ML20210B588
| ML20210B588 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/28/1987 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20210B547 | List: |
| References | |
| NUDOCS 8705050361 | |
| Download: ML20210B588 (7) | |
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l ATTACHMENT 1 Pages Deleted Pages Inserted 190 190 190a 190a 192 192 194 194 195 195 206 206 8705050361 870428 PDR ADOCK 05000271 p
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VYNPS 6.0 ADMINISTRATIVE CONTROLS Administrative controls are the written rules, orders, instructions, procedures, policies, practices, and the 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 t
A.
The Plant Manager has on-site responsibility for the safety and efficient operation of the facility.
Succession to this responsibility during his absence shall be delegated in writing.
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 Operations.
D.
Conduct of operations of the plant is shown in Figure 6.1.2 and 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
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there is fuel in the reactor.
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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.
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4.
Qualifications with regard to educational background experience, and technical specialities of the key l
supervisory personnel listed below shall apply and be maintained in accordance with the levels described i
in the American National Standards Institute N18.1-1971, " Selection and Training of Personnel for Nuclear i
Power Plants".
a.
Plant Manager g.
Operations Supervisor (See Item D.7, Page 190a) b.
Operations Superintendent h.
Reactor and Computer Supervisor c.
Technical Services Superintendent 1.
Maintenance Supervisor d.
Maintenance Superintendent j.
Instrument and Control Supervisor e.
Chemistry Supervisor k.
Shift Supervisors I
f.
Radiation Protection Supervisor Amendment No. 64, 78, 87, 90 190
VYNPS 5.
The Radiation Protection Supervisor or Plant Health Physicist shall meet or exceed the qualifications l
of Regulatory Guide 1.8, Revision 1 (September 1975).
6.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a sc.entific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
7.
If the Operat ions Supervisor does not possess a Senior Operator License, then an Assistant Operations Supervisor sLill be designated that does possess a Senior Operator License. All instructions to the shift crews involving licensed activities shallothan be approved by designated Assistant Operations Supervisor.
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.
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- 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 absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
Amendment No. 63, 75, 79, 87 190-a
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R 1-6 F iguro 6.1.2 PLANT OPERATIONS ORGANIZATION I
i PLANT MANAGER I
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TECHNICAL 8
MAINTENANCE SUPERINTENDENT l
SUPERINTENDENT gy%Qg OPERATIONS
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l 50 INSTRtMNT REACTOR ENGINEERING RADIATION NAINTENANCE AM)
AND OPER AT IONS CHfMISTRY
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SUPERVISOR SUPERV SOR SueERviSOR SueERvlSOR UP RVI OR SP OR 50 SHlf T M
ENGINEERING uplSM RADIATION HEALTH MAINTENANCE A
S T
PR0i TION PHYSICIST STAFF CONTROL COMPUTER STAFF STAFF So SUF'f RVI SORY SHIFT C0t4 TROL ROOM ENGINEER OfERATORS 0
CON 1ROL h00M e -RESPONSIBLE FOR FIRE PROTECTION G,LH A T ORS
- * - ANSI 18.1 -1971 REtLICENSE 50 LICENSED SENIOR OPERATOR O -LICENSED OPERATOR
-ADMINISTRAllVE POSITIONS NOT SHOWN
. -IN HEALTH PHYSICS NATTERS. THE RADI AT]ON PROIECTION SUPERVISOR HAS DIRECT l
ACCESS TO THE PLANT MANAGER Aux!LIARY A -OK OF THESE POSITIONS WILL BE DESIGNATED AS ALTERNATE TO THE PLANT Of'E R A TORS MANAGER AND MAY BE RETLILED ASSISTANT PLANT MANAGER ANENDNENT NO. (d. 7/. 7% pp. (/. 90 192
- . -EXCEPT AS SPECiflED IN SPECiflCATION 6.1.D.4 1
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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.
Plant Operations Review Committee 1.
Membership i.
a.
Chairman: Plant Manager b.
Vice-Chairman: Operations Superintendent c.
Vice-Chairman: Technical Services Superintendent d.
Vice-Chairman: Maintenance Superintendent e.
Engineering Support Supervisor f.
Operations Supervisor g.
Maintenance Supervisor h.
Reactor and Computer Supervisor
- i. Chemistry Supervisor
- j. Instrument and control Supervisor k.
Health Physicist 1.
Radiation Protection Supervisor 2.
Qualifications 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.
Meeting Frequency: Monthly, and as required, on call of the 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.
Amendment No. 66, 75 194
VYNPS Designated alternates shall be from other plant personnel in the appropriate disciplines or as selected 5.
by the Plant Manager; however, there shall be no more than three (3) alternates serving on the committee at any one time.
6.
Responsibilities Review proposed normal, abnormal, and emergency operating procedures. Review all proposed a.
maintenance 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.
Review proposed tests and experiments.
Review proposed changes to Technical Specifications.
c.
J Review proposed changes or modifications to plant systems or equipment, which changes would require d.
a change in procedures in (a) above.
Review plant operations to detect any potential safety hazards.
e.
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).
Perform special reviews and investigations and render reports thereon as requested by the Chairman g.
of the Nuclear Safety Audit and Review Committee.
7.
Authority t'
The Plant Operation Review Committee.shall be advisory.
a.
The Plant Operation Review Committee shall. recommend to the Plant Manager approval or disapproval of b.
proposals under Items 6 (a) through (d) above.
t 1.
In the event of disagreement between the recommendations of the Plant Operation Review l
Committee and the actions contemplated by the Plant Manager, the course determined by the Plant f
Manager to be the more conservative will be followed with immediate notification to the Manager e
of Operations.
195 Amendment No. 66
n VYNPS 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.
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 4
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 6.5.8 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 j
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 i
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 cample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall immediately ba 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 10.005 microcuries of. removable contamination.
l Amendment No. 89, 83 206 I
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