ML19345E423

Proposed Changes to Tech Specs 1.1 & 6.5 Re Ofc & Staff Organizational Changes

ML19345E423
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/03/1977
From:	Bilby C CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML19345E422	List: ML19345E421 ML19345E423
References
NUDOCS 8101190177
Download: ML19345E423 (17)

Text

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1.0 INTRODUCTION

1.1 SCOPE 1.1.1 These Technical Specifications set forth the principal design features and operating limits and requirements which have an effect on the safety of operation of the Big Rock Point Nuclear Plant (the plant).

1.1.2 Sections 1 through 7 present the plant operating limits (including original fuel) through the period of the full-term license.

In the order of presen-tation, Section 1.0 concerns the introduction, Section 2.0 concerns the site, Sections 3.0 through 6.0 cover the plant and its syste=3, and Section T.0 presents procedures for plant start-up and procedures for normal and emergency operation of the plant. This section also includes administrative and procedural safeguards to the extent that these have a potential effect on nuclear safety.

Section 8.0 describes Phase II of the Research and Development Program, including para =etric variations and operating limits on R&D fuel during Phase II.

Section 9 0 presents the primary system sur-veillance requirements.

1.1.3 The dimensions given in these specifications of the plant design features are subject to normal manufacturing tolerances. The operating limits and requirements which are significant from the standpoint of nuclear safety are specified with each of the plant's systems.

1.1.k Surveillance requirements shall be applicable as specified for individual components or systems as stated in individual specification requirements.

Each surveillance requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not to exceed 25% of the surveillance

interval, b.

A total maxinum combined interval time for any three consecutive sur-veillance intervals not to exceed 3 25 tices the specified curveillance int erv al.

1.2 DEFINITIONS Various provisions of these Technical Specifications set forth licitations and restrictions which depend upon modes of operation. The following modes of operation are defined to clarify the intent of such provisions, and are not the same as, nor should they be confused with, the positions of the mode selector switch described in Section 6.1.3 1.2.1 Povar Operati 2 - is any operation other than shutdown or cold shutdown with the reactor vessel closure bolted in place.

1.2.2 Core Alteration - is any completed planned sequence of movements or core co=ponents resulting in either a net change in the configuration of the reactor core or a net gain in core reactivity.

1.2.3 Refuelin.c Oceration - is any operation with any of the reactor vessel clo-sures cpen during which a core alteration, or other operation which might increase core reactivity, is in progress.

1.2.h Major Fefueling - is any refueling operation with the head off during which four or more fuel bundles are added, exchanged or repositioned in the reactor core."

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a B.

Remove Page 10-2, " Figure 6.2.1, Consumers Power Company Off-Site Organization," and replace it with the following:

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Consumers Power Company OFF-SITE ORGANIZATION PRESIDENT EXECUTIVE VICE PRESIDENT SAFETY AND AUDIT VICE PRESIDENT REVIEW PRODUCTION & TRANSMISSION BOARD l

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I MANAGER OF MANAGER OF DIRECTOR OTHER PRODUCTION -NUCLEAR MAINT &

A SUR CE ADM SERVICES P&T PLANT GENERAL SUPT QA SUPERINTENDENTS ADM SERVICES ADMINISTRATOR (NUCLEAR)

NUCLEAR TRAINING ADMINISTRATOR FIGURE 6.2-1 10:2

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R-move Page 10-3, " Figure 6.2-1, Consumers Power Company Big Rock Point Organization," and replace it with the followin6:

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Consumers Power Company BIG ROCK POINT.

Organization QA-ADMIN OFF-SITE PLANT SUPERINTENDENT PLANT

' REVIEW-QA SUPT COMMITTEE I

l-PERSONNEL TECIINICAL

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DIRECTOR ENGINEER TRAINING OPERATIONS ADMINISTRATIVE

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TECllNICAL MAINTENANCE C00RDINATOR' SUPERINTENDENT SUPERVISOR PIlYSICIST SUPERINTENDENT SUPERINTENDENT i

SOL (a)

I&C QC.

MAINTENANCE SECURITY CHEM & RAD ENGINEERS ENGTNEER 1

TRAINING.

OPERATIONS l

0RDNSORf--. MA fENACE INSTRUCTOR SUPERVISOR TECHNOLOGISTS INSPECTOR 16C-SOL (b)

MAINTENANCE SUPERVISOR SifPERVISOF PLANT SIIIFT HM A

A OR SUPERVISORS ENGINEER ASSISTANT.

EPLANT SOL l

MAINTENANCE TECilNICT6Nf ERVISOR~

ENGINEER OPERATORS I

REPAIRMEN SQL - Senior Operator Licensee (a) The Operations Superintendent need not hold an SOL provided he meets the.oth'er requirements -or'6.3;1' of these

, specifications and the position of " Operations Supervisor" is' filled. Under;these conditions, the Operations Supervisor shall be responsible for directing the activities of licensed operators.

(b) This. position need not be filled if the Operations Superintendent holds an' SOL.

4 FIGUREL6.2-1 10-3'

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D.

Remove Pages 10-5, 10-7, 10-8, 10-10 and 10-11 and replace them with the following:

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6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff shall' be maintained under the direction of the Nuclear Training Administrator and shall meet or exceed the regrirements and recommendations of Section 5 5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR, Part 55 6.5 REVIE4 AND AUDIT 6.5 1 PLANT REVIE4 COMMITI'EE (PRC) 6.5.1.1 FUNCTION The Plant Review Committee (PRC) shall function to advise the Plant Superintendent on all matters related to nuclear safety.

6.5 1.2 COMPOSITION The PRC shall be composed of the:

Chairman:

Plant Superintendent Member:

Operations Superintendent Member:

Technical Superintendent Member:

Maintenance Superintendent Member:

Instrument and Control Engineer Member:

Reactor Engineer Member:

Health Physicist Member:

Shift Supervisor Member:

Engineer or Technologist With at Least One-Year Plant Experience 6.5.1.3 ALTEPNATES Alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in PRC activities at any one time.

10-5

6.5.1 (Cont'd) 6.5.1.7 AUTHORITY The PRC shall:

Recommend to the Plant Superintendent written approval or disapproval of items a.

considered under 6.5.1.6(a) through (d) above, b.

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

l c.

Provide immediate written notification to the Manager of Production, Nuclear and

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the Chairman of SARB of disagreement between the PRC and the Plant Superintendent.

However, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuar.t to 6.1.1 above.

6.5.1.8 RECORDS The PRC shall maintain written minutes of each meeting and copies shall be provided to the Manager of Production, Nuclear, the Chairman of SARB, PRC members and alternates.

6.5.2 SAFEfY AND AUDIT REVIEW BOARD (SARB) 6.5.2.1 RESPONSIBILITIES SARB is responsible for maintaining a continuing examination of designated plant activities.

In all cases, where a matter is formally considered by SARB, its findings and recommendations are communicated in writing to the Vice President - Production & Transmission (P&T) and other appropriate levels of management. A written charter is prepared and approved bv the Vice President - P&T which designates the membership, authority and rules for conduatn_g the meetings. Board membership, qualifications, meeting frequency, quorum, responsibilities, authority and records are in accordance with the nuclear "lant Technical Specifications and ANSI N18.7-1972.

6Property "ANSI code" (as page type) with input value "ANSI N18.7-1972.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..5.2.2 FUNCTION The SARB shall function to provide independent review of designated activities affecting safety-related components, systems and structures designated on the plant's Safety-Related Quality List contained in the Consumers Power Company Quality Assurance Program.

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6.5.2 (Cont'd) 6.5.2.3 COMPOSITION AND QUALIFICATIONS Collectively, the personnel appointed for the SARB by the Vice President - P&T shall be l

competent to conduct reviews and technical audits in the followf g areas:

a.

Huclear power plant operations.

b.

Nuclear engineering.

c.

Chemistry and radiochemistry.

d.

Metallurgy.

e.

Instrumentation and control.

f.

Radiological safety.

g.

Mechanical and electrical engineering.

h.

Quality Assurance practices.

An individual appointed to the SARB may possess expertise in more than one of the above specialties. He should, in general, have had professional experience at or above the senior engineer level in his specialty.

6.5.2.h ALTFRHATE MEMBERS Alternate members may be appointed by the Vice President - P&T to act in place of members l

during any legitimate and unavoidable absences including a conflict-of-anterest determination.

The qualifications of alternate members shall be similar to those members for whom they will substitute.

6.5.2.5 CONSULTA!TPS Consultants shall be utilized as determined by the SARB members and/or chairman to provide expert advice to the SARB. SARB members are not restricted as to sources of technical input and may call for separate investigation from any competent source.

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6.5.2 (Cont'd) h.

The status-of deficiencies identified by the Quality Assurance Program, -including the effectiveness of the corrective actions completed and implemented,,at least _once every six (6) months.

i. Audits of the Security Program required by ' the ' " Nuclear Power Plant Security Plan."'

6.5.2 9 AUDITS Audits of safety-related facility activities during operations are performed.by 'the Quality Assurance Department - P&T.in accordance with the policies and procedures of the Consumers-~

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Power Company Quality Assurance Program. - Qualit'y Assurance audit reports are sent to. SARB for review. In addition, technical audits.are the' responsibility'or;the Technical-Services Department and shall be reviewed by_SARB. These technical audits encompass:

The conformance of facility operation to all provisions contained within the Technical a.

Specifications and. applicable license conditions at least ance per year.

b.

The performance, training and qualifications of the entire facility staff at least once per year.

c.

The facility Site Emergency _ Plan and implementing procedures at least once per two years. -

d.

Any other area of facility operation considered appropriate by SARB or' the Vice President - P&T.

6.5 2.10 AUTHORITY SARB shall report to and advise the Vice President - P&T on those areas of responsibility specified in 6.5.2.8 and 6.5 2.9 6.5.2.11 RECORDS Records of SARB activities shall be prepared and distributed as indicated below:

i a.

Minutes of each SARB meeting shall be prepared.and forwarded to the Vice President - P&T and l

each SARB member within fourteen (1h) days following each meeting.

Minutes shall be approved 4

at or before the next regularly scheduled meeting-following distribution of the minutes.

b.

If not included in SARB meeting minutes, reports of reviews encompassed by.Section 6.5.2.8 above shall be prepared and forwarded to the,Vice President - P&T within fourteen (14) days following completion of the review.

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6.5.2 (Cont'd) c.

Audit reports encompassed by 6.5.2.9 above, shall be forwarded to the Vice President'-

P&T and management positions responsible for the areas audited' vithin thirty (30) days.

after ' completion of-the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The. following actions shall be taken in the event of a reportable occurrence:

The Commission shall be immediately notified pursuant to 6.7 or a report submitted pursuant.

a.

to the requirements of 6.9 i

'b.

All events which are required by regulation or Technical Specifications to be ' reported to the NRC in writing within 2h hours shall be reviewed by the PRC. The results of the PRC review shall be submitted-(either by PRC minutes or by separate _ report) to SARBf and 'the Manager of Production, Nuclear.

6.7 SAFETY LIMIT VIOLATION

'6.7.1 The following actions shall be taken in the - event a Safety Limit is violated:

The reactor shall be shut down immediately and not restarted until Commission authorization' n.

is received [10 CFR 50.36(c)(1)(1)].

b.

The Safety Limit violation shall be reported immediately to the Commission in accordance with 10 CFR 50.36, the Manager of Production, Nuclear and to SARB Chairman or Vice-Chairman, A report shall be prepared.in accordance with 10 CFR 50.36 -and 6.9 of this specification.

c.. The Safety Limit violation and the report shall be reviewed by the PRC.

d.

The report shall be submitted within 10 days to the Commission '(in accordance with the I

requirements of 10 CFR 50.36), SARB Chairman and the Manager of Production, Nuclear.

i 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained for all structures, systems, components and safety actions defined in the Big Rock Point Quality List. These procedures shall-meet.or exceed the requirements of ANSI-18.7 10-l'

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Remove Table 6.2-1, " Minimum Shift Crew Co= position," and replace it with the following:

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TABLE 6.2-1 Minimum Shift Crew Composition The minimum shift crew shall be as follows except when plant conditions specified in paragraph (a) or (b) below have been established (see note (1) below) or when an unexpected absence occurs (see note (2) below):

1 Shift Supervisor - SOL 2 Operators - OL 1 Operator - Nonlicensed l

(a) Cold Shutdown 1 Shift Supervisor - SQL 1 Operator - OL 1 Operator - Nonlicensed (b) Refueling Operations (See note (3) below) 1 Shift Supervisor - SOL 1 Operator - OL 2 Operators - Nonlicensed SOL - Senior Operator Licensed in accordance with 10 CFR 55 OL - Operator Licensed in accordance with 10 CFR 55.

(1) During control rod motion associated with reactor start-up (to a power level 2 5 percen,t), one licensed Operator shall observe the control rod manipulation to ensure established control rod withdrawal pro-cedures are adhered to.

(2)

In the event that any member of a minimum shift crew is absent or incapacitated due co 'illnese or injury, a qualified replacement shall report on site within two hours.

(3) Does not include additional personnel required when core alterations are being conducted. See 6.2.2.e.

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l II. -DISCUSSION A.

Changes to Section 1.0, " Introduction" Section 1.1.4 is proposed to incorporate a definition of surveillance requirements in terms of applicability and time frame. The model for this proposal is the Standard Technical Specifications for General Electric Boiling Water Reactors (Section h.0.2) and represents an industry-wide currently acceptable definition.

Incorporating this proposal vill help alleviate any ambiguities that could arise in the imple=entation of surveillance requirements and define a more orderly approach for their accomplishment.

i B.

Management Organization At the time of the issuance of the December 19, 1975 Administrative Control Technical Specifications, the Consumers Power Co=pany organi-zation' contained a Vice President-Bulk Power Operations and an Executive Manager-Bulk Power Operations. On January _1, 1976, Mr R A Lamley-retired i

from Consumers Power Company. Mr C R Bilby, for=erly Executive Manager--

Bulk Power Operations, was appointed to Vice President-Bulk Power Oper-ations to replace ths Lamley. Mr Bilby's title was then subsequently changed to Vice President, Production and Transmission. At present, Consumers Power Company does not plan to fill.the slot vacated by Mr l

Bilby. Thus, Figure 6.2-1 and Pages 10-T, 10-8, 10-10 and 10-11 have been appropriately revised to reflect this organization change.

C.

Big Rock Point Organization Change A position of Operations Supervisor has been created in order to lighten the workload on the Operations Superintendent. This position is re-flected on-the Big Rock Point Organization Chart included in this pro-posed change.

In addition, provision has been made such that a licensed Senicr Reactor Operator is required to directly supervise the shift supervisors. To alleviate some of the workload of the Technical Super-intendent, additional engineers and technologists nave been added and are reflected in the Organization Chart.

D.

Change in PRC Authority and Makeup The proposed change to the Plant Review Committee makeup is one of title rather than staff functions. The change is submitted to reflect the 6

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' changes in the 3ig Rock Point organizational chart and does not alter.

the seniority.or composition 'of the PRC.

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A typographical error apparently occurred in Section 6.51.T(b) on -

Page 10-7 The Standard Technical Specifications and' the' Palisades Plant' Technical Specifications require PRC to render determinations in

writing with regard.to whether or not each'ites considered under 6.5 1.6(a) through'(e) above constitutes an unreviewed safety question.

The Technical Specifications issued for the Big Rock Point Plant Dece=ber 19,~ - 1975 contained a similar requirement except that "e" was replaced with "f." - We believe this.vas a typographical error and request that it be changed to "e."-

E.

Minimum Operating Crew Complement The new Administrative Control Technical Specifications require that one Senior Licensed Operator, two _ Licensed Operators and two Nonlicensed Operators are on. site during normal plant operations. The original mini-mum shift complement, specified in the FHSR, Section ll'.l.3,.vas one Licensed Operator and one Honlicensed Operator.

In our proposed'new Administrative Controls, we requested that the minimum shift complement during nor=al operations be defined as one Senior Licensed Operator, one Licensed Operator and two Nonlicensed Operators. We are amending that-request to specify that the minimwm shift complement during normal plant operations consists of one Senior Licensed Operator, two Licensed Oper-ators and one Nonlicensed Operator.

In our Technical Specifications change request of March 8,1976, sub-stantial justification for a reduced shift complement was presented.

However, there are other amplifying factors that lend substantial-credence to'this justification.

The duties of the Auxiliary Operator (Nonlicensed) include operation of auxiliary equipment (electrical and mechanical), minor component' repair, equipment tag outs and log keeping. All tasks are performed under the direct supervision of a licensed operator. At a plant the site and

. complexity of Big Rock Point, these tasks can readily be performed by a single individual during normal plant operations without jeopardizing any aspect of operational safety.

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III. CONCLUSI0!IS Based on the foregoing, the Big Rock Point Plant Review Committee has con-cluded that this proposed Technical Specifications Change does not involve an unreviewed safety question.

COIISUMERS POWER COMP /JPI By CRBilby,VicePrecipat Production & Transmiselon Sworn anu subscribed to before me this 3rd day of March 1977 WA) i O//Or) h inda P. Thayer, Hotary/Public Jackson County, Michigan (SEAL)

My commission expires July 9, 1979 8

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