ML20041D879

Application for Amend to License NPF-7,providing Tech Spec 3.4.1.2b Exemption to Allow Reactor Pump to Be de-energized for Boron Mixing & Cooldown Test Under Natural Circulation Conditions Using Decay Heat.Details Encl

ML20041D879
Person / Time
Site:	North Anna
Issue date:	03/02/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
132, NUDOCS 8203090402
Download: ML20041D879 (6)

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m. . . e. . . , _ . s ye g Mr. Harold R. Denton, Director Serial No. 132 Office of Nuclear Reactor Regulation N0/JHL:acm ,

Attn: Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

PROPOSED AMENDMENT TO OPERATING LICENSE NPF-7 NORTH ANNA POWER STATION UNIT NO. 2 Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an amendment to Operating License No. NPF-7 for North Anna Power Station Unit No.

2.

The proposed change is to exempt North Anna Unit No. 2 from Technical Specification 3.4.1.2b while performing Operating License Conditions 2.C(15)(f) and 2.C (20) (b) . Operating License Conditions 2.C(15) (f) and 2.C(20)(b) require North Anna Unit No. 2 to perform a boron mixing and cooldown test under natural circulation conditions usinF decay heat. While performing Operating License Conditions 2.C(15)(f) and 2.C(20)(b) the reactor coolant pumps must be deenergized for a period of time greater than Technical Specification 3.4.1.2b allows (one hour). Therefore, to perform Operating License Conditions 2.C(15)(f) and 2.C(20)(b), North Anna Unit No. 2 will need a one time exemption from Technical Specification 3.4.1.2b for the duration of these tests. The proposed Operating License changes for North Anna Unit No. 2 are provided in Attachment 1. The discussion of the changes are provided in Attachment 2.

This request has been reviewed and approved by the North Anna Station Nuclear-Safety and Operating Committee and by the Safety Evaluation and Control staff.

It has been determined that this request does not pose an unreviewed safety question.

This action is a revision to a previous request, (Letter dated February 17, 1982, SN: 074) therefore; no further fee is needed regarding this issue.

Very truly yours, =

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Y R. H. Leasburg I{

8203090402 820302 PDR ADOCK 05000339 P PDR

e Vinoiwia Etscruic axo Powra coxpaxy to liarold R. Denton Attachments:

1. Proposed Operating License Changes

2. Discussion of Proposed Operating License Changes cc: Mr. James P. O'Reilly, Regional Administrator Office of Inspection and Enforcement Region II i

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C0fHONWEALTH OF VIRGINIA CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid.

Acknowledged before me this 4 day of M ,19 84 .

My Comission expires: 2 - >4 ,19P# .

bd. WA Notary Public e

(SEAL)

a COP 940NWEALTH'0F VIRGINIA CITY OF. RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid.

Acknowledged before me this =? day of M ,19 2 A .

My Comission expires: 4-A' . 19 2f . ,

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Notary Public M 'A (SEAL)

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ATTACHMENT 1 Proposed Changes to License Conditions 2.C.15f and 2.C.20.b Replace paragraph 2.C(15)(f) of North Anna Unit No. 2 Operating License with the following:

(f) VEPCO shall submit for Commission approval, the results of the tests applicable to North Anna Power Station, Unit 2, of a study concerning mixing of added borated water and cooldown under natural circulation conditions. VEPCO is allowed an exemption from Technical Specification 3.4.1.2b for the duration of these tests; Replace paragraph 2.C(20)(b) of North Anna Unit No. 2 Operating License with the following:

(b) Training During Low-Power Testing (Section 22.2 Item I.G.1)

No later than one year from the date of issuance of this license, VEPCO shall complete the evaluation of the results of the low power test program for incorporation into the Surry Power Station simulator. Also within one year, Vepco shall provide a report to the NRC describing changes made to the simulator model as a result of the tests.

VEPCO shall perform a boron mixing and cooldown test using decay heat within 31 days after burnup sufficient to produce at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of decay heat equivalent to one percent of rated thermal power. VEPCO is allowed an exemption from Technical Specification 3.4.1.2b for the duration of these tests.

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ATTACHMENT 2 Discussion of Proposed Operating License Changes Background and History North Anna Unit 2 Facility Operating License Conditions 2.C(15)(f) and 2.C(20)(b) require tests be done to evaluate boron mixing and cooldown under natural circulation conditions. These tests are to be completed at the end of Cycle 1 when sufficient decay heat will be available to produce natural circulation for the duration of the tests. The Salem Nuclear Generating Station Unit 2 successfully completed these tests in approximately 9 hrs.

Technical Specifict. tion 3.4.1.2b allows all reactor coolant pumps to be deenergized for not more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> while in mode 3. These tests will require the reactor coolant pumps to be deenergized for mo e than I hour.

Justification Prior to starting these tests the unit will be in Mode 3 with at least a 1.77%

shutdown margin. Boron concentration stability will be established, then the reactor coolant pumps will be deenergized and stable natural circulation confirmed. Heavily borated water will be added to the RCS to borate it to cold shutdown concentration. The RCS will be sampled frequently to verify boron mixing. When cold shutdown concentration is confirmed a cooldown will be initiated.

Safety Evaluation The probability of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the FSAR is not increased because; a) no safety related equipment will be required to operate outside of its normal operating parameters, b) the reactor coolant pumps will be available at all times to return the RCS to a forced circulation condition and, c) the reactor will be shutdown in Mode 3.

The possibility of a different type of accident or malfunction than was previously evaluated in the FSAR has not been created because the ability to remove heat under natural circulation conditions has been demonstrated and, all safety related equipment will be operable.

The margin of safety as described in the BASIS section of any part of the Technical Specifications is not reduced because the ability to remove heat under natural circulation conditions has been demonstrated.

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