ML18150A139

Proposed Tech Specs Re Reorganization of QA Organization

ML18150A139
Person / Time
Site:	Surry
Issue date:	06/03/1987
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18150A128	List: ML18150A127 ML18150A139
References
NUDOCS 8706100036
Download: ML18150A139 (10)

Text

ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE (---B-70_6_1 o-o=--0=3=-6--;-----;s:;-::7=--:o=-6:--:0:-:3:---

P DR ADOCI.<. 05000280 p PDR \ SURRY POWER STATION UNIT NOS. 1 AND 2 e TS 6.1-12 6. Any other matter involving safe operation of the nuclear power stations which is referred to the Director -Safety Evaluation and Control. 7. Reports and meeting minutes of the Station Nuclear Safety and Operating Committee.

f. Authority The Supervisor-IOER shall report to and advise the Director -SEC regarding any safety concern discovered during the independent review process the Director -Safety Evaluation and Control shall report to and advise the Manager -Nuclear Programs and Licensing, who shall advise the Vice President

-Nuclear Operations on those areas of responsibility specified in Section 6.1.C.2.e.

g. Records Records of IOER 6.1.C.2.e shall activities be prepared required by Specification and maintained in the SEC files and a summary shall be disseminated each calendar month as follows: 1. Vice President

-Nuclear Operations

2. Nuclear Power Station Managers 3. Manager -Nuclear Operations Support 4. Manager -Nuclear Programs and Licensing

5. 6. Manager -Corporate Quality Assurance Others that the Director -Safety Evaluation and Control may designate

'* e e TS 6.1-14 6. The Station Security Plan and implementing procedures at least once per 12 months. 7. Any other area of facility operation considered appropriate by the Manager -Corporate Quality Assurance or the Senior Vice President

-Power Operations.

8. The Station Fire Protection Program and implementing procedures at least once per 24 months. 9. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm. 10. An inspection and audit of the fire prevention program shall be performed by protection a qualified fire consultant at least once per 36 months. and loss outside 11. The radiological environmental monitoring program at least once per 12 months. 12. The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months. I _I TS 6.l-14a 13. The Process Control Program and implementing procedures for processing and packaging of radioactive waste at lest once per 24 months. b. Authority The Quality Assurance Department shall report to and advise the Manager -Corporate Quality Assurance, who shall advise the Senior Vice President

-Engineering and Construction on those areas of responsibility specified in Specification 6.1.C.3.a above.

.. TS 6.1-15 c. Records Records of the Quality Assurance Department audits shall be prepared and maintained in the department files. Audit reports shall be disseminated as indicated below: 1. Vice President

-Nuclear Operations

2. Nuclear Power Station Manager 3. Manager -Nuclear Operations Support 4. Manager -Corporate Quality Assurance

5. Manager -Nuclear Programs and Licensing

6. Director -Safety Evaluation and Control 7. Supervisor of area audited 8. Nuclear Power Station Manager -Quality Assurance

\ Figure 6.1-1 Offsite Organization for Facility Management and Technical Support PRESIDENT POWER COMPANY SENIOR VICE PRESIDENT POWER OPERATIONS SENIOR VICE PRESIDENT ENGINEERING

& CONSTRUCTION

...---------------------1

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MANAGER MAINTENANCE

& PERFORMANCE SERVICES MANAGER POWER TRAINING SERVICES MANAGER NUCLEAR OPERATIONS SUPPORT VICE PRESIDENT NUCLEAR OPERATIONS*

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I !~iii"" 1 I I DIRECTOR HEALTH PHYSICS DIRECTOR OPERATIONS

& MAINTENANCE SUPPORT DIRECTOR ADMINISTRATIVE . SERVICES

• Responsible for Corporate Fire Protection Program MANAGER NUCLEAR PROGRAMS AND LICENSING I SUPERVISOR CORPORATE EMERGENCY PLANNING I MANAGER CORPORATE QUALITY ASSURANCE DIRECTOR SAFETY EVALUATION AND CONTROL ---Communications CJ Onsite e UPERINTENDENT NUCLEAR TRAINING SUPERVISOR PLANNING AND SUPPORT SERVICES UPERINTENDENT OPERATIONS SL SHIFT SUPERVISOR SL ASST. SHIFT SUPERVISOR SL CONTROL ROOM OPERATOR OL CONTROL ROOM OPERATOR/

TRAINEE SL -Senior License OL -Operator's License ---Communications CJ Off-site ASSISTANT STATION MANAGER (O&M) UPERINTENDENT MAINTENANCE SUPERVISOR MECHANICAL MAINTENANCE SUPERVISOR ELECTRICAL MAINTENANCE SUPERVISOR MAINTENANCE SERVICES UPERINTENDENT TECHNICAL SERVICES SUPERVISOR CHEMISTRY INSTRUMENT SUPERVISOR SUPERVISOR SURVEILLANCE AND TEST ENGINEERING SUPERVISOR PLANT ENGINEERING STATION MANAGER UPERINTENDENT PROJECTS LICENSING COORDINATOR ASSISTANT STATION MANAGER (NS & L) SUPERVISOR SAFETY ENG. NUCLEAR SHIFT TECHNICAL ADVISORS MANAGER QUALITY ASSURANCE SUPERVISORS QUALITY STATION SECURITY SUPERVISOR

--_I UPERINTENDENT HEALTH PHYSICS SUPERVISOR ADM IN ISTRA TIVE SERVICES COORDINATOR SUPERVISOR BUSINESS EMERGENCY RECORDS SYSTEMS PLANNING MANAGEMENT SUPERVISOR STATION SUPERVISOR SAFETY PERSONNEL COORDINATOR SERVICES ST A TION LOSS PREVENTION COORDINATOR Figure 6.1-2 SURRY POWER STATION ORGANIZATION CHART -

e ' , ATTACHMENT 2 SAFETY EVALUATION SURRY POWER STATION UNIT NOS. 1 AND 2 e --,, Description of Change This proposed change will modify Section 6 of the Surry Technical Specifications to reflect a company reorganization in which the Quality Assurance organization will now report to the Senior Vice President Engineering and Construction, rather than the Senior Vice President

-Power Operations.

It also changes the titles of several on-site and off-site managers and supervisors, and deletes the Director, Nuclear Training.

As the major emphasis of the Company's nuclear program is on operations rather than construction, it is appropriate that the QA organization report to Engineering and Construction to enhance the independence of the QA organization.

Basis for No Significant Hazards Consideration The proposed amendment does not involve a significant hazards consideration because operation of Surry Units 1 and 2 in accordance with the change would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated.

This change merely revises where the QA organization reports to enhance independence and corrects titles in the on-site and off-site organization charts. Thus, this change does not change plant design or operation and does not increase the probability or consequences of an accident.

(2) create the possibility of a new or different kind of accident from any previously analyzed.

It has been determined that a new or different kind of accident will not be possible due to this change. Realigning the QA organization with Engineering and Construction, revising supervisor or manager titles or deleting the Director, Nuclear Training position do not create the possibility of a new or different kind of accident.

(3) involve a significant reduction in a margin of safety. This change doesn't involve a change in the basis for any Technical Specification or the Updated Final Safety Analysis Report accident analysis.

Therefore, the change doesn't involve a significant reduction in the margin of safety. 50.59 Safety Review The proposed change does not involve a unreviewed safety question because operation of Surry Units 1 and 2 in accordance with this change would not: (1) increase the probability of occurrence or consequences of an accident or malfunction of equipment previously evaluated in the safety analysis report because these organizational changes and titles do not effect plant design or operations; (2) increase the possibility of an accident or malfunction of a different type than previously evaluated in the safety analysis report because the organization change does not effect plant design or operations.

, (3) reduce the margin of safety Specification because the Technical Specification or safety analysis.

as defined in change does the Updated the not Final e basis for a Technical effect the basis of any Safety Analysis Report Pursuant to 10 CFR 50.59 and 50.92, it has been determined that this change does not involve a unreviewed safety question or a significant safety hazards consideration.