ML20041A807

Application for Amend to License NPF-7,revising License Condition 2.C.20(b),by Deleting Requirement to Perform Mixing & Cooldown Test Using Decay Heat.Amend Fee Encl

ML20041A807
Person / Time
Site:	North Anna
Issue date:	02/17/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
074, 74, NUDOCS 8202220540
Download: ML20041A807 (3)

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P.Ecenc VIRGINIA ELECTRIC AND Powen COMPANY

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Mr. Harold R. Denton, Director Serial No. 074 Office of Nuclear Reactor Regulation N0/GSS:acm Attn:

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

PROPOSED AMENDMENT TO OPER\\ TING LICENSE NPF-7 NORTH ANNA POWER STATION UNIT 2 i

Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an amendment to Operating License NPF-7 for North Anna Power Station Unit No. 2.

The proposed change is enclosed.

1 The ' proposed change is to revise License Condition 2.C.20(b) by deleting the requirement to perform a boron mixing and cooldown test using decay heat.

The Operating License Condition 2.C.20.b, to perfore a natural circulation boron mixing and cooldown test using decay heat, is not necessary.

The criteria in SER Supplement-10,Section I.G for North Anna Unit 2 at the time of low power testing have been satisfied for natural circulation testing.

Performance of the natural circulation boron mixing and cooldown test using 4

decay heat would not provide additional operator training.

Additionally, Vepco has incorporated the natural circulation tests into the Surry Power Station Simulator Program; therefore, training in the performance of the natural circulation test using decay heat can be obtained at the Surry Power i

Station Simulator.

The ability to mix added borated water and cooldown under natural circulation conditions has been demonstrated at the Salem Nuclear Power Station using decay heat and at the Sequoyah Power Station using a critical reactor.

The Salem, Sequoyah and North Anna nuclear plants are similar in design, therefore, the test has been performed on a representative plant.

Since operator training is available at the Surry Power Station Simulator, and the boron mixing and cooldown tests have been performed at representative nuclear plants, it is justifiable to delete this test from the North Anna Unit 2 Operating License.

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Vinoixs4 Etzcturc AND Powen COMPANY To This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.

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

We have evaluated this request in accordance with the criteria in 10CFR170.22.

It has been determined that this request requires a Class III amendment fee.

Accordingly, a voucher check in the amount of $4,000 is enclosed in payment of the required fee.

ulg/] yeJirs, Very t I

p R.If.Leasburg Attachments:

1.

Prcposed Modification to License Condition 2.C.20(b) 2.

Voucher Checl-Na. 4717 for $4,000.00 cc:

Mr. James P. O'Reilly, Regional Administrator Office of Inspection and Enforcement Region II

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evaluation of individual reactor vessel nozzle clad cracks should they grow larger than the acceptance standards contained in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.

(19) No later than five years from the date of issuance of this license, VEPCO shall perform radiation-thermal testing of the encapsulated saddle material used for shielding, and within six months thereafter, VEPCO sahll evaluate the testing and provide the Commission with results of the evaluation.

(20) TMI Action Plan Conditions Each of the following conditions references the appropriate section of Supplement No. 11 to the Safety Evaluation Report (NUREG-0053) for the North Anna Power Station, Unit 2, dated August 1980.

(a)

Control Room Design Review (Section 22.2 Item I.D.1)

Within the schedule requirements of NUREG-0737, VEPCO shall submit an evaluation of the benefits of installing data recording and logging equipment in the control room to correct deficiencies associated with the trending of important parameters on strip chart recorders in use at most nuclear power plants, as part of their one-year control room design review.

(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.

(c)

Auxiliary Feedwater System Reliability Evaluation (Section 22.2 Item II.E.1.1)

With respect to the AFW Endurance Test, VEPCO shall test the steam turbine diven pump af ter unit startup when steam will be available in accordance with VEPC0 letter, dated July 11, 1980.

(d)

Upgrade Emergency Preparedness (Section 22.2 Item III.A.1.1)

VEPCO shall maintain in effect an emergency plan that meets:

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