ML20150D233
| ML20150D233 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/18/1988 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20150D229 | List: |
| References | |
| NUDOCS 8803230207 | |
| Download: ML20150D233 (14) | |
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TABLE 6.2-1" MINIMUM SHIFT CREW COMPOSITION Total Staffing Re_quirements for Station Operation i
With Either or Both Units in Mode 1, 2, 3 or 4 POSITION - NUMBER - CONDITIONS ONE (Shift Supervisor may fulfill duties for both units.)
ONE (If ONE unit is in MODE 5, 6 OR DEFUELED, Senior Reactor Operator is assigned to the Unit in MODE 1, 2, 3 or 4.)
RO -
THREE (ONE Reactor Operator is assigned to each unit PLUS one is
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shared by both units.
g-FOUR (TWO Auxiliary Operators are assigned to each unit.)
STA -
ONE (Shift Technical Advisor may fulfill duties for both units.)
With Both Units in Mode 5 or 6 (or DEFUELED)
POSITION - NUMBER - CONDITIONS ONE (Shift Supervisor may fulfill duties for both unfte.)
SS i
SRO -
NONE RO -
TWO (ONE Reactor Operator is assigned to each unit.)
p-
'IVO (ONE Auxiliary Operators are assigned to each unit.)
STA -
ONE (Shift Technical Advisor may fulfill duties for Both units.)
a-This Table and Table 6.2.1 of Unit 2 Technical Specifications represent Total Station Staffing and ARE NOT ADDITIVE.
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NORTH ANNA - UNIT 1 6-4 8803230207 880318 PDR ADOCK 05000339 P
t ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. These reports shall be submitted pursuant to the ruquirement of the applicable specification:
a.
Inservice Inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion.
b.
MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.
c.
RADIATION MONITORING INSTRUMENTATION.
Specification 3.3.3.1 TABLE 3.3-6 Action 35 d.
SEISMIC INSTRUMENTATION. Specificat?.ons 3.3.3.3 and 4.3.3.3.2.
e.
METEOROLOGICAL INSTRUMENTATION. Specification 3.3.3.4.
f.
FIRE DETECTION INSTRUMENTATION. Specification 3.3.3.7.
g.
LOOSE PARTS MONITORIFG SYSTEMS. Specification 3.3.3.9.
h.
REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Specificatien 3.4.8.
1.
OVERPRESSURE PROTECTION SYSTEMS. Specification 3.4.9.3 j.
EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3.
k.
SETTLEHENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
1.
GROUND WATER LEVEL - SERVICE WATER RESERVOIR. Specification 3.7.13.
m.
FIRE SUPPRESSION SYSTEMS. Specifications 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4 and 3.7.14.6.
n.
RADIOACTIVE EFFLUENTS. Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4 and 3.11.4.
o RADIOLOGICAL ENV!RONMENTAL MONITORINC. Specification 3.12.1.b.
p.
SEALED SOURCE CONTAMINATIO". Specification 4.7.11.1.3.
q.
REACTOR COOLANT SYSTEM STKCCTURAL INTEGRITY. Specification 4.4.10.
For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during 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.
NORTH ANNA - UNIT 1 6-21
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 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:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equfpment 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 annual audit of the Station Emergency Plan and implementing procedures.
J.
Records of the annual audit of the Station Security Plan and implementacion procedures.
l 6.10.2 The following records shall be retained for the duration of the Facility Operating License:
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6-22 NORTH aGL4 - UNIT 1
ADMINISTRATIVE CONTROLS 6.13 - Deleted 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the Semiannual Radioactiva Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and l
l c.
Documentation of the fact that the changes has been reviewed and found seceptable by the SNSOC.
2.
Shall become effective upon review and acceptance by the SNSOC.
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l NORTH ANNA - UNIT 1 6-25
ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES NORTH ANNA POWER STATION UNIT 2 l
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Virginia Electric and Power Coupany
. (3) Initial Test Program VEPCO shall conduct the post-fuel-loading initial test program (set forth in Section 14 of VEPCO's Final Safety Analysis Report, as amended) without making any major modificatians of this program unless modifications have been identified and have received prior Commission approval.
Major modifications are defined as:
(a) Elimination of any test identified in Section 14 of VEPCO's Final Safety Analysis Report, as amended, as essential; (b) Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of VEPCO's Final Safety Analysis Report, as amended, as essential; (c)
Performance of any test at a power level different from there described; and (d) Failure to complete any cests included in the described program (planned or scheduled for power levels up to the authorized power level).
(4) VEPCO shall take the following remedial actions, or alternative actions, acceptable to the Commission, with regard to the environmental qualification requirements for Class IE equipment:
(a) DELETED (b) DELETED (c) VEPC0 shall test the narrow and wide-range resistance temperature detectors for the reactor coolant system by the Loop Current Step Response method each calendar quarter until a long-term qualified resistance temperature detector is available.
Resistance temperature detectors will be replaced if unsatisfactory Loop Current Step Response test results are acquired.
For narrow and wide-range resistance temperature detectors not replaced at a given refueling outage, VEPC0 shall assure that resistance temperature detector cable connectors are adequately sealed and shall use the Arrhenius methodology to affirm that the resistance temperature detector material has not endured significant l
degradation due to environmental parameters. The results of this affirmation shall be added to central environmental qualifications files.
. (d)
DELETED (e)
DELETED (5) Prior to operating the facility at a power level above 25 percent, VEPC0 shall develop a surveillence program for fiberglase c;. ray pond piping and supports that is in compliante with the re gulatory position in Revision 2 of Regulatory Guide 1.72, or an alternative position acceptrble to the Commission.
(6) Prior to operating the facility at a power level above 90 perce't, VEICO shall perform secondary flow stability tests which have bean approved by the Commission.
VEPC0 sh ll provide at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to Office of Inspection and Enforcement (ole) prior to conducting such approved tests so that these teste may be witnessed by the Commission.
The exceptions to Technical Specifications 3.3.2.1(a), 3.3.2.1(b),
3.5.2, 3.7.1.2, and 3.7.1.3, issued with Amendment No. 2 to the Fuel-Load and Low-Power Testing License dated August 1950 shall be in effect until these are completed.
(7) Prior to operating the facility at a power level above 90 perceri, VEPCO shall demonstrate to the satisfaction of the NRC that the actual in-plant measurements of transformer tap settings are in agreement with their analysis.
(8) Prior to operating above 90 percent pawer, VEPC0 shall complete the visual verification of operability of the 37 feedwater system hydraulic snubbers, designated in VEPCO's letter dated August 7,
1980, at operating temperature to the satisfaction of the OIE.
(9) VEPCO is authorized to perform steam generator moisture carryover studies at the North Anna Station. These sendies involve the use of an aqueous tracer solution cf two (2) curies of sodium-24.
The licensee personnel will be in charge of conducting these studies and be knowledgeable in the procedures.
VEPC0 will impose personnel exposure limits, posting, and survey requirements in conformance with those in 10 CFR Part 20 to minimize personnel exposure and contamination during the studies.
Radiological controls will be established in the areas of the chemical feed, feedwater, steam,
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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION Total Staffing Requirements for Station Operation With Either or Both Units in Mode 1, 2, 3 or 4 POSITION - NUMBER - CONDITIONS l
SS -
ONE (Shift Supervisor may fulfill duties for both units.)
SRO -
ONE (If ONE unit is in MODE 5, 6 OR DEFUELED, Senior Reactor Operator is assigned to the Unit in MODE 1, 2, 3 or 4.)
RO -
THREE (ONE Reactor Operator is assignej to each unit PLUS one is shared by bcth units.
Af! -
FOUR (TWO Auxiliary Operators are assigned to each unit.)
STA -
ONE (Shift Technical Advisor may fulfill duties for both units.)
With Both Units in Mode 5 or 6 (or DEFUELED)
POSITION - NUMBER - CONDITIONS SS -
ONE (Shift Supervisor may fulfill duties for both units.)
SRO -
NONE Jt ! -
TWO (ONE Heactor Operator is assigned to each unit.)
f AO -
TWO (ONE Auxiliary Operators are assigned to each unit.)
STA -
ONJ (Shift Technical Advisor may fulfill duties for Both units.)
a-This Table and Table 6.2.1 of Unit 1 Technical Specifications represent Total Station Staffing and ARE NOT ADDITIVE.
NORTH ANNA - UNIT 2 6-4
o ADMINISTRATIVE CONTROLS SPECIAL REFORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report.
These reports shall be submitted pursuant to the requirement of the applicable specification:
a.
Inservice Inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion, b.
MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.
c.
FIRE DETECTION INSTRUMENTATION. Specification 3.3.3.7.
d.
RADIATION MONITORING INSTRUMENTATION.
Specification 3.3.3.1 TABLE 3.3-6 Action 35 e.
REACTOR COOLANT SYSTEM SPECIFIC ACTIVIIT. Specification 3.4.8.
f OVERPRESSURE PROTECTION SYSTEMS. Epecification 3.4.9.3 g.
EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3.
h.
SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
i.
GROUND WATER LEVEL - SERVICE WATER RESERVOIR. Specification 3.7.13.
j.
FIRE SUPPRESSION SYSTEMS. Specifications 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4, 3.7.14.5 and 3.7.14.6.
k.
PENETRATION FIRE BARRIERS. Specification 3.7.15 1.
RADI0 ACTIVE EFFLUENTS. Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4 and 3.11.4.
m RADIOLOGICAL ENVIRONMENTAL MONITORING. Specification 3.12.1.b.
n.
SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.
o.
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specification 4.4.10.
For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during 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.
p.
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 completion of Specification 4.6.1.6.
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final report, which includes (1) a description of the condition of the l
liner plate and concrete, (2) inspection procedure, (3) the tolerance on cracking, and (4) the corrective actions taken, shall be submitted l
l within 90 days after the completion of Specification 4.6.1.6.
l NORTH ANNA - UNIT 2 6-21 lc
ATTACHMENT 3 SAFETY EVALUATION t
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Virginia Electric and Power Company l
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Changes to Technical Specification TABLE 6.2-1, MINIMUM SHIFT CREW COMPOSITION, Units 1 and 2.
DISCUSSION-This change is'to simplify the Shift Composition requirements of Technical
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Specification TABLE 6.2-1 by eliminating =the reduced staffing allowances for operations with one unit in Modes 5 and 6 and by combining the requirements of the current independent but interrelated Units 1 and 2 Technical Specifications.
into a single comprehensive table.
This change will not reduce the requirements from the current Technical Specifications and in fact will increase the staffing requirements when one unit is in Mode.1, 2, 3, or 4 and one unit is in Mode 5 or 6.
Also the change adds the requirement for an additional "A0" which is in accordance with our' commitments in 10 CFR 50 Appendix R Report, Revision 3 (Chapter 5 ATTACEMENT 1, TABLE 1, MINIMUM SHIFT CREW COMPOSITION).
BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION We have reviewed the change rn Technical Specification 6.2.1 and have found that it is similar to 48FR14870, "Examples of Amendments that are not likely to involve significant hazards considerations are listed below," Example (ii)
"A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications:
for example, a more stringent surveillar.cc requirement."
This change will increase the Minimum Shift Crew Composition in accordance with our commitments for 10 CFR 50 Appendix R compliance.
This change will not (a) result in a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident, or (3) result in a significant reduction in the margins of safety, because the change only increases the minimum required shif t crew composition and has no effect on plant design or operation and is in accordance with current operating practices and other regulatory commitments.
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Deletion of Unit 1 Technical Specification 6.13 ENVIRONMENTAL-QUALIFICATION and Unit 2 Facility Operating License, Sections 4.a. 4.b, 4.d, and 4.e.
DISCUSSION Unit 1 Technical Specification 6.13 cnd Unit 2 Facility Operating License Sections 4.a. 4.b,. 4.d, and 4.e are to be deleted in accordance with 10 CFR 50.49.g which provides the schedule for identification of qualified. equipment important to safety and the replacement of equipment important to safety that is not' qualified and. 10 CFR 50.49j which requires the maintenance of an auditabic record of the equipment qualification.
10 CFR 50.49.g also states "The schedule in this paragraph supersedes the
. June 30,
- 1982, deadline, or any other previously imposed date, for environmental qualification of electrical equipment contained in _certain nuclear power operating licenses."
BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION We have reviewed the change to delete Unit 1 Technical Specification 6.13 and Unit 2 Facility Operating License Sections 4.a. 4.b, 4.d, and 4.e and have found that they are similar to 48FR14870, "Examples of Amendments That Are Not Likely To Involve Significant Hczards Considerations Are Listed Below," Example (vii)
"A change to make a license conform to changes in regulations, where the license change results in very minor changes to facility operations cicarly in keeping with the regulations."
10 CFR 50.49 provides the requirements of, or supersedes, the Technical Specifications and Facility Operating License Conditions being deleted.
The change will not (1) result in a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident, or (3) result in a significant reduction in the margins of safety, beceuse the change is administrative and has no impact on plant design or operations.
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Changes to Technical Specifications 6.9.2 SPECIAL REPORTS, Unit 1.
DISCUSSION Technical Specification 6.9.2 will be revised to provide a more complete list of_the Special Reports required by the Technical Specifications.
' Items f.'"LOOSE PARTS MONITORING,"
h.
"0VERPRESSUPE PROTECTION EFFLUENTS,"
- j. "SETTLEMENT OF CLASS 1 STRUCTURES "
1.
"RADI0 ACTIVE EFFLUENTS," and
- m. "RADIOLC01 CAL ENVIRONMENTAL MONITORING" have been added in accordance with the reporting -requirements of the applicable Technical Specifications.
The description of each reporting requirement has been changed to refer specifically to the specification describing the report, where applicable.
This will reduce the possibility of inconsistencies between the reference specification and Section 6.9.2.
In certain cases, the reporting requirement
.is not described in the reference specification, but only in Section 6.9.2 (items a. Inservice Inspection Program Reviews, o.
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY and p. CONTAINMENT STRUCTURAL INTEGRITY).
In these cases, the description has been retained in Specification 6.9.2.
BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION We have reviewed the change to Technical Specification 6.9.2 and have found that it is similar to 48FR14870, "Examples of Amendments That Are Not Likely To Involve Significant Hazards Considerations Are Listed Below," Example (i)
"A purely administrative change to technical specifications:
for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."
The purpose of this change is to achieve consistency between Technical Specification 6.9.2 and the various LCOs ther require the submission of Special
. Reports.
Specification 6.9.2 has been updated to provide a more complete list of Special Reports required by the Technical Specifications.
The change will'not (1) result in a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a ner or different kind of accident, or (3) result in a significant reductton in the mar gins of safety, because the change is administrative and hat no impact en plant design or operations.
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4 Changes to Technical Specification 6.9.2 SPECIAL REPORTS, Unit 2.
b DISCUSSION Technical Specification 6.9.2 will be revised to provide a more complete list of the Special Reports required by the Technical Specifications.
Items.e.
"0VERPRESSURE PROTECTION EFFLUENTS,"
- g. "SETTLEMENT OF CLASS 1 STRUCTURES," h. "GROUND WATER LEVEL - SERVICE WATER RESERVOIR," j. "RADI0 ACTIVE EFFLU ENTS," and
- k. "RADIOLOGICAL ENVIRONMENTAL MONITORING" have been added in accordance with the reporting requirements of the applicable Technical Specifications.
The description of each reporting requirement has been changed to refer specifically to the specification describing the report, where applicable.
This will reduce the possibility of inconsistencies between the reference specification and Section 6.9.2.
In certain cases, the reporting requirement is not described in the reference specification, but only in Section 6.9.2 (items a. Inservice Inspection Program Reviews, m.
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY and n. CONTAINMENT STRUCTURAL INTEGRITY).
In these car.es, the description has been retained in Specification 6.9.2.
BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION We have reviewed the change to Technical Specification 6.9.2 and have found that it is similar to 48FR14870, "Examples of Amendments That Are Not Likely To Involve Significant Hazards Considerations Are Listed Below," Example (i)
"A
. purely administrative change to technical specifications:
for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature."
The purpose of this change is to achieve consistency between Technical Specification 6.9.2 and the various LCOs that require the submission of Special Reports.
Specification 6.9.2 has been updated to provide a more complete list of Special Reports required by the Technical Specifications.
The change will not (1) result in a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident, or (3) result in a significant reduction in the margins of safety, because the change is administrative and has no impact on plant design or operations.