ML18149A034

Requests Relief from ASME Code Requirements for First Period,Second Interval Inservice Insp During May 1986 Refueling Outage.List of Exams Requiring Delay & Sketch of Code Allowed Tolerance Band Encl.Fee Paid

ML18149A034
Person / Time
Site:	Surry
Issue date:	02/03/1986
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation
References
86-040, 86-40, TAC-60712, NUDOCS 8602070039
Download: ML18149A034 (4)

Text

• • • . o e e VJROINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS February 3, 1986 Mr. Harold R. Denton, Director Serial No.86-040 Office of Nuclear Reactor Regulation NO/dn Attn: Mr. Lester S. Rubenstein, Director Docket No. 50-280 PWR Project Directorate #2 License No. DPR-32 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washinton, D.C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NO. 1 FIRST PERIOD, SECOND INTERVAL INSERVICE INSPECTION PROGRAM RELIEF REQUEST Surry Power Station Unit No. 1 is scheduled to complete its first period, second interval inspection requirements for ASME Section XI, 1980 edition, Winter 1980 addenda, inspection program B, during the next refueling outage (May 1986). Pursuant to 10 CFR 50.55a(g)(5), we are requesting relief from certain code requirements defined in IWB 2412(b) of our code edition, for Surry Power Station Unit No. 1. The following basis is provided.

The code currently specifies in IEB 2412(b) that an inspection period may be decreased or extended by as much as a year to enable an inspection to coincide with a plant outage. Figure 1 provides an illustration of this code allpwed toierance band. Under this requirement Surry Unit 1 should complete all period 1, interval 2 inspection requirements by December 22, 1986, which allows the next refueling outage to be included into the first period inspection. Certain examinations, specifically involving the use of the reactor vessel examination device, are required to be completed within the' first period of the second interval. These examinations are detailed on Attachment 1. Completion of these code required examinations places an impractical delay on the current (May 86) outage plan, affecting outage duration and power availability during "peak" season.

Alternatively, it is requested that these examinations (Attachment lY be delayed to the following refueling outage. Additionally, second period, second interval examinations would be performed concurrent with the delayed examinations.

• A similar request was submitted to extend the tolerance band, for Surry Unit 2 (dated 6/14/83 from Mr. W. L. Stewart to Mr. H. R. Denton). This Relief Request was approved by letter (dated 5/7/84 from Mr. S. A. Varga to Mr. W. L. Stewart). The basis for the Surry Unit 2 exemption was the Steam Generator Replacement Program. A similar replacement program was

e e VIRGINIA. ELECTRIC AND POWER Co~PANY TO Mr. Harold R. Denton completed for Surry Unit No. 1 between September 14, 1980 and July 6, 1981.

This relief request does not eliminate any examination. It only delays the requirements, extending the code tolerance band. As such, granting approval of this proposed relief would not endanger the public, nor affect the necessary inspection provided by the code.

In accordance with 10CFR170 an application fee of $150 is enclosed.

If you have any questions, or need additional information to process this request please contact us.

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W. L. Stewart Attachment/Enclosure cc: Dr. J.Nelson Grace Regional Administrator NRC Region II Mr. Roger D. Walker, Director Division of Reactor Projects NRC Region II Mr. Donald J. Burke NRC Resident Inspector Surry Power Station Mr. Terence L. Chan NRC Surry Project Manager PWR Project Directorate #2 Division of PWR Licensing-A

ATTACHMENT 1 Category Item Description Exam Method B-A Bl.30 Reactor vessel shell to flange UT weld #1. Examine 50%.

B-D B3.90 Reactor vessel nozzle-to vessel UT welds #10, 12, 14. (outlet nozzles) Examine 100%.

B-D B3.100 Reactor Vessel nozzle inside radius UT sections. (outlet nozzles)

Examine 100%.

B-F BS .10 Loop 1 outlet nozzle-to-safe-end UT/PT weld #lDM. Examine 100%.

B-F BS .10 Loop 3 outlet nozzle-to-safe-end UT/PT weld #lDM. Examine 100%.

B-F BS .10 Loop 2 outlet nozzle-to-safe-end UT/PT weld #lDM. Examine 100%.

- .. FIGJJRE 1

)

ARTICLE IWB 2000 INSPECTION PROGRAM B

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0. 16%-34% 50%-67% 100% .

.. Y-- Tolerance ~and 0 2 4 6 8 10

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lnspectiori Interval Years.

_....- - Inspection Periods