ML20064C856
| ML20064C856 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  (DPR-32-A-188, DPR-37-A-188, NPF-4-A-180, NPF-7-A-161) |
| Issue date: | 03/01/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064C859 | List: |
| References | |
| NUDOCS 9403100283 | |
| Download: ML20064C856 (31) | |
Text
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UNITED STATES a
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NUCLEAR REGULATORY COMMISSION k..u,/
WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 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 July 20, 1993, 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 it reasonable assurance (1) 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.
)
9403100283 940301 PDR ADOCK 05000280 P
. 2.
Accordingly, the license is amended by changes tt-the Technical l
Specifications as indicated in the attachment to 'his license amendment, l
and paragraph 3.8 of Facility Operating License No. OPR-32 is hereby l
amended to read as follows:
l (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.188, are hereby incorporated in the license.
i The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
l FOR THE NUCLEAR REGULATORY COMMISSION l
l' l
He bert N. Berkow, Director Project Directorate II-2 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 1, 1994
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S UNITED STATES NUCLEAR REGULATORY COMMISSION
- gj WASHINGTON, D.C. M555-0001 l
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 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 July 20, 1993, 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 l
1
. +,
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. OPR-37 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.108, 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 W
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 1, 1994 l
l l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0. 188 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. DPR-37 QOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paati 6.1-8 6.1-8 6.1-11 6.1-11 6.1-12 6.1-12 6.4-6 6.4-6 6.5-3 6.5-3
TS 6.1-8 t
i 9.
Deleted.
10.
Deleted.
l 11.
Review of every unplanned onsite release of radioactive material j
to the environs exceeding. the limits of Specification 3.11 j
including the preparation 'of reports covering evaluation, recommendations and disposition of the corrective action to
[
prevent recurrence and the forwarding of these reports to the Vice t
i President - Nuclear Operations and to the Management Safety Review Committee.
l 12.
Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
i l
g.
Authority l
The SNSOC shall:
i 1.
Provide written approval or disapproval of items considered under E
(1) through (3) above. SNSOC approval shall be certified in writing by an Assistant Station Manager.
2.
Render determinations in writing whh regard to whether or not each item considered under (1) through (5) above constitutes an unreviewed safety question.
3.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -
Nuclear Operations and to the Management Safety. Review Committee of disagreement between SNSOC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.A above.
h.
Records The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Operations and to the Management Safety Review Committee.
Amendment Nos.188 and 188
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 l
in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
9.
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 i
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.
i 3.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety, Amendment Nos.188 and 188
TS 6.1-12 4.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50.
5.
Any other area of facility operation considered appropriate by the MSRC or the Vice President - Nuclear Operations.
I 6.
The Fire Protection Program and implementing procedures.
7.
An independent fire protection and loss prevention inspection and audit shall be performed utilizing an outside qualified fire consultant.
+
8.
The radiological environmental monitoring program.
9.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.
10.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive waste.
i Amendment Nos.188 and 188
I TS 6.4-6 l
i H.
l Practice of site evacuation exercises shall be conducted annually, following emergency procedures and including a check of communications with off-site report groups.
I.
Deleted.
l l
J.
Deleted.
l 1
l K.
Systems intecrity The licensee shall implement a program to reduce leakage from systerns l
outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visua!
l inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
i l
Amendment Nos.188 and 188 i
l TS 6.5-3 9.
' Records of the service lives of all hydraulic and mechanical snubbers on safety related systems, including the data at which the service life commences and associated installation and l
maintenance records.
l 10.
Records of the Station Emergency Plan and implementing procedures audits.
l 11.
Records of the Station Security Plan and implementing procedures audits.
12.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
I Amendment Nos.188 and 188 w
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[k UNITED STATES iS(w ~j NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20555-4001 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION. UNIT N0. 1
.A_M1NJMENT TO FACILITY OPERATING LICENSE i
Amendment No.180 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 20, 1993, 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 3
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
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 d
E.
The issuance of this amendment is in a.cordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Speci-3 fications as indicated in the attachment to this license amendment, and i
paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
j (2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, are hereby incorporated in the l
license. The licensee shall operate the facility in accordance with the. Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
4 FOR THE NUCLEAR REGULATORY COMMISSION
/
I Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 1, 1994
ATTACHMENT TO LICENSE AMENDMENT N0.180 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 50-338 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by 1
amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Paaes
-Insert Paaes 4
6-6 6-6 6-9 6-9 6-10 6-10 6-13 6-13 6-22 6-22 t
T l
L I
i 4
i ADMINISTRATIVE CONTROLS l
MEETNG FREQUENCY j
6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated alternate.
C1.ER.N 6.5.1.5 A quorum of the SNSOC consists of the Chairman or Vice-Chairman and two members including alternates.
I RESPONSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:
l a.
Review of 1) all procedures required by Specifications 6.8.1, 6.8.2 and 1
6.8.3 and changes thereto, 2) all programs required by Specification 6.8.4 and changes thereto,3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety,
- b. Review of all proposed tests and experiments that affect nuclear safety.
j i
Review of all proposed changes or modifications to plant systems or c.
j equipment that affect nuclear safety.
d.
Review of all proposed changes to Appendix "A" Technical Specifications and i
Appendix "B" Environmental Protection Plan. Recommended changes shall be j
submitted to the Station Manager.
Investigation of all violations of the Technical Specifications including the 4
e.
j preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Operations and the MSRC.
f.
Review of all REPORTABLE EVENTS and Special Reports.
g.
Review of facility operations to detect potential nuclear safety hazards.
i
- h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee or Station Manager.
1.
Deleted.
l
- j. Deleted.
1 NORTH ANNA - UNIT 1 6-6 Amendment No.180 i
s
ADMINISTRATIVE CONTROLS
- e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance, f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g.
Events requiring written notification to the Commission.
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
l.
Reports and meetings minutes of the SNSOC.
AUDITS 4
6.5.2.8 Audits of facility activities shall be performed under the cognizance of the MSRC. These audits shall encompass:
- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.
l
- b. The performance, training and qualifications of the entire facility staff.
l
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.
l
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50.
Any other area of facility operation considered appropriate by the MSRC or e.
the Vice President - Nuclear Operations.
f.
The Fire Protection Program and implementing procedures, l
- g. An independent fire protection and loss prevention inspection and audit shall be performed utilizing an outside qualified fire consultant.
- h. The Radiological Environmental Monitoring Program and the results thereof.
NORTH ANNA UNIT 1 6-9 Amendment No.180 1
4 I
ADMINISTRATIVE CONTROLS l
- i. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.
J. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes.
AUTHORITY 6.5.2.9 The MSRC shall report to and advise the Senior Vice President - Nuclear on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of MSRC activities shall be prepared, approved and distributed as indicated below;
- a. Minutes of each MSRC meeting shall be prepared, approved and forwarded.to tho Senior Vice President - Nuclear within 14 days of each meeting.
- b. Reports of reviews with safety significant findings encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior V'ce President - Nuclear within 14 days following completion of the review.
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
NORTH ANNA - UNIT 1 6-10 Amendment No.180
ADMINISTRATIVE CONTROLS i
- c. Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
- h. OFFSITE DOSE CALCULATION MANUALimplementation.
- i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.
6.8.2 Each procedure of 6.8.1 above, except 6.8.1.d. 6.8.1.e and 6.8.1.f and changes thereto, shall be reviewed and approved by the SNSOC prior to implementation and reviewed periodically as set forth in administrative procedures. Procedures of 6.8.1.d, 6.8.1.e, and 6.8.t.f shall be reviewed and approved as set forth in the facility's Security Plan, Emergency Plan, and section 6.5.1.6.m of the Technical Specifications, respectively. SNSOC approval shall be certified in writing by an Assistant Station Manager.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
i
- c. The change is documented, reviewed, and approved by the SNSOC within 14 1
days of implementation. SNSOC approval shall be certified in writing by an Assistant Station Manager.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the recirculation spray, safety injection, chemical and volume control, gas stripper, and hydrogen recombiners.
The program shall include the following:
(i) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
NORTH ANNA - UNIT 1 6-13 Amendment No.180 i
5 ADMINISTRATIVE CONTROLS
- b. In-Pfant Radiation Monitonrg i
A program which will ensure the capability to accurately determine the airbome iodine concentration in vital areas under accident conditions. This program shall include the following:
i (i)
Training of personnel, (ii)
Procedures for monitoring, and (iii)
Provisions for maintenance of sampling and analysis equipment.
c.
Secondarv Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shallinclude:
I (i)
Identification of a sampling schedule for the critical variables and control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, f
(iii)
Identification of process sampling points, which shallinclude monitoring the discharge of the condensate pumps for evidence of condenser inleakage, (iv)
Procedures for the recording and management of data, (v)
Procedures defining corrective actions for all control point chemistry conditions, j
and (vi)
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-Accident Samolina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following-1 (i)
Training of personnel, (ii)
Procedures for sampling and analysis, 4
(iii)
Provisions for maintenance of sampling and analysis equipment.
I NORTH ANNA UNIT 1 613a Amendment No.40:4iG,169 a
ADMINISTR ATIVE CONTROLS (Cominued) l SPECIAL REDORTS l
6.9.2 Special reports shall be submitted to the Regional Administrator, Region ll, within the time period specified for each report. These reports shall be submitted pursuant to the j
requirement of the applicable specification:
- a. Inservice inspection Reviews, Specification 4.0.5, shall be reported within 50 days of completion,
- b. MODERATOR TEMPERATURE COEFFICIENT. Wion 3.1.1.4.
I
- c. RADIATION MONITORING INSTRUMENTATION. Specification 3.3.3.1. Table 3.3 6, i
1 Action 35.
- d. SEISMIC INSTRUMENTATION. Specifications 3.3.3.3 and 4.3.3.3.2.
- e. METEOROLOGICAL INSTRUMENTATION. Meion 3.3.3.4.
f.
Deleted.
j g.
LOOSE PARTS MONITORING SYSTEMS. Spoofication 3.3.3.9.
i h.
REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Speedication 3.4.8.
l
- i. OVERPRESSURE PROTECTION SYSTEMS. Specifcation 3.4.9.3.
- j. EMERGENCY CORE COOUNG SYSTEMS. S;+?-Mi-:-7 3.5.2 and 3.5.3.
- k. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
1.
GROUND WATER LEVEL SERVICE WATER RESERVOIR. Specification 3.7.13.
- m. Deleted.
- n. RADIOACTIVE EFFLUENTS. As reqwed by the ODCM
- o. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM
- p. SEALED SOURCE CONTAMINATION. Spodfication 4.7.11.1.3.
- q. REACTOR COOLANT SYSTEM GTRUCTURAL NTEGRITY. Spedcation 4.4.10. For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor-Coolant System pressure boundary detected durin0 the performance of Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.
I NORTH ANNA UNIT 1 6 21 Amendment No. 3.H.53.
N.103.1H.140, SEP 131990
ADMINISTRATIVE CONTROLS
- r. CONTAINMENT STRUCTURAL INTEGRITY, Specification 4.6.1.6.
For any abnormal degradation of the containment structure detected during the performance of Specification 4.6.1.6, an initial report shall be submitted within 10 days after the completion of Specification 4.6.1.6.
A final report, which includes (1) a description of the condition of the liner plate and concrete. (2) inspection procedure, (3) the tolerance on cracking, and (4) the corrective actions taken, shall be submitted within 90 days after the completion of Specification 4.6.1.6.
~
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
Records and logs of facility operation covering time interval at each power a.
- level,
- b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
- c. ALL REPORTABLE EVENTS and Special Reports.
d.
Records of surveillance activities, inspections and calibrations required 'by
~
these Technical Specifications.
e.
Records of changes made to Operating Procedures.
f.
Records of radioactive shipments.
g.
Records of sealed source leak tests and results.
- h. Records of annual physical inventory of all sealed source material of record.
- i. Records of the Station Emergency Plan and implementing procedures audits.
J. Records of the Station Security Plan and implementation procedures audits.
6.10.2 The following records shall be retained for the duration of the Facility Operating Ucense:
NORTH ANNA UNIT 1 6-22 Amendment No.180 l
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UNITED STATES 1[
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-339 NORTH ANNA POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.161 License No. NPF-7 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 20, 1993, complies with the i
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set j
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; l
C.
There is reasonable assurance (1) 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 l
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.
1
.. A
I c.
< l 2.
Accordingly, the license is amended by changes to the Technical Speci-l fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 161
, 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 H rbert N. Berkow, Director i
Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: March 1, 1994 l
I t
... l
ATTACHMENT TO LICENSE AMENDMENT NO.161 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET N0. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Paaes Insert Paaes 6-7 6-7 6-10 6-10 6-11 6-11 6-14 6-14 6-22 6-22 l
ADMINISTRATIVE CONTROLS MEET 1NG FREQUENCX 6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated altemate.
CUDRLM 6.5.1.5 A quorum of the SNSOC consists of the Chairman or Vice Chairman and two members including alternates.
RESPONSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:
a.
Review of 1) all procedures required by Specifications 6.8.1, 6.8.2 and 6.8.3 and changes thereto, 2) all programs required by Specification 6.8.4 and changes thereto,3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety,
- b. Review of all proposed tests and experiments that affect nuclear safety.
- c. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
d.
Review of all proposed changes to Appendix "A" Technical Specifications and Appendix "B" Environmental Protection Plan. Recommended changes shall be submitted to the Station Manager.
e.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Operations and the MSRC.
f.
Review of all REPORTABLE EVENTS and Special Reports.
g.
Review of facility operations to detect potential nuclear safety hazards,
- h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee or Station Manager.
- i. Deleted.
J. Deleted.
NORTH ANNA - UNIT 2 67 Amendment No. 161
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The MSRC shall be composed of the MSRC Chairman and a minimum of four MSRC members. The Chairman and all members of the MSRC shall have qualifications that meet the requirements of Section 4.7 of ANSI /ANS 3.1-1979 Rev. 1 (Draft).
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the HSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in MSRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants should be utilized as determined by the MSRC Chairman to provide expert advice to the MSRC.
MEETING FREQUENCY 6.5.2.5 The MSRC shall meet at least once per calendar quarter.
QUORUM i
6.5.2.6 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 alternate and at least 50% of the HSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 The MSRC shall be responsible for the review of:
The safety evaluations for 1) changes to procedures, equipment a.
or systems and 2) tests or experiments completed under the i
provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR, c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License.
NORTH ANNA - UNIT 2 6-9 Amendment No. II,H,118, i
ADMINISTRATIVE CONTROLS
- e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Sig,'ificant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety, g.
Events requiring written notification to the Commission.
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
- i. Repons and meetings minutes of the SNSOC.
AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the MSRC. These audits shall encompass:
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- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.
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- b. The performance, training and qualifications of the entire facility staff.
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- c. The results of actions taken to correct deficiencies occurring !n facility equipment, structures, systems or method of operation that affect nuclear safety.
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- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50.
- e. Any other area of facility operation considered appropriate by the MSRC or the Vice President - Nuclear Operations, f.
The Fire Protection Program and implementing procedures.
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- g. An independent fire protection and loss prevention inspection and audit shall be performed utilizing an outside qualified fire consultant.
- h. The Radiological Environmental Monitoring Program and the results thereof.
h NORTH ANNA UNIT 2 6 10 Amendment No.161
ADMINISTRATIVE CONTROLS 1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.
J. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes.
AUTHORITY 6.5.2.9 The MSRC shall report to and advise the Senior Vice President - Nuclear on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
4 RECORDS 6.5.2.10 Records of MSRC activities shall be prepared, approved and distributed as indicated below:
- a. Minutes of each MSRC meeting shall be prepared, approved and forwarded to the Senior Vice President Nuclear within 14 days of each meeting.
- b. Reports of reviews with safety significant findings encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President - Nuclear within 14 days following completic.1 of the review.
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- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
l NORTH ANNA - UNIT 2 6-11 Amendment No.161
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4 THIS PAGE IS LEFT INTENTIONALLY BLANK I
i AmendmentNo.JJ,37,$].,$S,73, NORTH ANNA - UNIT 2 6-12 u,
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l ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The followir.g 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 SNSOC and the results of this review shall be submitted to the Vice President-Nuclear.0perations and the MSRC.
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6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within i
one hour.
The NRC Operations Center shall be notified by telephone as scbn b.
as possible and in all cases within one hour. The Vice President-Nuclear' 0perations'and 'the MSRC shall be notified within
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24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A.%fety Limit Violation Report shall be prepared. The report c.
sht ' be reviewed by the SNSOC. This. report 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.
l d.
The Safety Limit Violation Report shall be submitted to the Cnmmission, the Vice President-Neclear Operations ~and the MSRC within 14 days of the violation.
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6.8 PR0CEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendiv A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
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NORTH ANNA - UNIT 2 6-13 AmendmentNo.JJ,447,SS,
- 118, Correction Letter of 10-3-90 i
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ADMINISTRATIVE CONTROLS l
- c. Surveillance and test activities of safety related equipment.
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- d. Security Plan implementation.
e.
Emergency Plan implementation, f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM irnplementation.
- h. OFFSITE DOSE CALCULATION MANUAL implementation.
- i. Quality Assurance Program for effluent and environmental monitoring, using l
the guidance in Regulatory Guide 1.21 Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.
6.8.2 Each procedure of 6.8.1 above, except 6.8.1.d. 6.8.1.e and 6.8.1.f and changes thereto, shall be reviewed and approved by the SNSOC prior to implementation and reviewed periodically as set forth in administrative procedures. Procedures of 6.8.1.d, 6.8.1.e, and 6.8.1.f shall be reviewed and approved as set forth in the facility's Security Plan, Emergency Plan, and section 6.5.1.6.m of the Technical Specifications, j
respectively. SNSOC approval shall be certified in writing by an Assistant Station Manager.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
l
- a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
- c. The change is documented, reviewed, and approved by the SNSOC within 14 days of implementation. SNSOC approval shall be certified in writing by an Assistant Station Manager.
6.8.4 The following programs shall be established, implemented, and maintained:
- a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the recirculation spray, safety injection, chemical and volume control, gas stripper, and hydrogen recombiners.
The program shall include the following:
i (i) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
NORTH ANNA - UNIT 2 6-14 Amendment No.161
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l ADMINISTRATIVE CONTROLS (Continued) 6.10 RECORD RETENTION in addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least f've years r
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- a. Records and logs of facility operation covaring time interval at each power level.
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- b. Records and logs of principal maintenance activities, inspections. repair and 1
replacement of principal items of equipm6nt related to nuclear safety.
- c. Al.L REPORTABLE EVENTS and Special Reports.
l d Records of surveillance activities, inspections and calibrations required by I
these Technical Specifications.
e.
Records of changes made to Operating Procedures.
f.
Records of radioactive shipments.
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g.
Records of sealed source leak tests and results.
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- h. Records of annual physical inventory of all sealed source material of record.
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1.
Records of the Station Emergency Plan and implementing procedures audits.
- j. Records of the Station Security Plan and implementation procedures audits.
6.10.2 The following records shall be retained for the duration of the Facility Operating Ucense:
- a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
1'
- c. Records of facility radiation and contamination surveys.
d Recoids of radiation exposure for all individuals entering radiation control areas.
- e. Records of gaseous and liquid radioactive material release to the environs.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7-1.
NORTH ANNA-UNIT 2 6-22 Amendment No.161 4
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