ML18139A624
| ML18139A624 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/04/1980 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A623 | List: |
| References | |
| NUDOCS 8008060353 | |
| Download: ML18139A624 (16) | |
Text
ATTACID1ENT 1 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE NO. 84 SURRY POWER STATION
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e e TS 6.1 6.0 ADMINISTl4-TIVE CONTROLS I
6.1 ORGANIZATION, SAFETY AND OPERATION REVIEW Specification A. The Station Manager shall be responsible for the safe operation of *the facility. In his absence, the Assistant Station Manager shall be responsible for the safe operation of the facility. During the absence of both, the Station Manager shall delegate in writing the succession to this responsibility. The Station Manager shall report to the Manager-Nuclear Operations and Maintenance. The relationship between this Manager and other levels of company management is shown in TS Figure 6.1-1.
1*
B. The Station organization shall conform to the chart as shown in TS Figure 6.1-2.
- 1. Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N.18.1-1971 for comparable positions, except for the Supervisor-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1~8, September 1875~
e e TS 6.l-2a
- 2. Retraining and replacement training of station personnel shall be in accordance with American National Standard 18.1 "Selection and Training of Nuclear Power Plant Personnel" dated March 8, 1971 and 10 CFR 55, Appendix Ao
- 3. The following requirements supplement the applicable regulations of 10 CFR 50.54:
CONDITION MINIMUM COMPLEMENTa
- 2. One unit fueled and shutdown** 1 SLO, l LO, 1 AO 3e One unit operating and one unit shutdown 1 SLO*, 3 LO, 2 .AO
SLO = Senior Licensed Operator as defined by 10 CFR 55.4(e)
LO = Licensed Operator as defined by 10 CFR 55.4(d)
AO = Auxiliary Operator
- = When the shutdown unit is undergoing refueling or startup, 1 additional SLO will be added to this shift comple1,1ent to ensure supervision of these activities.-
a = An.individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
4.. A fire team at least five members, all of whom have received fire service training:, will be maintained on-site at all. times.
This excludes personnel in Section 3 above of the minimum shift crew necessary for safe shutdown of the plant and any personnel required for other 'essential functions during a fire emergency.
e e TS 6.l-2b
- 5. A training program for the fire brigade and fire teams shall be main-tained under the directions of a Fire Marshall and shall meet or exceed the requirements of the NFPA Code Section 27 (1975), except that training sessions and drills shall be held at least once per 92 days.
C. Organization units to provide a continuing review of the operational and safety aspects of the nuclear facility shall be constituted and have the authority and responsibilities outlined below:
- 1. Station Nuclear Safety and Operating Committee
- a. Membership (1) Chairman - Station Manager (2) Vice Chairman - Assistant Station Manager
- , (3) Member Superintendent Operations (4) Member Superintendent Maintenance (5) Member Superintendent - Technical Services
e eTS 6.1-3
- b. Qualifications: The qualifications of the regular members of the Station Nuclear Safety and Operating Committee with regard to the combined experience and technical specialties of the individual members shall be maintained at a level at least equal to those described in Section 6.l.Be1 of the SpecificationsG
- c. Meeting frequency: As called by the Chairman but not less than monthly.
d*. Quorum: Chairman or Vice Chairman, and two others to provide a quonnn of three members.. The Chairman or Vice Chairman may appoint a similarly qualified designee to represent a member other than the Chairman or Vice Chairman on a temporary basis.
No more than two alternates shall participate as voting members in SNSOC activities at any one time.
- e. Responsibilities
- 1. Periodically review all proposed normal,. abnormal,. and emergency operating procedures and all proposed maintenance procedures. Review proposed changes to those procedures, and any other proposed procedures or changes thereto as determined by the Station Manager which affect nuclear safety.
e TS 6.l-l~
- 2. Review all proposed test and experiment procedures and results thereof when applicable.
- 3. *Review* proposed changes to Technical Specificat:ions.
- 4. Review all proposed changes or modifications to systems or equipment that would require a change in established procedures, or which would constitute.a design change.
- 5. Periodically review all operations to detect any potential safety hazards.
60 Investigate all reported instances of departure from f
Technical Specification limits, such investigations to include review~ evaluation and recounnendations to pre.vent recurrence, to the Station Manager, }Ianager-Nuclear Operations and Maintenance, and to the Chairman of the System Nuclear Safety and Operating Committee.
- 7. The Station Nuclear Safety and Operating Committee shall make determinations as to whether or not proposa1s considered by the Connnittee involve unreviewed safety questions. This determination shall be subject to review by the System Nuclear Safety and Operating Committee.
80 Review all reportable occurrence reports.
e e TS 6.1-5
- 9. Perform special reviews and investigations and render reports thereon as requested by the Chairman of the System Nuclear Safety and Operating Committee.
- 10. Initiate periodic drills to test the effectiveness of the emergency procedures.
- f. Authority -
le The Station Nuclear Safety and Operating Committee shall advise the Manager on all matters affecting the safe operation of the facility.
2o The Station Nuclear Safety and Operating Committee shall recommend to the Station Manager approval or disapproval of proposals under items e(l) through (4) above.
(a) In the event of disagreement between the recommen-dations of the Station Nuclear Safety and Operating Committee and the actions contemplated by the Station Manager, the course determined by the Station Manager.
will be followed with immediate notification to the I
Manager-Nuclear Operations and Maintenance and the Chairman of the System Nuclear Safety and Operating Committee a
- g. Records Minutes shall be kept of all meetings of *the Station Nuclear
TS 6.1-6 Safety and Operating Committee and copies shall be sent to the Manager-Nuclear Operations and Maintenance and to all members of the Station and System Nuclear Safety and Operating Committees.
- h. Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method of submission, and the content of presentations to the connnittee, provisions for the use of subcommittees; review and approval by members of written committee evaluations and recommendations; the distributions of minutes; and, such other matters as may be appropriate.
2o System Nuclear Safety and .Operating Committee (SyNSOC)
- a. Composition
- 1. The SyNSOC shall be composed of the Chairman and four other memberso Membership shall be composed,of the Managers or Directors of the Power Station Engineer"ing,. Fuel Resources, Nuclear Operations, and Licensing and Quality Assurance Departments or qualified designees from these departments and a sixth qualified member selected by the five other members.
- b. Qualifications The minimum qualifications of the members. of the SyNSOC will be:
An engineering graduate or equivalent with combined nuclear and conventional experience in power station design and/or operation
e TS 6.1-11
- 4. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix B;* 10 CFR 50, at least once every two (2) years.
- 5. The Station Emergency Plan and implementing procedures at least once every two (2) years.
- 6. The Station Security Plan and implementing procedures at least once every year.
7c The facility fire protection program and implementing proce-dures at least once every 24 months.
- 8. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either quali-fied offsite license personnel or an outside fire protection finn.
- 9. An inspection and audit of the fire protection and 1.oss pre-vention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
- 10. Any other area of facility operation considered appropriate by SyNSOC or the Executive Vice President-Power.
- j. Authority The SyNSOC shall report to and advise the Executive Manager-Licensing and Quality Assurance, who shall advise the Executive Vice President-Power on those areas of responsibility specified in Sections 6.1.C.2.h and 6.1.C.2.i and review and apprm.Te the meeting minutes of the SyNSOC.
e 'F:S 6.1-12
- k. Records Records of SyNSOC activities shall be prepared and disseminated promptly to~
L Executive Vice President-Power 2s Nuclear Power Station Managers 3~ Manager-Nuclear Operations and Maintenance 4o Members of the SyNSOC So Others that the Chairman of the SyNS©C may designateo
- 1. Procedures Written bylaws and administrative procedures for COIIll-nittee operation shall be maintained describing tt.ili.e met.hpdEl qf submission and the content of presentatio'En.s to the committee; provisions for use of subcommittee evaluations and recommendations; d~'.stribution of minutes, and 2 . such other matters as may be appropriate *.
EXECUTIVE VICE PRESIDENT POWER*
EXECUTIVE MANAGER MANAGER MANAGER LICENSING AND NUCLEAR NUCLEAR QUALITY ASSURANCE OPERATIONS & MAINT. TECHNICAL SERVICES SYSTEM NUCLEAR SAFETY ANO OPERATING COiviriilTTEE' I I I NUCLEAR DIRECTOR DIRECTOR DIRECTOR DIRECTOR STATION OPERATION AND SAFETY EVALUATION TECHNICAL ANALYSIS CHEMISTRY AND MANAGERS MAINTENANCE SERVICES AND CONTROL HEAL TH PHYSICS I !STATION SUPERVISOR
.fSAFETY ENGINEERING l
I SECTION !iUPV I
SECTION SUVP Sl:CTION SUPV OPERATION AND ADMINISTRATIVE e
TRAININQ MAINTENANCE SUPPORT SERVICE!i Offsite Orgnnization for Facility Management amt Technical Support
-.~
~-------*--
MANAGER NUCLEAR OPERATIONS & MAINTENANCE SUPERVISOR QA I I OPE RATIONS &
MAINTENANCE
~---.-~
I STATION NUCLEAR SAFETY & OPERATING COMMITTEE
STATION MANAGER ------ - - - - - -- - - -- ------
RESIDENT I QUALITY CONTROL ENGINEER I ASSISTANT STATION MANAGER e
SUPEIIINTENOENT SUPERINTENDENT SUPERINTENDENT SL OPERATIONS MAINTENANCE I TECHNICAL SERVICES I I I
TRAINING SUPERVISOR SUPERVISOR HEALTH PHYSICS SL SHIFT SUPERVISOR - MAINTENANCE COORDINATOR H SUPERVISOR CHEMISTRY
,._______, I SUPERVISOR ADMINISTRATIVE SERVICES SL ASSISTANT SHI FT SUPERVISOR H MECHANICAL SUPERVISOR H INSTRUMENT SUPERVISOR
,_______. H FIRE MARSHALL e
OL CONTROL ROOM OPERATOR - ELECTRIC/IL SUPERVISOR I I
I I
- ENGINEERING SUPERVISOR - STATION SECURITY SUPERVISOR
- I' CONTROL ROOM OPERIITOI\ TRAINEE *~-*
I SUPERVISOR SAFETY ENGINEERING LfGEND
/IUXILIIIRY SL - SENIOR LICENSE OPERATOR OL - OPERA TOR'S LICENSE
..
- COMMUN/CATIONS SURRY POWER STATION ORGANIZATION C,HART
e eTS 6.2-l 6.2 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE IN STATION OPERATION Specification A. Any reportable occurrence shall be reported innnediately to and pro~ptly reviewed by the Chairman-Station Nuclear Safety and Operating Committee or his designee, Manager-Nuclear Operations and Maintenance, and the Chairman-System Nuclear Safety and Operating Committee. Prompt corrective action shall be taken to correct the anomaly.
B. A qualified individual shall prepare a written report for each reportable occurrence for submittal to the NRG. This report shall include an evalua-tion of the cause of the occurrence and also recommendations for appropriate action to prevent or reduce the probability of a recurrence.
C. Copies of all such reports shall be submitted to the Superintendent-Operations, the Station Manager, who also serves as the Chairman-Station Nuclear Safety and Operating Committee, Manager-Nuclear Operations and Maintenance, and to the Chairman-System Nuclear Safety and Operating Coilli~ittee for review and approval of any recommendationn D. A duly authorized executive of the Company, or designee, shall report the circumstances of any reportable occurrence to the NRC as specified in Section 6.6.2 of these Specifications.
e TS 6.3-1 6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Specification A. Should a safety limit (see Section 2.0 of the Technical Specifications) be exceeded, the reactor shall be placed at least in hot shutdown within one hour. Reactor operation shall only be resumed in accordance with the authorization within 10 CFR 50.36 (c)(l)(i}.
B. A report of the incident shall be made to the NRG, the Manager-Nuclear Operations and Maintenance, and the Chairman of the System Nuclear Safety and Operating Committee within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. DELETED D. A complete analysis of the incident together with recommendations to prevent recurrence shall be prepared. A Safety Limit Violation report shall be reviewed and approved by the Station Nuclear Safety and Operating Committee. The report shall be forwarded to the NRG, and the Chairman of the System Nuclear Safety and Operating Committee within 14 days of the violation.
- e TS 6.4-5
- 1. Administrative Station Manager 2o Abnormal Superintendent-Operations
- 3. Annunciator Superintendent-Operations I
- 4. Health*Physics Supervisor-Health Physics 5 .. Emergency Superintendent-Operations t
- 6. Maintenance Mechanical Supervisor Electrical Supervisor Instrument Supervisor
- 7. Operating Superintendent-Operations t
- 8. Periodic Test Engineering Supervisor
- 9. Start-up Test Engineering Supervisor
- 10. Special Test Engineering Supervisor
- 11. Quality Assurance Resident-Quality Control i
Engineer
- 12. Chemistry Supervisor-Chemistry Such changes will be documente.d and subsequently reviewed by the Station Nuclear Safety and Operation Committee and approved by the Station Manager.
G. In cases of emergency, operations personnel shall be authorized to depart from approved procedures where necessary to prevent injury to personnel or damage to the facility. Such changes shall be doc1.I1Thented and reviewed by the Station Nuclear Safety and Operating Committee and approved by the Station Manager.
e ATTACHMENT 2 Assistant Station Manager - Surry.Power Station - Robert F. Saunders Formal Education BS Mechanical Engineering with Nuclear Option, Virginia Polytechnic Institute and State University, 1970.
Professional Engineering License - State of Virginia, October 197 6 ..
Training Senior Reactor Operator License Surry Nuclear Power Station, December 1977.
Experience July 1961 to September 1965, Designer in the Atomic Power Design Division with Newport News Shipbuilding and Drydock Company.
September 1973 to April 1975, Nuclear Construction Super-visor with Newport News Shipbuilding and Drydock Company.
April 1975 to March 1976, Associate Engineering with Vepco, Surry Power Station.
March 1976 to September 1977, Engineer, Surry Power Station.
September 1977 to January 1979, Engineering Supervisor, Surry Power Station.
January 1979 to May 1980, Superintendent - Maintenance, Surry Power Station.
Present Position May 19EO.