ML20012A525

Proposed Tech Specs Involving Deletion of Organizational Charts & Other Associated Minor Changes

ML20012A525
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/02/1990
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20012A215	List: ML20012A214 ML20012A525
References
NUDOCS 9003120163
Download: ML20012A525 (8)

Text

. ,--. - _

-1 ,

' -~

VTNPS 1

ume

.So'6.0.

u ADMINISTRATIVE CONTROLS s-

> PJ  ;.Ceinistrative controls are the written rules, orders, instructions, procedures, policies, practices, and the c3 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.

C4 eo 6.1 DJtGANIZATION 00 1 OU g A. Lines of authority, m ponsibility, and comumunication shall be established and defined for the highest ce** management levels through intermediate levels to and including all operating organizational. positions.

c These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Yankee Operatioral Quality Assurance Manual.

B. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those on-site activities necessary for safe operation and maintenance of the plant. Succession to this responsibility during his absence shall be delegated in writing.

C. The Manager of Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

D. Conduct of operations of the plant will be in accordance with the following minimum conditions.

1. An individual qualified in radiation protection procedures shall be present on-site at all times when there is fuel in the reactor.

2. Minimum shift staffing on-site shall be in accordance with Table 6.1.1.

3. A dedicated, licensed Senior Operator shall be in charge of any reactor core alteration.

4. Qualifications with regard to educational background experience, and technical specialities 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".

Amendment No. 66, 78, 87, 99, 19I 190'

. ~ - __ .

VYNPS .

a. Plant Manager e. . Operations Supervisor (See Item D.7, Page 190a)

b. Superintendent (s)- f. Reactor and Computer Supervisor

c. Chemistry Supervisor g. Maintenance Supervisor

d. Radiation Protection Supervisor h. Instrument and Control Supervisor

i. Shift Supervicors

5. The Radiation Protection Supervisor or Plant Health Physicist shall meet _ or exceed the qualifications of Regulatory Guide 1.8, Revision 1 (September 1975).

6. The Shif t Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

7. If the Operations Supervisor does not possess a Senior Operator License, then an Assistant Operations Supervisor shall be designated that does possess a Senior Operator License. All instructions to the shift crews involving licensed activities shall than be approved by designated Assistant Operations Supervisor.

8. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate on-site manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

E. A Fire Brigade of at least 5 members shall be maintained on-site at all times. # This excludes 2 members of the minimum shift crew necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.

1. Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absen :e of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

Amendment No. 63, 75, 7%, 87, I9I 190-a

- . ~ _

.- _ - - ~ _ _ _ . _._ - ~ _ _ _ _ _ _ _ __

uet e,

t *

(;< r=t Os.

L.

~ .

1 t

l-l i

I

?

p 1

+

r d

.-1 i

5 1

4 h

th '

M $

. t i

+

,s s

i

'h.

i R

j. Y N

4 4

e 1 e) y N

,k C

1

.  ?

n w+ -ma- +4-'e

p :. > . r

,. s i<

.a b

> ..* O I, , 4 w Y

k4

\.

5 d

s O

M 14

'5 4

lA H

'f ial '

g u) m 1 N .

S i

' w .

J O

e N

M e

,Q.

. t2 s

N

.y N y

i .

g O

n N

• i

^!

e O

E i C

f

m . . ,. _ _ _ . _

y

/ ..g

~

~

VYNPS

~

6.2~ REVIEW AND AUDIT _

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

A. . Elant Ooerations Review Committee

1. tktobership

a. Chairman: Plant Manager

b. Vice-Chairman: Superintendent (s)

c. Engineering Support Supervisor

d. Operations Supervisor

e. Maintenance Supervisor -

f. Reactor and Computer Supervisor

g. Chemistry Supervisor

h. Instrument and Control Supervisor i.- Radiation Protection Supervisor

2. Qpalifications i The qualifications of the regular members of the Plant Operations Review 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. Meetine Frequency: Monthly, and as required, on call of the Chairman.

4. Quanus

Chairman or Vice-Chairman plus four members or their designat..M alternates.

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

l Amendment No. 66,-75, 19I 194 I

- . . . -. . - . . - - , , - . - .,. - . . . . . . . ~ . . . - . . -. .. .- -

~

VYNPS 4

5. Designated. alternates shall be from other plant personnel in the appropriate disciplines or as selected by the Plant Manager; however, there shall be no more than three (3) alternates sceving on the committee at any one time.

6. Responsibilities

a. Review proposed normal, abnormal, and emergency operating procedures. . Review.all proposed maintenance procedures and proposed changes to those procedures; and any other proposed procedures or changes thereto as determined by the Plant Managar to affect nuclear safety.

b. Review proposed tests and experiments.-

c. Review proposed changes to Technical Specifications.

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.

4

f. Investigste reported instances of violations of Technical Specifications, such investigations to include reporting, evaluation, and recoamendations to prevent recurrence, to the Manager of Operations.

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

7. Antharity

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 6 (a) through (d) above.

1. In the event of disagreement between the recommendations of the Plant Operation Review Committee and the actions contemplated by the Plant Manager, the course determined by the Plant Manager to be the more conservative will be followed with immediate notification to the Manager of Operations.

Amendment No. 66, 10I 195

~. _ _ . .

- ~*

VYNPS N-

c. The Plant Operation Review Conunittee shall make centative determinations as to whether or not proposals considered by the Connaittee involve unreviewed safety questions. This determination ,

shall be subject to review by the Nuclear Safety Audit and Review Committee.

8. Records -

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

B. N_uclear Safety Audit and Review Commiitee

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

a. Chairman

b. Vice Chairman

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

d. No more than three members shall be selected from the organization reporting to the Manager of Operations.

e. The Conunittee will obtain advice and counsel from scientific or technica1' personnel employed by the Company or other organizations whenever the Conamittee considers it necessary to obtain further. scientific or technical assistance in carrying out its responsibilities.-

f. The Conumittce membership and its Chairman and Vice Chairman shall be appointed as specified in the Yankee Quality Assurance Manual

2. Qual.ifications The Connaittee shall consist of a minimum of six (6) members of designated alternates who as a group employ expertise in the following areas:

a. Nuclear Power Plant Technology

b. Reactor Operations

c. Utility Operations 196

- . . _ _ _ - . , - . . . . ,- - . - . - - ~_ - - - .- - _ . . .

3 .

VYNPS I

C. Procedures prepared for A and B above shall be reviewed and approved by the applicable Department Supervisor and the Plant Manager, or his designee (superintendent level).

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. Licensed radioactive sealed sources shall be leak tested for contamination. 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 sources 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 apply 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 leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferrer 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 from 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 20.005 ricrocuries of removable contamination.

Amendment No. 89,-83, 19I 206 y-- -w -r. -+ ,9yy- .gNv- '

-se-w- w u. ges+-. y =M mi_ ,_d =

- We s T ___ ___

__y__e as _w._ _ _._ __,._-ir__ u_.m._m_.,__ _ _ _ . ____.a-__.r__ mah_-h--_