ML20009H679

Tech Specs Reflecting Proposed Organizational Structure at Facility

ML20009H679
Person / Time
Site:	Vermont Yankee
Issue date:	08/04/1981
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20009H675	List: ML20009H674 ML20009H679
References
NUDOCS 8108100354
Download: ML20009H679 (9)

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VYNPS 6.2 REVIEW AND AUDIT .

r Organizational units for the review and audit of plant operations shall be constituted and have the responsibilities and authorities outlined below:

^

A. Plant Operations Review Committee

1. Membe rship

a. Chai rman : Plant Manager i b. Vice-Chairman: Assistant Plant Manager

c. Vice-Chai rman : Operations Superintendent

d. Vice-Chairman: Technical Services Superintendent

e. Engineering Support Supervisor

f. Operations Supervisor

g. Maintenance Supervisor

h. Reactor and Computer Supervisor

1. Chemistry and Health Physics Supervisor

j. Instrument and Control Supervisor

k. Health Physicist I

2. Qualifications The qualifications of the regular members of the Plant Safety Committee with regard to the combined experience and technical specialties of the individual members shall be maintained at a level at least equal to or higher than as described in Specification 6.1.

3. Meeting frequency: Monthly, and as required, on call of t'.c Chairman.

4. Quorum: Chairman or Vice-Chairman plus four members or their designated alternates.

NOTE: For purposes of satisfying a quorum, a Vice-Chairman may be considered a member providing that Vice-Chairman is not presiding over the meeting.

194

VYNPS Designated alternates shall be from other plant personnel in the appropriate disciplines or from ths Technical Services Group; however, there shall be no more than three (3) alternate members serving on the 5

committee at any one time.

r

6. Responsibilities Review all proposed maintenance

a. Review proposed normal, abnormal and emergency operating procedures.

procedures and proposed changes to those procedures; and any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety.

b. Feview proposed tests and experiments.

c. Review proposed changes to Technical Specifications.

4

d. Review proposed changes or modifications to plant systems or equipment, which changes would require a change in procedures in (a) above.

e. Review plant operations to detect any potential safety hazards.

f.

Investigate reported instances of violations of Technical Specifications, such investigations to include reporting, evaluation and recommendations to prevent recurrence, to the Manager of Operations (See Figure 6.1.1).

g. Perform special reviews and investigations and render reports thereon as requested by the Chairman of the Nuclear Safety Audit and Review Committee.

! 7. Authority i

a. The Plant Operation Review Committee shall be advisory.

b. The Plant Operation Review Committee shall recommend to the Plant Manager approval or disapproval of proposals under Items f (a) through (d) abova.

In the event of disagreement between the recommendations of the Plant Operation Review Cormittee and

1. the course determined by the Plant Manager to be the

. the actions contemplated by the Plant Manager, more conservative will be followed with immediate notification to the Manager of Operations.

195

VYNPS ,

c. The Plant Operation Review Committee shall make tentative determinations as to whether or not proposals considered by the Committee involve unreviewed safety questions. This determination shall be subject to review by the Nuclear Safety Audit and Review Committee. 4

8. Records Minutes shall be kept at the plant of all meetings of the Plant Operation Review Committee and copies shall be sent to the Manager of Operations and the Nuclear Safety Audit and Review Committee.

B. Nuclear Safety Audit and Review Committee

1. The Committee shall consist of at least six (6) persons:

a. Chai rman i

b. Vice Chairman

c. Four technically qualified persons who are not members of the plant staff. i l

d. No more than three members shall be selected from the organization reporting to the Manager of l Ope ra t ions .

e. The Committee will obtain advice and counsel from scientific or technical personnel employed by the Company or other organizations whenever the Committee considers it necessary to obtain further scientific or technical assistance in carrying out its responsibilities.

f. The Committee membership and its Chhirman and Vice Chairman shall be appointed by the Vermont Yankee Vice President or such person as he shall designate.

! 2. Qualifications I

l The Committee shall consist of a minimum of six (6) -embers or designated alternates who as a group employ expertise in the following areas:

a. 'uclear N Power Plant Technology

b. Reactor Operations l

c. Utility Operations 196

O VYNPS

d. Power Plant Design

e. Reactor Engineering i

f. Radiation Safety

g. Safety Analysis

h. Instrumentation and Control

1. Metallurgy

3. Meeting Frequency: Semi-annually and as required on call of the Chainnan. l j

4. Quorum:

Chairman or Vice Chairman plus four members or designated alternates. l

5. Responsibilities

a. Review proposed changes to the operating license including Technical Specifications.

b. Review minutes of meetings of the Plant Operation Review Committee to determine if matters considered by j

that committee involve unreviewed or unresolved safety questions, i

c. Review matters including proposed changes or modifications to plant systems or equipment having safety significance or referred to it by the Plant Operation Review Committee or by the Plant Manager.

d. Periodic audits of plant operations, and audits of the facility fire protection program and implementing procedures shall be performed under cognizance of the Committee.

e. Investigate all reported instances of violations of Technical Specifications, reporting findings and l

' recommendations to prevent recurrence to the Manager of Operations.

f. Perform special reviews and investigations and render reports thereon as requested by the M'anager of

' Operations.

g. Review proposed tests and experiments and results thereof when applicable.

n. Review abnormal performance of plant equipment and anomalies.

197

VYNPS

i. Review unusual occurrences and incidents which are reportable under the provisions of 10 CFR Part 20 and 10 CFR Part 50. ...

J. Review of occurrences if Safety Limits are exceeded.

6. Authority

a. Review proposed changes to the operating license including Technical Specifications and revised bases for submittal to the NRC.

b. Review proposed changes or modifications to plant systems or equipment, provided that such changes or modifications do not involve unreviewed safety questions.

c. Recommend to the Manager of Operations appropriate action to prevent recurrence of any violations of l Technical Specifications.

I

d. Evaluate actions taken by the Plant Operation Review Committee.

7. Records Minutes of all meetings of this committee shall be recorded. Copies of the minutes shall be forwarded to I the Manager of Operations, the Vice President-Operations, the Plant Manager and any others that the Chairman may designate.

l l

l 198

VYNPS Procedures prepared for A and B abose shall be reviewed and apprt red by the Plant Manager or his designee and the Manager of Operations.

D. Temporary changes to procedures described in Specification 6.5. A above which do not change the intent of the original procedure, may be made with the concurrence of two individuals holding senior operator licenses. Such changes shall be documented and subsequently reviewed by the PORC and approved by the Plant Manager or his designee. ,

E. Temporary changes to procedures described in Specification 6.5.B may be made with the concurrence of an individual holding a senior operator license and the health physicist on duty.

F. Practice of site evacuation exercises shall be conducted annually, following emergency procedures and including a check of communications with off-site support groups. Annual reviews of the Emergency Plan shall be performed.

G. Licensed radioactive sealed sources shall be leak tested for contami .ation. Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State as follows:

1. Each licensed sealed source except startup so* rces previously subjected to core flux, containing radioactive materials, other than Hydrogen 3, with half-life greater than thirty days and in any form, other than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.

2. The periodic leak test required does not cpply to sealed sources that are stored and are not being used.

The sources exempted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been Jeak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferer indicating that a leak test has been made within six months prior to the transfer, sealed sources shall not be put into use until tested.

3. Each sealed startup source shall be tested within 31 days prior to being subjected to core flux and following repair or maintenance to the source.

The leakage test shall be capable of detecting the' presence of 0.005 microcurie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall immediately be withdrawn from use, decontaminated, and repaired, or be disposed of in accordance with Commission regulations.

Notwithstanding the periodic leak tests required by this Technical Specification, any licensed sealed source is exempt f rom such leak test when the source contains 100 microcuries or less of beta and/or gamma emitting material or 5 microcuries or less of alpha emitting material.

A special Report shall be prepared and submitted to the Commission within 90 days if source leakage tests reveal the presence of 0.005 microcuries of removable contamination.

206

1 VYNPS .

l 6.0 ADMINISTPtTIVE CONTROLS ,,.

' Administrative controls are the written rules, orders, instructions, procedures, policies, practices, and the j designation of authorities and responsibilities by the management to obtain assurance of safety and quality of'

operation and maintenance of a nuclear power reactor. These controls shall be adhered to.

6.1 ORGANIZATION-

)

A. The Plant Manager or the Assistant Plant Manager has on-site responsibility for the safety and efficient l operation of the facility.

B. The portion of the corporate management which relates to the operation of this plant is shown in Figure 6.1.1.

C. In all matters relating to the' operation of the plant and to those Technical Specifications, the Plant Manager shall report to and be directly responsible to the Manager of Operationa.

D. ~ Conduct of operations of the plant is shown in Figure 6.1.2 and will be in accordance with the following minimum conditions (See Table 6.1.1).

1 A licensed Senior Operator and an individual qualified in radiation protection procedures shall be present on site at all times when there is fuel in the reactor.

2. Licensed Operators on site shall be in accordance.with Table 6.1,1, one of which must be in the control room at all times when fuel is in the reactor.

'3. A licensed Senior Operator shall be in charge of any refueling operation.

4. Qualifications with regard to educational background experience, and technical specialties of the key supervisory personnel listed below shall apply and be maintained in accordance with the . levels described in the American National Standards Institute N18.1-1971 " Selection and Training of Personnel for Nuclear Power Plants.*

a. Plant Manager f. Operations Supervisor

b. Assistant Plant Manager g. Reactor and Computer Supervisor

c. Operations Superintendent h. Maintenance Supervisor

d. Technical Services Superintendent 1. Instrument and Control Supervisor

e. Chemistry and Health Physics J. Shift Supervisors Supervisor 190