ML20062B002
| ML20062B002 | |
| Person / Time | |
|---|---|
| Site: | North Anna  (NPF-04-A-140, NPF-07-A-123, NPF-4-A-140, NPF-7-A-123) |
| Issue date: | 10/03/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20062B007 | List: |
| References | |
| NUDOCS 9010230290 | |
| Download: ML20062B002 (6) | |
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E BASES sec7ias Td.7 PLANT SYSTrus s
3/4.7.1 T U R B I N E C YC L E.....................................................
B 3/4 7 1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE UMITATION..
B 3/4 7 4 l
3/4.7.3 COMPONENT COOUNG WATER SUBSYSTEM...................
B 3/4 7 4 3/4.7.4 SER VIC E WATER S YSTEM...................................................................
B 3/4 7 4 3/4.7.5 U LTIMAT E H EAT S INK........................................................................
B 3/4 7 5 i
3/4.7.6 FLCoD PROTECTION............................................................................
B 3/4 7 5 3/4.7.7 CONTROL ROOM EMERGENCY HABITABluTY..................................
B 3/4 7 5 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM.....................................
B 3/4 7 5
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3/4.7.9 RESIDUAL HEAT REMOVAL SYSTEMS........................
B3/476-3 / 4. 7.1 o S Ntl B B E R S.....................................................................j 3/4.7.11 SEALED SOURCE CONTAMINATION................................................. B 3/
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3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES................................ B 3/4 7 7 3/4.7.13 GROUNDWATER LEVEL SERVICE WATER RESERVOIR..............
B 3/4 7 9 T4 a KL FCTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. ANDD.C. POWER SOURCES AND D ISTRI B UTI ON............................................................'......... B 3 4
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i 901023029o 901003 PDR ADOCK 05000338 P
PNV y
NORTH ANNA UNIT 2 Xill Amendment No. J 23. -
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!ECDON EfGE 3/d 9 REF1IRIING OPERATONS 3/4.9.1 BORE 0CPCENTRATICN...............................................;...........B 3/4 91 i
3/4.9.2 INSTRUNENTATION...................................................................B i
3/4 91 l
3/4.9.3 DECAY TNE............................................................................. S 3/4 91 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS...
......A 3/4 91 3/4.9.5 C004ANCATIONS................................................................... A 3/4 91 3/4.9.6 MANIPULATOR CRANE OPERABILITY............................... B 3/4. 9 2 3/4.9.7 CRANE TRAVEL.."ENT FUEL PIT..............................................B 3/4 92 3/4.9.8 RESIDUAL HEAT RSAOVAL AND COOUNT CRCULATION..............B 3/4 92 3/4.9.9 CCMA#NENT PURGE APO EXHAUST ISOLATION SYSTBd..........A 3/4 92 3/4.9.10 and 3/4.9.11 WATER LEVEL. REACTOR VESSEL AND SPENT FUEL PIT..............................................A3/4 93 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM........................................B 3/4 93 3/410 spgelALTEST EXosm j
3/4.10.1 SHUTDOWN MARGIN.................................................................. A 3/4 10 1 3/4.10.2 GROUP HEIGHT,NSERTION. AND POWER DISTRIBUTION UMITS.................................................................B 3/4 10 1 3/4.10.3 PHYSIC S TESTS............................................................................ A 3/4 10 1 3/4.10.4 1:EACTOR COQUWT LOOPS..................................................
....B 3/4 10 1 i
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NORTH ANNA UNIT 2 XIV Amendment Dio. 121 j
4.
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l ADMINISTRATIVE CONTROLS I
k.
Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation.
recomendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President-Nuclear Operations and the Management Safety Review Committee.
1 Review changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE.
CALCULATION MANUAL.
m.
Review of the Fire Protection Program and implementing procedures and
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shall submit recommended changes to the Station Manager.
AUTHORITY 6.5.1.7 The SNSOC shall:
i a.
Provide written approval or disapproval of items considered under 6.5.1.6(a) through (c) above.
SNSOC approval shall be certified in writing by an Assistant Station Manager, b.
Render determinations in writing with regard to whether or not eachitemconsideredunder6.5.1.6(a)through(e)aboveconstitutes an unreviewed safety question.
c.
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 the Management Safety Review C6mmittee (MSRC) of disagreement between the SNSOC and the Station Manager; however, the Station Manager shall have ~ responsibility-for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS l
6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Station Manager, the Vice President-Nuclear.Qperations and the MSRC.
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6.5.2 MANAGEMENT SAFETY REVIEW COMMITTEE (MSRC)
FUNCTION j
l 6.5.2.1 The MSRC shall function to provide independent review of designated activities in the areas of:
a.
Station Operations l
b.
Maintenance-c.
Reactivity Management d.
Engineering e.
Chemistry and Radiochemistry f.
Radiological Safety
- g.. Quality Assurance Practices
-=
h-Emergency Preparedness NORTH ANNA - UNIT 2' 6-8
-Amendment No. JJ.)J48,86,1 JJg,-
'123;
l
- r ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The SNSOC shall meet at least once per cal lder month and as convened by tha SNSOC Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the SNSOC consists of the Chairman or Vice-Chhirman and two members including alternates.
RESPONSIBILITIES t
6.5.1.6 The SNSOC shall be responsible for:
Review of 1) all procedures required by Specifications 6.8.1, 6.8.2 a.
and 6.8.3 and changes thereto, 2) all programs required by Specifica-tion 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.
Review of all proposed changes or modifications to plant systems c.
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.
Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evalue-
-tion and recommendations to prevent recurrence to the'Vice President-Nuclear Operations a'nd the MSRC.
f.
Review of all REPORTABLE EVENTS and Special Reports.-
Review of facility operations to detect potential. nuclear safety.
g.
hazards.
h.
Performance of special reviews, investigations 'or analyses and i
reports thereon as requested by the Chairman of the Station Nuclear -
Safety and Operating Committee or Station Manager.
i.
Review of the Plant Security Plan and implementing procedures and shall submit reconsnended changes to the Station Manager.
J.
Review of the Emergency Plan and implementing procedures and shall' submit reconnended changes to the Station' Manager.-
NORTH ANNA - UNIT 2 6 _7 AmendmentNo.JJ,(H7,.p[
118...'
7
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ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.S.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the SNSOC consists of the Chairman or Vice-Chairman and two members including alternates.
RESP 0NSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:
Review of 1) all procedures required by Specifications 6.8.1, 6.8.2 a.
and 6.8.3 and changes.thereto, 2) all programs required by Specifica-tion 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
. c safety.
r Review of all proposed changes or modifications to plant systems l
c.
I or equipment that affect nuclear safety.
d.
Review of all proposed changes to Appen,fix."A"~ Technical
- 1 Specifications and Appendix "B" Environnental Protection Plan.
Recommended changes shall be submitted to the Station Manager.
Investigation of all violations of the' Technical Specifications e.
including the preparation and forwarding of reports covering evalue-tion and reconnendations to prevent ~ recurrence-to the Vice President-Nuclear Operations a'nd the MSRC.
f.
Review of all REPORTABLE EVENTS and Special Reports.
Review of facility operations.to detect potential nuclear safety, g.
- 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.
Review of. the Plant Security Plan and implementing procedures and shall submit recommended changes to the' Station Manager.
s j.' Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Station Manager. -
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NORTH ANNA - UNIT 2.
6-7
.AmendmentNo'.JJ,(?$p,SW,
-118c
.m-
ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 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 SNSOC and the results of this review shall_be submitted to the Vice President-Nuclear Operations and the MSRC.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following &ctions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within one hour, b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The -Vice President-Nuclear Operations and the MSRC shall.be notif.ied within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, A Safety Limit Violation Report shall be prepared.- The report c.
shall 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, d.
The Safety Limit Violation Report shall be submitted to the Cnmmission, the Vice President-Nuclear: 0perations'and the MSRC within 14 days of the violation.
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6.8 PROCEDURES AND PROGRAMS l
6.8.1 Written procedures shall be established, implemented and maintained 1
covering the activities referenced below:
The applicable procedures recomended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February-1978.
b.
Refueling operations.
i NORTH ANNA - UNIT 2 6-13 Amendment No..JJ, MS/,_85,'
l
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+
ADMINISTRATIVE CONTMLS Surveillance and test actMtles of safety related equipment, c.
Security Plan implementation, d.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation, g.
PROCESS CONTROL PROGRAM implementation.
I h.
OFFSITE DOSE CALCUI.ATION MANUAL implementation, l.
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.
I 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 there shall be reviewed and approved by the SNSOC prior to implementation and reviewed per
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l as set forth in administrative procedures. Procedure of 6.8.1.d. 6.8.1.e. and 6.8.1.f shall be reviewed and approved as per certified in writing by an Assistant Station Manager.6.5.1.6.1, 6.5.1.6.], and 6.5.1.6.m. S 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.
i
- 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.
3
- c. The change is docuinented, 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:
3, Primarv thlant Sourcan Outelda Canimir=nt 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 a
injection, chemical and volume control, gas stripper, and hydrogen recombiners.
The program shall include the following:
(l) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for. each system at refueling cycle 1
intervals or less.
' i NORTH ANNA - tjNIT 2 6-14 Amendment No. U,87,123,
.j i
U ADMNSTRATIVE'NJE Surveillance and test actMties of safety related equipment.
c.
d.
Security Plan implementation.
\\
e.
Emergency Plan implementation.
l f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implenantaten.
h.
OFFSITE DOSE CALCULATION MANUAL implementabon, 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.
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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,
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shall be reviewed and approved by the SNSOC prior to implementation and reviewed perio j
as set forth in administrative procedures. Procedure of 6.8.1.d. 6.6.1.e and 6.6.1.f shall be reviewed and approved as per 1
6.5.1.6.1, 6.5.1.6.J. and 6.5.1.6.m. SNSOC approval shall be j
certified in writing by an Assistant Station Manager.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:.
4
- 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 day 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, Primarv f%almet Aameen C '".2 Cs:i..- r.:
l A program to reduce leakage from those portions of systems outside containment 1
that could contain highy 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 (ll) Integrated leak test requirements for each system at refueling cycle intervals or less.
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A1 NORTH ANNA - UNIT 2 6-14 Amendment No'. H.67.123.
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