted as a High Radia-

. tion Area. Entrance thereto shall be controlled by requiring a  !

special work permit and any individual or group of individuals permitted to enter such an area shall be provided with a radia-tion monitoring device which continuously indicates the radiation f i

I dose in the area. l In addition to the above requirement, any high radiation area in which the intensity of radiation is greater than 1000 MREM /hr, shall be provided with locked doors to prevent entry into such areas by unauthorized personnel. The keys to these doors shall be kept under the administrative control of the shift supervisor l and the Manager, Operations..

F. Practice drills on Emergency Procedures shall be conducted prior to initial criticality and at least annually thereatter. Such drills shall include as a minimum, partial or complete evacuation of the I site and a test of the adequacy of communications with off-site support groups.

Reference (1) Letter to Dr. Peter A. Morris, U.S.A.E.C., Division of Reactor Licensing from Karl Cohen, BRDO, General Electric Company dated February 28, 1969.

l 6.2-2 Proposed Change No. 7 October 8, 1971

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6.3 Action to Be Taken in the Event of an Abnormal Occurrence A. LimitingSafetySystemdetting

1. If.a limiting safety system setting is violated without causing l g a reactor scram or other safety system action, the reactor shall

, be, shut down immediately, and the occurrence shall be reported- j promptly to the Manager, SEFOR recility Site.

2. A thorough investigation of the conditions related to the occur-j rence shall be made by the Site Safety Committee. The Committee l

shall prepare a report for each such occurrence, including an 1 1

evaluation of the cause of the occurrence and recommendations I

'for appropriate actions to prevent or reduce the probability of recurrence. Copies of this report shall be forwarded to the

-BRDO Cennol ".o..eger Manager. SEFOR.

3. The DRL shall be promptly notified of the occurrence.
4. Reactor operations may be resumed after corrective action has ,

1 been taken to prevent recurrence of the situation, provided I such operation is recommended by the Site Safety Committee.

l B. Limiting Conditions for Operation

1. If during operation, the limiting conditions for operation specified in Section 3 of these Technical Specifications are not met, the reactor shall be shut.down. ,

1 l 2. The Site Safety Committee shall review the occurrence and ascer-  !

tain that corrective measures are taken to prevent or minimize the probability of recurrence of the event. The committee shall prepare a report documenting its evaluation of the event and its recommendations and forward the report to the -itRDO Gcaccal "anager Manager. SEFOR.

3. If a violation of the limiting conditions for operation causes a reactor shutdown, the,DRL shall.be notified by means of the quarterly operations report. This report shall include the j circumstances of the abnormal occurrence and the remedial  !

actions taken.

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4. Reactor operations may be resumed when remedial actions have been taken and the limiting conditions for operation are met.

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. 6.3-1 i

Proposed Change No. 7 October 8, 1971

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l C. Component Failures and Deterioration of Fission Product' Barriers l

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1. If component failurds should occur which threaten the operabil- -  !

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, ity of an engineered safety system or if abnormal deteriora-tion should be discovered which could threaten the integrity of g ]

-on,e of the' harriers to the release of fission products, the l ,

, reactor shall be shut down.

j, 2. The Site Safety Committee shall review the occurrence and ascer-tain that corrective measures'are taken before reactor operations l are resumed. The Committee shall prepare a report documenting .,

I. the occurrence and the basis for any action it recommends and +

forward the report to'the ""0C Cmum el Mouo3er Manager, SEFOR.

3. The DRL'shall be notified of the occurrence as required by the license and by means of the Quarterly Operations Report. This  ;

report shall identify the circumstances and the remedial action ,

t taken. i D. Administrative and Procedural Controls  !

! 1. S'hould inadequacies in administrative or procedural controls l be disclosed during the course of facility operations which  :

create or could Icad to an unsafe condition, immediate action l

shall be taken to put the affected portion of the plant in the j safest possible condition.  !

l 2. The Site Safety Committee shall review the deficiencies and ,

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y assure that corrective measures are taken before normal opera-  ;

l tions are resumed. The Committee shall prepare a report of  :

L the. circumstances and action taken and. forward the report to l l

the ""0C Ceneral Manager Manager. SEFOR. j

3. The DRL shall be notified by means of the Quarterly 0perations ,

Report.

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i 6.3-2 -l t

l Proposed Change No. 7 i October 8, 1971 ,

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6.4 Action to Be Taken if a Safety Limit is Exceeded-If a safetf 11mit is exceeded, the reactor shall be shut down immedi- j l

  • Reactor operations shall not be resumed until authorized by ately.

l the DRL. An immediate report shall be made to the Manager, SEFOR ,

the Omuerol Moeeger of Ormeder neector Ocvalmemaet Operstien and to l

i the DRL. A complete analysis of the circumstances leading up to and resulting from the situation, together with a recommendation to pre-vent a recurrence shall be prepared by the SEFOR Site Safety Committee.

l This report sha21 be submitted to the Manager, SEFOR, Meeeger ef the Orceder neecius Develvymene Or mretien and the Chairman, SEFOR Safety )

Review Committee for review and action. Appropriate analyses and reports, verbal and written, shall be submitted to t'eh DRL.

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6.4-1 l

. Proposed Change No. 7 October 8, 1971

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