ML17251A324
| ML17251A324 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/10/1988 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17251A320 | List: |
| References | |
| NUDOCS 8810170249 | |
| Download: ML17251A324 (17) | |
Text
ATTACEiMENT A Revise the Technical Specification pages as follows:
Remove Insert Page 6.1-1 Page 6.2-1 Page 6.5-1 Page 6.5-2 Page 6.5-3 Page 6.5-4 Page 6.5-11 Page 6.6-1 Page 6.7-1 Page 6.8-2 Page Page Page Page Page Page Page Page Page Page Page 6.1-1 6.2-1 6.5-1 6.5-2 6.5-3 6.5-4 6.5-4a 6.5-11 6.6-1 6.7-1 6.8-2 01 oCK Q~~QQQQ 70249 eeioiQ
6.0 6.1 6.1.1 ADMINISTRATIVE CONTROLS RESPONSIBILITY The Superintendent, Ginna Station shall be responsible for overall on-site Ginna Station operation and shall delegate in writing the succession to this responsibility'during his absence.
Amendment No.
gg 6.1-1 Proposed
6.2 6.2.1 ORGANIZATION Onsite and Offsite Or anization An onsite and an offsite organization shall be established for unit operation and corporate management.
The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all Plant management positions.
Those relationships shall be documented and
- updated, as appropriate, in the form of organization charts.
These organization charts will be documented in the UFSAR and updated in accordance with 10CFR50.71.
b.
The Vice President, Production and Engineering, shall have corporate responsibility for overall Plant nuclear
- safety, and shall take any measures needed to assure acceptable performance of the staff in operating, maintaining, and providing technical support in the Plant so that continued nuclear safety is assured.
c.
The Superintendent, Ginna Station shall have responsibility for overall unit operation and shall have control over those resources necessary for safe operation and maintenance of the Plant.
Amendment No.
6.2-1 Proposed
6.5 6.5.1 6.5.1.1 REVIEW AND AUDIT 1
Three separate organizational units shall be established for the purpose of review and audit of plant operations'nd safety-related matters.
One of these will be an on-site operations review
- group, the Plant Operations Review Committee (PORC).
A second is the Quality Assurance (Q.A.)
- group, responsible for the audit of safety-related activities associated with plant operations.
A third is the independent audit and review group, the Nuclear Safety Audit and Review Board (NSARB).
This group is responsible for the periodic review of the activities of the Plant Operations Review Committee, for directing audits and evaluating their results, and for the management evaluation of the status and adequacy of the Quality Assurance program.
PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION The Plant Operations Review Committee shall function to advise the Superintendent, Ginna Station on all matters related to nuclear safety and for referral of appropriate matters to the Nuclear Safety Audit and Review Board.
Corrected, Amendment No.
gg 6.5-1 Proposed
0
COMPOSITION 6.5.1.2 The PORC shall be composed of the; Chairman:
Superintendent, Ginna Station Vice Chairman/Member:" Superintendent-Ginna Support Services Vice Chairman/Member:
Operations Manager Member: Maintenance Manager Member: Instrument
& Control Supervisor Member: Technical Manager Member: Results and Test Supervisor Member: Reactor Engineer Member: Health Physics and Chemistry Manager Member: Nuclear Assurance Manager Member: Quality Control Engineer ALTERNATES
- 6. 5. 1. 3 Alternate members shall be designated by name, in writing t
by the Chairman.
MEETING FRE UENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman.
QUORUM 6.5.1.5 A quorum of the PORC shall consist of the Chairman or Vice Chairman and four members including alternates.
No more than two shall be alternates.
Amendment No.
/jan 6.5-2 Proposed
RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:
a.
Review of
- 1) all procedures required by Specification 6.8 and changes
- thereto, 2) any other proposed procedures or changes thereto as determined by the Superintendent, Ginna Station to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e.
Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Vice President, Production and Engineering, and to the Chairman of the Nuclear Safety Audit and Review Board.
f.
Review of facility operations to, detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Safety Audit and Review Board.
6.5-3 Proposed
0 0
RESPONSIBILITIES (Continued) h.
Review of the Plant Security Plan and shall submit recommended changes to the Chairman of the Nuclear Safety Audit and Review Board.
i.
Review of the Radiation Emergency Plan and shall submit recommended changes to the Chairman of the Nuclear Safety Audit and Review Board.
j.
Review of implementing procedures for the Plant Security Plan and the Radiation Emergency Plan and proposed changes thereto.
k.
Review of all Reportable Events.
AUTHORITY 6.5.1.7 The PORC shall:
a.
Recommend in writing to the Superintendent, Ginna Station approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (d) above constitutes an unreviewed safety question as defined in 10 CFR Section 50.59.
Amendment No.
6.5-4 Proposed
~..
c.
Provide immediate written notification to the Vice President, Production and Engineering, and the Nuclear Safety Audit and Review Board of disagreement between the PORC and the Superintendent, Ginna Station;
- however, the Superintendent, Ginna Station shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Vice President, Production and Engineering, the Chairman of the Nuclear Safety Audit and Review Board, and such others as the Chairman may designate.
i r
I 6.5-4a Proposed
AUTHORXTY 6.5.2e9 a.
The Chairman of-the Nuclear Safety Audit and Review Board is responsible to the President on all activities for which the Review Board is responsible.
b.
The NSARB shall report to and.
advise the Vice President, Production and Engineering, on those areas'f responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of NSARB activities shall be
- prepared, approved, and distributed as indicated below:
a.
Minutes shall be recorded of all meetings of this Board.
Copies of the minutes shall be forwarded within 14 days following each meeting to the Corporate Chairman of the
- Board, Vice President, Production and Engineering and such others as the Chairman of the NSARB may designate.
b.
Reports of reviews encompassed by Section 6.5.2.7 e,f,g and h above, shall be prepared, approved and forwarded to the Vice President, Production and Engineering within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.8
- above, shall be forwarded to the Vice President, Production and Engineering and to the management positions responsible for the areas audited within 30 days after completion of the audit.
Amendment No.
gg 6.5-11 Proposed
6.6 r
6.6.1 REPORTABLE EVZRG.'CTION The following actions shall be taken for Reportable Events:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each Reportable Event shall be reviewed by the PORC and the results of this review shall be submitted to the NSARB and the Vice President, Production and Engineering.
Amendment No.
6.6-1 Proposed
6.7 6.7.1 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:
a.
The provisions of 10 CFR Section 50.36(c)(1)(i) shall be complied with immediately.
b.
The Safety Limit violation shall be reported to the Vice President, Production and Engineering, to the NSARB and to the Commission immediately.
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC.
This report V
shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the
- NSARB, and the Vice President, Production and Engineering within two weeks of the violation.
6.7-1 Proposed
c.
The change is documented, reviewed by the
- PORC, and approved by the Superintendent, Ginna Station within 10 days of implementation.
a 6.8-2 Proposed
C I
1f P
ATTACHME2FZ B This safety evaluation addresses a proposed revision to Section 6
of the Ginna Technical Specifications concerning changes in titles for the corporate positions having responsibility for overall Plant safety.
Specifically requested are changes in title from Senior Vice President, Production and Engineering or Vice President, Electric and Steam Production to Vice President, Production and Engineering, and changes to achieve consistency in the use of the title Superintendent, Ginna Station.
This proposed amendment has been reviewed against the three factors of 10CFR50.92.
It has been determined that the amendment does not involve a significant hazards consideration for the following reasons.
- 1. This change will not result in a significant increase in the probability or consequences of an accident previously evaluated.
The proposed revision does not involve the physical modification of the Plant or equipment.
The proposed change is administrative in nature and affects no
.analyses or responses of the Plant to accident conditions.
- 2. These changes will not create the possibility of a
new or different kind of accident previously evaluated.
As indicated
- above, the proposed revision to the Technical Specifications does not involve a physical modification to the Plant that could result in the creation of an accident not previously analyzed.
- 3. This change does not involve a significant reduction in the margins of safety.
The proposed revision does not in any way alter RG&E's commitment to maintaining a
management structure that contributes to the safe operation and maintenance of Ginna Station.
A single corporate officer is responsible for Plant safety and. will communicate and direct the lines of authority and responsibility for safe nuclear plant operations.
This officer continues to report directly to the President.
A single individual is responsible for overall safe unit operation and maintenance.
P I
1
'll I
5