ML20082N887
| ML20082N887 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/21/1995 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082N889 | List: |
| References | |
| NUDOCS 9504250431 | |
| Download: ML20082N887 (11) | |
Text
.
v# " %,
j
-d UNITED STATES g-g j
NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20556-4001
%...../
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 197 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 6, 1994, as supplemented March 7, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i)" that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
L 9504250431 950421 PDR ADOCK 05000290 p
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION N
David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 21, 1995 t
l ps***%
-fe ol UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20565-4001
,o t
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.197 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 6, 1994, as supplemented March 7, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
e
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.197, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Y
David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 21, i995
9
. ATTACHMENT TO LICENSE AMENDMENT 197 TO' FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.
AMENDMENT NO. 197 TO FACILITY OPERATING LICENSE NO. DPR-37 i
DOCKET NOS. 50-280 AND 50-281 f
x Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 6.1-7 TS 6.1-7 TS 6.1-10 TS 6.1-10 TS 6.1-11 TS 6.1-11 TS 6.4-3 TS 6.4-3 TS 6.4-4 TS 6.4-4 TS 6.4-5 TS 6.4-5 1
f f
i l
t
i TS 6.1-7 f.
Responsibilities The SNSOC shall be responsible for:
1.
Review of a) all new normal, abnormal, and emergency operating procedures and all new maintenance procedures, b) all procedure changes that require a safety evaluation, and c) any other procedures or l
changes thereto as determined by the Station Manager which affect ~
nuclear safety.
2.
Review of all new test and experiment procedures that affect nuclear l
safety.
3.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
4.
Review of proposed changes to Technical Specifications and shall i
submit recommended changes to the Station Manager.
5.
Investigation of all violations of the Technical Specifications, including l
the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear i
Operations and to the Management Safety Review Committee.
l 6.
Review on all Reportable Events and special reports submitted to the l
{
NRC.
7.
Review of facility operations to detect potential nuclear safety hazards.
8.
Performance of special reviews, invettigations or analyses and report thereon as requested by the Chairman of the SNSOC or Station l
Manager.
l Amendment Nos.197 and 197 L
i i
TS 6.1-10 e.
Meeting Frequency The MSRC shall meet at least once per calendar quarter.
f.
Ouorum i
The minimum' quorum of the MSRC necessary for the performance of the MSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated afternate and at least 50% of the MSRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.
g.
Review t
The MSRC shall be responsible for the review of:
1.
Safety evaluations as programmatically discussed in the Updated Final Safety Analysis Report for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to assess the effectiveness of the safety evaluation program and to verify that the reviewed actions did not constitute an unreviewed safety question.
2.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR. 3.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59,10 CFR. 4.
Proposed changes to Technical Specifications or the Operating Licenses.
t Amendment Nos.197 and 197
TS 6.1-11 5.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
6.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
7.
Events requiring written notification to the Commission.
8.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
9.
A representative sample of reports and meeting minutes of the SNSOC.
h.
Audits Audits of facility activities shall be performed under the cognizance of the MSRC. These audits shall encompass:
1.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.
l 2.
The performance, training and qualifications of the entire facility staff.
3.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear j
safety.
j i
Am>ndment Nos.197 and 197
3 TS 6.4-3 i
2.
The requirements of 6.4.B.1 above, shall also apply to each high radiation area in which the intensity of-radiation is greater than 1000 mrem /hr, but less than 500 rads /hr at one meter from a radiation source or any surface through which radiation penetrates. In addition, locked j
doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the senior station individual assigned the responsibility for health physics and radiation protection.
3.
Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
Process Control Program implementation.
i b.
Offsite Dose Calculation Manual implementation.
C.
All procedures described in 6.4.A and 6.4.B shall be reviewed and approved by j
the Station Nuclear Safety and Operating Committee (SNSOC) prior to implementation.
Subsequent procedure changes that require a safety evaluation shall also be reviewed and approved by SNSOC prior to implementation.
All other changes shall be independently reviewed and approved as discussed in the Updated Final Safety Analysis Report.
I i
Amendment Nos.197 and 197 i
i TS 6.4-4 f
i D.
All procedures described in Specifications 6.4.A and 6.4.B shall be followed.
t E.
Deleted j
F.
Deleted.
G.
In cases of emcigency, 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 documented, reviewed and j
approved by the Station Nuclear Safety and Operating Committee.
l l
i i
t f
t I
I i
l i
i t
i Amendment Nos.197 and 197 i
w e
w+-r w
m
TS 6.4-5 This page intentionally left blank.
Amendment Nos.197 and 197