ML19095A065

Letter Amendment to the Operating License Technical Specification Change No. 24 Relates to Steam Generator Inservice Inspection

ML19095A065
Person / Time
Site:	Surry
Issue date:	12/30/1976
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Reid R, Rusche B Office of Nuclear Reactor Regulation
References
Download: ML19095A065 (6)

Text

,*

e VIRGINIA ELECTRIC AND PowER CoMPAN ll!iw RICHMOND, VIRGINIA 23261.

December 30, 1976

• Rusche, Director Nuclear Reactor Regulation Attn:

Mr. Robert W. Reid, Chief*

Operating.Reactors Branch No. 4 Division.of Operating Reactors U.S. Nuclear ~egulatory Commission Washington, D.C.

20555

Dear Mr. Rusche:

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Serial No. 240/090876 LQA/DWSj r: vhe*.

.Docket Nos.. 50-280 50..;2a1 License No. DPR-32 DPR-37 Amendment to the Operating License Technical Specification Change No. -24

• Surry

• Power

• Station :units* 1

• and 2 Pursuant to 10CFR50.90, the Virginia Electric and Power Company hereby.requests an amendment to Operating Licenses DPR-32and DPR-37 for the, Surry Power Station, Unit Nos. 1 and 2.

The amendment requested is a change to the Technical Specification and has been designated as Change No. 24 *.

Based on your request of September 8, 1976, we are revising our earlier proposed Technical Specification for Steam Generator Inservice Inspection, our resubmittal uses as guidance your model Technical Speci-fication which is based on Revision 1 of Regulatory Guide 1.83 dated July 1975.

These changes* have been reviewed by both the Station Nu.clear Safety and Operat:i.ng Committee and the System Nuclear Safety and Operating Committee.

Further it has been determined' that these changes do not involve an unreviewed safety* question as defined in 10CFR50.59.

Attachment cc:

Mr~ Norman C. Moseley Very truly you~~K*A

. /,/ c. M.

irigs

~ Vice.President-Power Supply_

• • and Production Operations

V!RGIN.IA ELECTRIC AN!) PO'!"ER COMPANY.TO Mr *. aenard : C *. ~usche SHEET NO *

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D. :A. Hillsman, Jr., Assistant cretary COMMONWEALTH OF VIRGINIA

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CITY OF RICHMOND

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Before me, Clarence Hundley, Jr., a Notary Public, in and for the City and Commonwealth aforesaid, on this,30th day of December, 1976,.personally appeared Stanley Ragone and D. :A. Hillsman, Jr., who. being duly sworn, made*oath. and said (1) that they are Executive Vice President and Assistant Secretary, respectively, of th.e Virginia Electric and Power Company, (2) that th.ey are duly authorized* *to execute and file the foregoing Amendment in behalf of that Company and (3) that the statements in the Amendment are true to the best of their knowledge and belief.

Given under my hand and notarial seal this 30th day of December, 1976.

My Commission expires June 3, 1978:. *

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. (i,4,(t,),td_~/4i4 Clar nee Hundley,/

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Applicability Applies to the periodic inspection of steam generator tubes.

Objective To verify the integrity of the boundary between the primary and secondary coolant.

Specifications

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A.

Steam generators will be inspected by means of an eddy current test or equivalent technique to determine wall thinning and mechanical damage.

B.

Instrumentation and equipment shall generally conform with the recommen-dations of Regulatory Guide 1.83 Rev. 1 "Inservice Inspection of Pressurized Water Reactors Steam Generator Tubes", Office of Stanaards Development U. S. Nuclear Regulatory Commission, Jul~ 1975.

C.

Sample selection will be determined by the following criteria:

1.

Tube selection should be random "in nature except where experience in similar plants with similar secondary water chemistry indicates critical areas to be inspected *.

2.

The number of tubes to be inspected should be at least 3% of the total number of the unplugged tubes per steam generate;.

3.

• Subsequent inspections should include tubes-that had detectable

wall. penetrations (> 20%) on previous inspections. It should also include* tubes in areas where experience has indicated potential problems.

D.

Classification and definitions

a.

The results of the inspection will be classified into one of the following categories:

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1.

C-1

2.

C-2

3.

C-3 NOTE:

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Less than 10% of the tubes have wall penetrations greater than, or equal to 20% and no tube has imperfections that exceed the plugging limit.

Less than 10% of the tubes have wall penetrations greater than, or equal to, 20% and that no more than three (3) tubes have imperfections that exceed the plugging limit.

More than 10% of the tubes have wall,penetrations greater than, or equal to, 20% or more than 1% tubes exhibit indications of exceeding the plugging limit.

All totals must _include previously inspected tubes that have exhibited (> 10%) further*wall penetrations.

b.

Imperfection means a decrease in the nomiµal wall thickness required by drawing or specification.

c.

Defect means an imperfection of such severity that the tube is un-acceptable for continued service.

d.

Plugging Limit means the imperfection depth at or beyond which the plugging of the tube must be performed.

This depth is 40% of the wall thickness based on Westinghouse's analysis of degradated tube 1

strength.

E.

Acceptance Criteria

a.

If the results of the inspection are classified as C-1, the steam generator will be deemed operable and plant operation may resume.*

b.

If the results of the inspection are classified as C-2, the steam generator will be deemed operable after corrective action is taken, i~e. plugging the defective tube(s).

F.

Supplementary Sampling Requirements

a.

If the results of the inspection are classified as C-3, the following lwestinghouse Electric Corp. VPS-75-074 7 May 75.

e TS 3.22-3 inspected, concentrating in the area of the tube sheet array where the tubes with the imperfection were found.

2. If the results of the inspection of paragraph F.a.l is classified as C-l or C-2.the measu.res applicable to paragraph E.a and E.b will be carried out.

3.

If the results of the inspection of paragraph F.a.l is classified as C-3, then an additional inspection consisting of 6% of the unplugged* tubes in the steam generator will be inspected in the area of the tube sheet array where the defective tubes were found.

G.

The inspection interval will normally be refueling shutdown but no greater than 24 months.

The first inservice inspection will consist of all three steam generators.

Subsequent inspection.may consist of a single steam generator as long as the number of tubes ins~ected in the steam gene~ator is equal to 3% of all tubes of all steam generators in the Unit.

If the results of two consecutive inspections are classified C-1, then the inspection interval may be increased to 40 months.

Unscheduled inspections should be conducted in the event of the following:

a.

Loss of coolant accident requiring actuation of the engineering safeguards

b.

Major steam line or feedwater line break.

c.

Seismic occurrence greater than an. operational basis earthquake.

H.

Reporting

a.

The complete results of the s~eam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed.

This report shall include:

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li. Continued.

1. Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged.

- TS 3.22-4

b.

A report of all inspections will be filed in station records for the life of the plant.

Basis The above specification will provide a program of inservice inspection.

The need for this program has been dictated by the discovery of isolated cases of steam generator tube degradation.

Initial analysis have indicated tube wall thinning to be in the area of i.5 x 10-3 inches over the lifetime of the facility.

This is no longer the accepted case.

Tube wall thinning has been found to be in the area of 40%

of wall ::.thickness in just the current life of the facility.

The 40% of wall thickness is now the plugging limit.

Analysis have indicated that the tubes will have to be plugged when they reach this stage of degradation.

This specification is written to satisfy the terms, conditions, and recommendations of Reg. Guide 1.83 Rev. 1 "Inservice Inspection of Pressurized Water Reactors Steam Generator Tubes" Office of Standards Development, U.* S.

Nuclear Regulatory Commission, July 1975.

• References

1.

FSAR Sect *. 4.3 *.t.2 System Design Evaluation

2.

u~ S. Nuclear Regulatory Comission Reg. Guide 1.83 Rev *. 1

3. Westinghouse.Electric Corp. Letter VPS-75-074, 7 May 75.

• .