ML20091K646

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Application for Amend to License NPF-4,allowing one-time Extension of Specific Surveillance Requirements for Ninth Cycle to Permit Surveillance Testing to Coincide W/Steam Generator Replacement Program
ML20091K646
Person / Time
Site: North Anna Dominion icon.png
Issue date: 01/20/1992
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-001, 92-1, NUDOCS 9201270008
Download: ML20091K646 (17)
v • d • e


Text

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. Vauoin:A Eu:CTH IC A N D I'OW E H C mil'A N Y ItirsiMowu,Vainitxir utsuus January 20,1992 U. S. Nuclear Regulatory Commission Serial No. 92 001 Attn.: Document Control Desk NL&P/TAH: R0 Washington, D.C. 20555 Docket Nos.: 50 338 Licanse Nos.: NPF 4 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH _ ANNA POWER STATION UNIT 1 ONE TIME EXTENSION TO CERIAIN SURVEILLANCE REQUIREMENTS Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests an amendment,in the form of a license condition, to Operating License NPF-4 for North Anna Power Station Unit 1. The proposed license condition allows a one time extension of spe.:lfic surveillance requirements for the ninth cycle of North Anna Unit 1 ,

to allow surveillance testing to coincide with the Steam Generator Replacement Project, currently scheduled to begin in January 1993. As the p'oposed amendment request does not permit further addition of Technical Specification 4.0.2 surveillance extensions, the maximum surveillance intervalincreate will only be 1.5 months.

The list of specific curveillance tests and the discussion of the change is included in Attachment 1. The proposed license condition is in Attachmont 2 and the Significant Hazards Determinetion Evaluation is in Attachment 3.

The Station Nuclear Safety and Operating Committee and the Management Safety Review Committee have reviewed the proposed change and determined that the request may involve an unreviewed safety question as defined in 10 CFR 50.59. The margin of safety assureo by the required refueling surveillances may be slightly reduced by extending the surveillance intervals. However, we have concluded that extending the refueling outage surveillance intervals does not significantly teduce the reliability established by the normal operating surveillance requirements (e.g., daily, weekly, monthly surveillances). We evaluated the proposed change and determined that it does not involve a algnificant hazarda consideration as defined in 10 CFR 5032.

If you have any questions, please contact us.

Very truly yours, n ,

ll{' q Mb $p,j W. L. Stewart t Senior Vice President Nuclear i '

Attachments r

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Docket Nos.: 50 338 i Serial No. 92 001

. . Pago 2 of 2 pc: U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W.

Suite 2000 Atlanta, Georgia 30323 Mr. M. S. Lessor NRC Seritor Resident inspector North Anna Power Station Commissioner Departnient of Health Room 400 109 Governor Street Richmond, Virginia 23219

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NORTH ANNA POWER STATION - UNIT 1 LICENSE AMENDMENT REQUISI  ;

EXTENSION OF 18 MONTH SURV_EILLANCE INTERVALS Attachment 1 - Discussion of Proposed Changes-Attachment 2 . Proposed Changes - Unit 1 Final Copy Attachment 3 Significarit Hazards Considerations Determination (10 CFR 50.92 Evaluation)

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ATTACHMENT 1 i

LICENSE AMENDMENT REQUEST EXTENSION OF 18 MONTH SURVEILLANCE INTERVALS DISCUSSION i

NORTH ANNA POWER STATION - UNIT 1 Virginia Electric and Power Company.

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1 Docket No.: 50 330

. Serial No. 92 001 Attach.1 Page 2 of 7 DIScitSS10 LQf_ PROPOSED- CHANGES

[ptroductio n Currently, North Anna Technical Specifications require performing certain surveillance tests at 18 month intervals to coincide with the normal 18 month refueling cycles. The proposed change will extend the specified 18 month interval surveillance requirements for the ninth cycle of North Anna Unit 1 to allow the surveillance testing to coincide with the Steam Generator Replacement Project (SGRP) outage. The SGRP is currently scheduled to begin in vanuary 1993.

Backaround The ninth fuel cycle for North Anna Unit 1 was originally scheduled to have ended in September 1992 and the surven!ance testing required by Technical Specifications would have been performed then. Subsequently, we elected to shorten the current operating cycle to 13 months witn the outage roscheduled for April 1992. However, because Unit 1 entered an unplanned outage on December 23, 1991 for steam generator tube inspections, the refueling outage for the ninth cycle has now been rescheduled to begin in January 1993, This schedule change considers the expected duration of the current outage and will permit optimum fuel burnup before the next refueling outage but will result in certain Technical Specification surveillance intervals (plus Technical Specification 4.0.2 allowable extensions) expiring prior to the beginning of the 1993 outage.

This License Amendment will add a License Condition to permit t>xtending the specified 18 month Technical Specification surveillance intervals for the North Anna Unit 1 ninth fuel cycle. The proposed surveillance intervals will not exceed 24 months including any extension allowed under Technical Specification 4.0.2.

In addition, two License Conditions, 2.D.(3)s and 2.D.(3)t are deleted by this amendment. These License Conditions allowed extensions of the surveillance intervals for North Anna Unit 1 Cycles 7 and 8, respectively.

These fuel cycles have been completed and the license conditions are no longer valid. Deleting these invalid License Conditions is only administrative in nature.-

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Dockst No.:- 50 338 ,

. SorL-l No. 92 001  !

- Attach,1 Page 3 of 7

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Affected - Technical Snecification Survalliances  ;

Technical Specification - 4.1.3.2.1.b Rod Position Indicator Instrumentation  !

Technical Specification - 4.3.1.1.1 r items 1, 3, 4, 5, 6, 7, 8, 9,_10, 11, 12, 13, 14, 15, 16, 17 l Reactor Trip System Instrumentation (Instrument Channel  !

Operability - Channel Calibration and Functional Test) f Technical Specification - 4.3.1.1.2 ]

Items 1, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17 Reactor ' Trip System Instrumentation - Interlocks (Demonstrate l total interlock-function during channel calibration for each channel  ;

affected: by Interlock function.)-

Technical Specification - 4.3.1.1.3 .

-items 1, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17 Reactor Trip' System Instrumentation Response Times Technical Specification -- 4.3.2.1.1 .

- ltem s 1.c, 1.d, 1.e, 1.f, 2.c, 3.b.3, 4.c, 4.d, 5.a, 6.c and 6.d l Engineering Safety' Feature Actuation- System Instrumentation i (Instrument Channel Operability Channel Calibration and Functional

. Test) '

l Technical Specification - 4.3.2.1.2  !

Items -1.c, 1.d, 1.e, 1.f, 2.c, 3.b.3, 4.c, 4.d, 5.a 6.c and 6.d i Engineering Safety Feature Actuation System Instrumentation - '

Interlocks- (Demonstrate . total interlock function during channel calibration for each channel affected by interlock function.)

Technical Specification -- 4.3.2.1.3 i items 1.c, 1.d, 1.e, 1.f. 2.c, . 3.b.3, 4.c, 4.d, 5.a, 6.c and 6.d -

Engineering Safety Feature Actuation System ' Instrumentation -

Response Times l

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Docket No.: 50 338-  !

. Sotl No. 92 001

"' I 4 Att:ch.1 Page 4 of 7 j Teahnical Specifi. . lon - 4.3.3.1 l Items: 1.b.1, 1.b.il, 2. coll, 2.c.ill and 2.c.lv (

Radiation Monitoring Instrumentation - Channel Calibration -

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-Technical Specification - 4.3.3.3.1 '

- ltems' 1.a, 1.b, 2.a, 2.b, 2.c, 3.a, 4.a. 4.b, 4.c and 4.d Seismic Instrumentation Channel Calibration Technical ' Specification -

4.3.3.5 l items 1, 2,- 3, 4, 5, 6, 7 and 8 Auxiliary- Shutdown Pan'el Monitoring instrumentation - Channel -i Calibration  :

Technical'_ Specification - 4.3.3.6 f!

itema : 1, 2, 3, 4, 5, 6, 7, - 11,12,14, 15, 16 17 and 18 Accident Monitoring Instrumentation . Channel Calibration Technical Specification - 4.3.3.9.C l Loose Parts: Monitoring Instrumentation Channel Calibration  ;

Technical Specification - 4.4.3'.2.1.b l Reactor Coolant System - Relief Valves (PORV Instrument Channel l Calibration)

- TechnicalL Specification -- 4.4.9.3.1.b l 4-Reactor Coolant System Overpressure Protection Systems - Channel

-Calibration .

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I Technical Specification - 4.5.2' Litems . d.1, and g.2 -

' Emergency Core Cooling System - ECCS Subsystems - Tavg 2350'F ,

(Visual inspection of Contain_ ment Sump scieens for: loose debris L

and verification: of -manual valve positions) l  !

L - Technical.- Specificationi - -4.5.3.1 Emergency Core Cooling System - ECCS Subsystems - Tavg <350'F l- (Demonstrate' operab.ility per SR 4.5.2) '

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Dock:t No.: 60 338 F. Serbl No. 92 001

- Attach.1 Page 5 of 7 .

Technical Specification - 4.6.3 1.2.d l Containment isolation Valves Cycling of Weight or Spring Loaded j Check Valves i Technical Specification 4.7.1.1 Plent System Safety Valves (No additional Surveillance -;

Requirements other than those required by Specification 4.0.5)

Technical Specification - 4.7.9.1.a  ;

-Residual Heat Removal System - Auto Closure Interlock Test l

Technical Specification - 4.7.10 ,

item c Snubbers Large Bore Functional-Testing  ;

' Technical ' Specification -- 4.8.1.1.2.d.1 AC Sources Inspect EDGs.

' AC Sources - EDG Battery Dkcharge Test -

Technical . Specification - 4.8.2.3.2.c ,

items 1, 2,- 3, and 4 ,

DC Distribution - Battery' Cell Conditions and Charger Capacity  !

Technical Specification - 4.8.2.3.2.d  ;

DC! Distribution - Battery' Service Testing

, . Technical -Specifbation - 6.8.4,a ;(ll) _

~ Primary Coolant Sources.Outside. Containment (Integrated Leak Test Requirements)  ;

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l Docket No.: 50 338 Serial No.93-001 Attach.1 Page 6 of 7 Summary The deletion of License Conditions 2.D.(3)s and 2.D.(3)t is administrative in nature only as the terms of both License Conditions have expired and both have been satisfied.

Technical Spec"Ication 4.0.2 is an administrative control which ensures that surveillanca tests are performed periodical ly and defines a reasonable extension period for such testing. The basis of this specification describes the surveillance requirernents as "sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly derraded beyond that obtained from the nominal specified interval." The requested extension of the surveillance .

3 test intervals, due to the unplanned outage and the rescheduling of the  %

ninth cycle refueling outage, may involve an unreviewed safety question as defined in 10 CFR 50.59 because the margin of safety piovided by the surveillance frequencies required by Specification 4.0.2. may be slightly reduced by extending the intervals. Hower r, because the rr.axima allowable extension would only be 1.5 months, we have concluded that T reliability defined by the normal surveillance intervals will nr. bu significantly reduced by this extension. We base this conclusion 0; h following points:

. Current monitoring of instrumentation and ongoing TS surveillance tests provide assurance that the equipment involved in the extended survoillance tests will remain in an operable condition _

until their inspecticn at the next refueling outage.

V - Periodic surveillEnce tests have been performed since the last refueling outage to monitor system and component performance and to detect any significant degradation. Surveillance testing will continue to be performed during the requested extcnsion interval which provides added assurance that the reliabliity of '

equipment associated with the extended surveillance will not be significantly degraded by this one-time extension.

. Historically, the electronic components in the Reactor Protection ,

System and Engineered Safety Features Actuation System have shown a very high degree of reliability. Typically, any failures associated with instrements in these systeme have been catastrophic and not found during calibrations.

Docket No.: 50 338 Serial No. 93 001 Attach.1 Page 7 of 7

. All EO transmitters that have an 18 month calibration requirement to maintain. EQ qualifications have been or will be calibrated during this outage.

SI Blackout testing of both emergency buses, SI Functional, CDA Functional, as well as various other safety system testing has been performed during this Steam Generator Inspection Outage.

We have also concluded that although there could be a slight reduction in the margin of safety provided by Specification 4.0.2, for the reasons explained above, th!s reduction is not significant and does not create a Significant Hazard as defined in 10 CFR 50.92.

ASME Section XI Section XI of the ASME Code defines a refueling interval as 18, but no more than 24 months. Based upon this cefinition, all ISI testing, required to be done at refueling intervals, does not have to be performed until the unit is shutdown for steam generator replacement.

NOTE: Facility Operating License Pages 4 and 5, have been reformatted and reprinted to create space for the propor.ed License Condition without requiring an additional page, "6a"  : hey are included for continuity.

t ATTACHMENT 2 LICENSE AMENDMENT REQUEST EXTENSION OF 18 MONTH SURVEILLANCE INTERVALS p

i FINAL COPY L

lI-NORTH ANNA POWER STATION - UNIT 1 L

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l Virginia Electric and Power Company l

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4-(1) Mayimum Power Level VEPCO is authorized to operate the North-Anna Power Station, Unit No.1, at reactor core power levels not in excess of 2893 megawatts (thermal).

(2) Technical Soecifications 1

The Technical Specifications contained in Appendices A and B, as -l revised through Amendment- No. are hereby incorporated in l i

the license. The licensee shall operate the facility in accordance j with the Technical Specifications.  ;

, -(3) _ Additional Conditions The rnatters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of this amendment or within the operational

- restrlctions indicated. The removal of these conditions shall be

- made _by an amendment to the license supported by a favorable evaluation by the Commission:

c. -Virginia Electric and Power Company shall not operate the reactor in operational modes 1 and 2 with less than three reactor coolant pumps in operation.

' d. VEPCO may use two (2) fuel assemblies containing fuel rods clad with an advanced zirconium base alloy cladding material as described in the licensec's submittals dated February 20, 1987 and September 30,.1988.

e. If Virginia Electric and Power Company plans to remove or to - ^

make significant changes in the normal operation'of equipment that controls the amount of radioactivity in effluents from the North Anna Station, the Commission shall be notified in writing regardless-of-whether the change affects the amount of

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radioactivity in the effluents.

J.1 The Virginia Electric and Power Company shall modify or replace the presently installed Barton Models No. 763 and E .No. 764 Lot 1 Transmitters used in safety related circuits inside E containment with transmitters that have been demonstrated to provide a greater tolerance to harsh environments. 3

-The modifications- or replacement of these transmitters shall be completed as soon as practicable but not later than June 30,1982.  ;

Amendment No.452, l l y 4 l-

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o. The provisions of Specification 4.0.4 are not applicable to the performance of surveillance activities associated with diesel generator battery Technical Specification 4.8.1.1.3.d until the completion of the initial surveillance interval associated with that specification,
r. The Virginia Electric and Power Company shall perform a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
1. Identification of a rampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points;
3. Identification of process sampling po!nts;
4. Procedures for the recording and management of data;
5. Procedures defining corrective actions for cff control point chemistry conditions; and
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. Deleted by Amendment l t Deleted by Amendment l
u. Fire Protection VEPCO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final

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Safety Analysis Report foi the facility and as approved in the SER dated February 1979 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 31,

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v. The performance interval for surveillance tests specifically identified in the licensee's letter dated January 20, 1992, normally 18 months to coincide with the normal 18 month refueling cycle, shall be extended to coincide with the Steam Generator Replacement Project and Cycle 9 Refueling Outage ,

for North Anna Unit 1. The extended interval shall not exceed a l total of 24 months, j (4) The licensee is authorized to receive from the Surry Nuclear Power Station Units No.- 1 and 2, possess, and store irradiated Surry fuel l 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 No.1 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 No.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 training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of tne 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 24,1998; " North Anna Power Station Guard Training and Qualificatica Plan," with revisions submitted through May 14, 1987; and " North Anna-Power Station Safeguard Contingency Plan," with revisions submitted through January 9,1987.

Changes made in accordance with 10 CFR 73.55 shall be implemented

' In accordance with the schedule set forth therein.

Amendment No.-140 l

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t 1J ATTACHMENT 3 ,

LICENSE AMENDMENT REQUEST EXTENSION OF 18 MONTH SURVEILLANCE INTERVALS l

DETERMINATION OF. NO SIGNIFICANT HAZARDS CONSIDERATIONS (10 CFR 50.92 EVALU ATION).

NORTH ANNA POWER STATION - UNIT-1 Virginia Electric and Power Company

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Docket No.: 50 338 Sortal No. 92 001 Attach. 3 Pago 2 of 3 BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION I Currently, North Anna Technical Specifications require performing certain surveillance- tests at 18 month intervals to coincide with the normal 18 month refueling cycles. The proposed change will extend the specified 18 month interval surveillance requirements for the ninth cycle of North Anna Unit 1 to allow the surveillance testing to coincide with the Steam Generator Replacement Project (SGRP) outage. The SGRP is currently scheduled to begin in January 1993.

Rankaround The ninth fuel cycle for North Anna Unit 1 was originally scheduled to have ended in September 1992 ard the surveillance testing required by Technical Specifications would have been perforrned then. Subsequently, we elected to shorten the current operating cycle to 13 months with the i outage rescheduled for April 1992. However, because Unit 1 entered an unplanned outage on December 23, 1991 for steam generator tube inspections, the refueling outage for the ninth cycle has now been rescheduled to begin in January 1993, This schedule change considers the expected duration of the current outage and will permit optimum fuel burnup before the next refueling outage but will result in certain Technical Specification surveillance intervals (plus Technical Specification 4.0.2 allowable extensions) expiring prior to the beginning of the 1993 outage.

This License Amendment will add a License Condition to permit extending the specified 18 J1onth Technical Specification surveillance intervals for the North Anna Unit 1 ninth fuel cycle. The proposed surveillance intervals will not exceed 24 months including any extension allowed under Technical Specification 4.0.2. Operation of North Anna Power Station Unit 1 in accordance with this change will not involve a significant hazards consideration as defined in 10 CFR 50.92 because it will not:

1. result in a significant increase in the probability or consequence af an accident previously evaluated. Current monitoring of plant conditions and continuation of the surveillance testing required during normal plant operation will continue to be performed as usual to assure conformance with Technical Specification OPERABILITY requirements.

Docket No.: 50 338 Sorial No. 92 001

. Attach. 3 Page 3 of 3

2. create the possibility of.a new or different kind of accident from any accident previously identified. Extending the surveillance interval for the performance of the specific tests will not create the possibility 4 of any new or different kind of accidents. Current monitoring of plant conditions - and continuation of the surveillance testing required during normal plant operation will continue to be performed as usual to assure conformance with Technical Specification OPERABILITY requirements.
3. result in a significant reduction in a margin of safety. Extending the surveillance interval for the performance of the specific tests could slightly reduce equipment reliability and margin of safety derived from required surveillances, However, current monitoring of plant conditions and continuation of the surveillance testing required during normal-plant operation will continue to be performed as usual to assure conformance with Technical Specification OPERABILITY requirements and the bases thereof, Therefore, there will not be a significant reduction in the margin of safety during the extension.

Therefore, pursuant to 10 CFR 50.92, based on the above considerations, we have determined that this change does not involve a significant hazards consideration, i

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