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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 ML20132E6211996-12-17017 December 1996 Proposed Tech Specs 3/4.7.3 Re Component Cooling Water Sys ML20132B5111996-12-10010 December 1996 Proposed Tech Specs Re Groundwater Level Exceeding Current Maximum Water Level ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML20134H0051996-11-0606 November 1996 Proposed Tech Specs,Modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20134F8781996-09-0404 September 1996 Proposed Tech Specs Requiring Exemption from Certain Requirements of 10CFR50.44, Stds for Combustible Gas Control Sys in Light Water Cooled Power Reactors & 10CFR50.46, Acceptance Criteria for Eccs.. ML20107L3951996-04-25025 April 1996 Proposed Tech Specs,Providing Suppl Info Re Clarification of TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101Q0871996-04-0808 April 1996 Proposed Tech Specs Re EDG Allowed Outage Times ML20101F7971996-03-21021 March 1996 Proposed Tech Specs,Clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguards Area Ventilation Sys ML20097C0171996-01-31031 January 1996 Proposed Tech Specs,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy Portions of SRs Required During Shutdown ML20097J4341996-01-30030 January 1996 Proposed Tech Specs,Modifying Table 3.2-1 of TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9871996-01-23023 January 1996 Proposed Tech Specs,Permitting Use of 10CFR50,App J,Option B performance-based Containment Lrt ML20094N7921995-11-20020 November 1995 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0191995-10-25025 October 1995 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K5921995-10-17017 October 1995 Proposed TS 4.4.5.1,Table 4.4-1,reducing from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20093K6161995-10-17017 October 1995 Proposed Tech Specs,Allowing Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20092J4231995-09-19019 September 1995 Proposed Tech Specs,Increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J3051995-09-19019 September 1995 Proposed Tech Specs,Revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2481995-09-0101 September 1995 Proposed Tech Specs,Allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087A1171995-07-26026 July 1995 Proposed Tech Specs,Increasing Pressurizer Safety Valve Lift Setpoint Tolerance as Well as Reduce Pressurizer High Pressure Rt Setpoint & Allowable Value ML20087A1311995-07-26026 July 1995 Proposed Tech Specs,Clarifying TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20087G3471995-03-30030 March 1995 Proposed Tech Specs Re Changes That Allow One of Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operationin Order to Refurbish Isolated Svc Water Headers 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20211D9201999-08-20020 August 1999 Revised Pages to Third Ten Year ISI Program & Relief Requests ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20195B5881999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna Unit 2 IST Program Plan for Pumps & Valves Second Insp Interval,901214-001214 ML20195B5691999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna,Unit 1 IST Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20205P2511999-05-0101 May 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Program Plan for Third Insp Interval:Components & Component Supports ML20205P2341999-05-0101 May 1999 Rev 0 to Vepc North Anna Unit 1 ISI Program for Third Insp Interval Vol 1:ISI Program for Components & Component Supports for Interval 3 990501-090430 ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20205P2651999-02-0404 February 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Plan for Third Interval for Sys Pressure Tests ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20196K1971998-12-22022 December 1998 Rev 0 to NE-1176, North Anna Unit 1,Cycle 14 Startup Physics Tests Rept, Dec 1998 ML20206N8851998-12-14014 December 1998 Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval ML20206N8711998-11-30030 November 1998 Rev 11,Vol I to ISI Plan for Second Insp Interval for Components & Component Supports ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20236H5311998-07-0101 July 1998 Draft Nuclear Control Room Operator Development Program NAPS Module NCRODP-78 Spent Fuel Dry Storage Cask System. Draft Lesson Plans & Job Performance Measures Included ML20236U8891998-06-25025 June 1998 Rev 0 to NE-1163, North Anna Unit 2 Cycle 13 Startup Physics Tests Rept ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20236H5541998-06-0404 June 1998 Rev 5 to Procedure VPAP-0810, Crane & Hoist Program ML20236H5391998-06-0404 June 1998 Rev 1 to Procedure VPAP-0809, NUREG-0612 Heavy Load Program ML20206N8581998-04-30030 April 1998 Rev 5,Vol 1 to ISI Program for Second Insp Interval & Components & Component Supports,For 901214-010430 ML20236H5701998-04-0202 April 1998 Rev 8 to Procedure VPAP-1901, Industrial Safety & Health ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML20236H5631998-02-10010 February 1998 Rev 11 to Procedure VPAP-0105, Fitness for Duty Program ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20210Q2051997-12-31031 December 1997 1997 Severe Accident Management Tabletop (Scenario 1) Drill Manual ML20203G5191997-12-29029 December 1997 Ultrasonic Exam Technique for Detection of Microbilogically Induced Corrosion in North Anna Stainless Steel Service Water Piping ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20198G5401997-08-31031 August 1997 Rev 0 to NE-1133, North Anna Unit 1,Cycle 13 Startup Physics Tests Rept, Aug 1997 ML20199G5681997-06-30030 June 1997 Rev 5 to VPAP-2001, Station Planning & Scheduling. Even Numbered Pages of Incoming Submittal Not Included ML20210Q1991997-06-10010 June 1997 Rev 0 to VPAP-2604, Severe Accident Mgt Guideline (SAMG) Program Administration ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 1999-08-04
[Table view] |
Text
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ATTACllHENT PROPOSED LICENSE CONDITIONS i
Virginia Electric and Power Company I I
I GS10270230 G81019 PDR ADOCK 05000338 P PDC
RE0 VEST FOR t'XTENSION OF NORTH ANNA UNIT 1 J1 CLINICAL SPECIFICATIONS SURVEILLANCE TEST INTERVALS RE0 VESTED CHANGE >
Currently, North Anna Unit 1 Technical Specifications require the performance of certain surveillance tests at 18, 36, and 60 month intervals to coincide with normal 18-month refueling cycles.
The proposed change is to extend these surveillance test intervals for the North Anna Unit 1 7th cycle by six months to compensate for several unanticipated outages including the steam generator tube rupture event that occurred from July 15, 198/ to October 13, 1987, and to permit optimum fuel burn-up prior to refueling. Use of the allowable extension of the -
surveillance intervals in accordance with Specification 4.0.2 of the Technical Specifications would require an extension corresponding to the three month unplanned outage. Rather than use the extension allowed by Specification 4.0.2 and request an additional extension, a six-month extension for the affected surveillance test intervals is requested for the seventh cycle to preserve the extension allowed by Specification 4.0.2 for future refueling cycles.
SPECIFIC ONE-TIME CHANGES TO Tile TECHNICAL SPECIFICATIONS One-time changes to the surveillance test intervals associated with a plant shutdown or refueling outage as specified in the North Anna Unit 1 Technical Specifications for License Number NPF-4 are requested as follows:
- 1) The 18-month surveillance test cycle requirement as specified in the following Technical Specifications sections is changed to 24 months for the seventh cycle of unit operation only:
4.1.2.2.c 4.3.2.1.2 4.3.3.9.c 4.4.3.2.1.b 4.4.9.3.1.b 4.4.10.1.1 4.5.1.d 4.5.2.e 4.6.1.3.c 4.6.2.1.c 4.6.2.2.1.c 4.6.2.3.c 4.6.3.1.2 4.7.1.2.b 4.7.4.1.c 4.7.7.1.d 4.7.8.1.d 4.7.9.1.b 4.7.10.c 4.7.10.f 4.8.1.1.1.b 4.8.1.1.2.d 4.8.1.1.3.e 4.8.2.3.2.d 4.8.2.3.2.f
- 2) The 18/36-month surveillance test cycle requirement as specified in the following Technical Specifications sections is changed to 24/42 months for the seventh cycle of unit operation only:
4.3.1.1.3 4.3.2.1.3
- 3) The 60 month surveillance test interval requirement as specified in the following Technical Specifications section is changed to 66 months for the seventh cycle of unit operation only:
4.8.1.1.3.d
- f.'
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e t
4)- Table 1.2 of Section 1.0, Definitions, which defines "R" as "At least once per 18 months." as it ' applies to. the following Technical Specifications sections and related tables, and the 18-month requirement in the note in the tables indicated below, are changed to 24 ' months .for the seventh cycle of unit operation only:
Section Table Note 4.3.1.1.1 4.3-1 (4) 4.3.2.1.1 4.3-2 (1)-
4.3.3.1~ 4.3-3 ---
4.3.3.3.1 4.3-4 ---
4.3.3.5 4.3-6 ---
4.3.3.6 4.3-7 ---
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DISCUSSION OF REQUEST FOR EXTENSION OF NORTH ANNA UNIT 1 TECHNICAL SPECIFICATIONS SURVEILLANCE TEST INTERVALS North Anna Unit I completed applicable Mode 4, 5, and 6 surveillance tests during the sixth refueling outage which ended on June 29, 1987. It was not considered reasonable to repeat these surveillance tests during the time frame Unit I was shutdown for steam generator repairs. However, this unplanned outage did serve to impact the surveillance test intervals between the 6th and 7th refueling outages. This delay, together with additional time allowed for an optimum fuel burn-up before the next refueling, has resulted in a deferral of the next refueling outage for North Anna Unit I until April, 1989.
Specification 4.0.2 is an administrative control which ensures surveillance tests are performed periodically and defines a reasonable period for the tests. The basis of Specification 4.0.2 describes the surveillance requirements as "sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal specified interval." The requested extension of the surveillance test intervals due to unplanned outages may invoive an unreviewed safety question as defined in 10CFR50.59 because the margin of safety provided by the surveillance frequency required in Specification 4.0.2 may be slightly reduced by lengthening the time between tests. In our judgement, the reliability associated with the surveillance will not be significantly degraded by this one time extension of the surveillance test interval. Surveillance tests will continue to be performed during the extension interval. Current monitoring instrumentation and ongoing Technical Specification surveillance tests ensure the affected equipment and systems remain in an operable condition.
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RASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION The proposed change does not- involve a significant hazards consideration as defined in 10 CFR 50.92 because the extension of the North Anna Unit 1 operating period in accordance with this change would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. Current monitoring instrumentation and ongoing Technical Specification surveillance tests ensure the equipment l
and systems involved in the extended surveillance interval will remain in an operable condition until their inspection at the next refueling l outage.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated. Extending the interval for the l performance of specific surveillance tests does not create the possibility of a new or different kind of accident.
Periodic surveillance tests have been performed since the sixth outage to monitor system and component performance and to detect degradation.
Surveillance tests will continue to be performed during the extension interval.
- 3) Involve a significant reduction in the margin of safety. Extending the l interval for these specific surveillance tests for the 7th cycle of
! North Anna Unit I does not significantly degrade the margin of safety.
l Surveillance tests will continue to be performed during the extension interval. Current monitoring instrumentation and ongoing Technical i
i Specification surveillance tests ensure the affected equipment and systems remain in an operable condition.
i Therefore, it has been concluded that the proposed change does not involve a significant hazards consideration, l
i
, I l
- =,.
- 6. A procedure for identifying the authority responsible for the interpretation of,the data and the sequence and timing of administrative events required to initiate corrective action.
- s. The performance of certain surveillance tests at 18, 36, and 60 month intervals to coincide with the normal 18-month refueling cycles'shall be extended by six months for North Anna Unit I seventh cycle on).y as described in
~
the licensee's letter dated October 19, 1988.
l (4) The licensee is authorized to receive from the Surry Nuclear Power Station Units No. I and 2, possess, and store irradiated Surry fuel assemblies containing special nuclear material, enriched to not more than 4.1% by weight U-235 subject to the following conditions:
- a. Surry fuel assemblies may not be' placed in North Anna Power Station Units Nos. I and 2 reactors. -
- b. Irradiated fuel shipped to North Anna shall have been removed from the Surry reactors no less than 730 days prior to shipment.
- c. No more than 500 Surry irradiated fuel assemblies shall be received for storage at the North Anna Units Nos.1 and 2 spent fuel pool.
E. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard I training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54 (p). The plans, which contain Safeguards Information protected under 10 CFR 73.21 are entitled: "North Anna Power Station Security Plan," with revisions submitted through February 24, 1988; "North Anna Power Station Guard Training and Qualification Plan," with revisions submitted through May 14, 1987; and "North Anna Power Station Safeguard Contingency Plan," with j revisions submitted through January 9, 1987. Changes made in i accordance with 10 CFR 73.55 shall be implemented in accordance with !
the schedule set forth therein. 1 I
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