ML20247C762

Forwards Rev 0 to FNP-2-M-068, Updated Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per NRC 890320 Conference Call Request.Addl Component Sketches Also Encl

ML20247C762
Person / Time
Site:	Farley
Issue date:	03/23/1989
From:	Hairston W ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247C769	List: ML20247C762 ML20247C772
References
TAC-71578, NUDOCS 8903300257
Download: ML20247C762 (5)

Text

_ _ _ _ _ - _ _ _ _ _

Alabama Power Company.

600 North 18th Strert '

.j h- -

r n m, Alabama 352914400 Telephcne 205 250-1837_-

W. G. Hairston, lit Senior Vice President Nuclear Operations the southern electnc system 10CFR50.55a(g)

.j l

March 23, 1989 l

l l

Do'cket No'. 50-364 U. S. Nuclear. Regulatory Commission

' Attention: Document Control Desk l

Washington, D. C.

20555 l

Gentlemen Joseph M. Farley Nuclear Plant - Unit 2

-Updated Inservice Inspection Program for ASME Code Class 1, 2 and 3 Components (TAC No. 71578) i

)

By letter dated December 16, 1988, Alabama Power Company submitted an updated Inservice Inspection (ISI) Program for ASME Code Class 1, 2 and 3 Components for Farley. Nuclear Plant, Unit 2.

This program (including attendant relief requests) was submitted pursuant to the NRC's August 31, 1988 exemption which permitted revision of the Unit 2 ISI Program to coincide with the Code of record and update schedule currently used for Unit 1.

In accordance with this exemption, the updated program is to be implemented during the Unit 2 sixth refueling outage which commences on March 24, 1989. The NRC subsequently requested a list of only those reliefs which would be needed to support the forthcoming Unit 2 outage.

l I

This list was provided by letter dated February 8, 1989.

On March 20, 1989 a conference call was held to discuss additional information the NRC stated was necessary to complete their review of the outage specific relief requests. Enclosure 1 is a revised ISI Program which includes changes to the reliefs to provide the additional information requested by the NRC. Enclosure 2 contains additional component sketches i

referenced in relief requests RR-9, RR-10, RR-11, RR-14, RR-18, RR-19 and RR-20.

These sketches are being submitted as supplementary information and are not a part of the updated ISI Program.

In addition, several editorial i

h0 8903300257 890323 g

ADOCK0500g4 g

PDR o

l

____L________________

_ _ _ _ J

-U. S. Nuclear Regulatory Commission Page 2 changes have been made to clarify the ASME Code requirements as they apply to the performance of examinations durir.s the first and second intervals.

A summary of these technical and editorial changes is provided below 1.

Relief request RR-9 was revised to clarify that the pressurizer head-to-nozzle velds and the base metal on the heads vill be examined in accordance with Code requirements. Only 25% of the base metal on the nozzle sides can be examined due to nozzle geometry.

2.

Relief request RR-ll was revised to include a detailed cross section drawing of the steam generator primary nozzle and inner radius section which illustrates the difficulty in performing the examination as described in the Basis for Relief.

3.

Relief request RR-18 was revised to include an estimated amount of Code required examination volume for the regenerative heat exchanger velds which cannot be examined due to the adjacent nozzles and supperts. Drawing U-205224C included in Enclosure 2 depicts these limitations.

4.

Relief request RR-28 was revised to clearly describe the steam generator secondary side steam outlet nozzle forging configuration. A drawing of the forging is also provided.

5.

Relief request RR-29 was revised to include the Code required hydrostatic test pressure for the piping to be tested, the design pressure of the lover pressure piping downstream of the-interfacing check valve, and the system leakage test pressure being proposed as an alternative. Also, a discussion was added describing the impracticality of isolating the higher pressure piping from the lover eessure piping at the check valve.

6.

RR-31 was revised to describe why most of the service water pump is inaccessible for visual examination during the system pressure test.

7.

Editorial revisions were made as follows:

a.

The phrase "second 10 year" was removed from the cover page, Table of Contents and Page 1-1 since the program applies to the third period of the first interval as well as to the first and second periods of the second interval.

b.

Section 1.2 was expanded to further describe applicative of the updated Code requirements to the first interval and to state that some relief requests referenced in the tables have not been granted by the NRC.

c.

The tables in Sections 2.0, 3.0 and 4.0 were revised where appropriate to differentiate between the first and second

U. S. Nuclear Regulatory Commission Page 3 interval requirements. The " Extent and Frequency of Examination" column was modified on each affected page to show the first interval requirements on Sheet A and the second interval requirements on Sheet'B.

Section 5.0 remains unchanged since the requirements for component supports are the same for either interval.

d.

Page 4-9 and Drawing D-356343, Sheet 1 vere corrected to show proper examination requirements for the CCW surge tank.

Finally, the NRC requested Alabama Power Company to provide additional information on relief request RR-33 vhich requests exemption from hydrostatically testing the service water, component cooling water, chemical and volume control, reactor makeup and spent fuel pool cooling systems.

Also, the NRC requested that relief requests RR-35, RR-37 and RR-44 be revised to reference RR-33 since the former reliefs requested exemption from the required visual examination while at the alternative test pressure defined in the latter relief request. Additional information was also requested for relief request RR-24 which requests exemption from hydrostatically testing the RHR and SI relief valve discharge piping header and for relief request RR-38 which requests exemption from hydrostatically testing the Class 3 portions of the auxiliary steam piping to the auxiliary feed pump turbine.

It has been determined that additional time vill be required to evaluate the practicality of performing these hydrostatic tests as specified by the Code.

Performance of these examinations has been deferred beyond the sixth refueling outage, and relief requests RR-24, RR-33, RR-35, RR-37, RR-38 and RR-44 therefore vill not be needed for the upcoming outage as previously requested in the letter dated February 8, 1989.

If there are any questions or if additional information is required, please advise.

Respectfully submitted, ALABAMA POWER COMPANY (y,

. /[

W. G. Hairston, III VGH/DEM/ STB:cht-8.40 Enclosures cc:

Mr. M. L. Ernst Mr. E. A. Reeves Mr. G. F. Maxwell

.,.}.

bei Mr. Bill M.-Guthrie-Mr..R. P. Mcdonald Mr. J. D. Woodard Mr. J. W. McGowan Mr. D. N, Morey v/ enc..

Mr.-R. G. Berryhill Mr. D. B. Hartline=

v/ene.

Mr. D. E.,Mansfield Mr. Scott Fulmer Mr. F. D. Kuester-Mr. T. N.'Epps v/ene.

Mr. T.:T. Robin

.Mr. K. C. Gandhi-Mr.:J. A.'Knochel-Mr~.

G.~ Johnson v/ene.

Commitment Tracking System (2)v/ene.

FNP Document Control File: 'K-3.2.1.2

/8.39 i

I

)

Encl'osure 1 TJoseph M. Farley Nuclear Plant - Unit 2

' Updated Inservice Inspection Program-for ASME Code Class'1, 2 and 3 Components Insertion' Instructions Section Instruction.

Cover Sheet.

Replace Table of Contents Replace Section 1.0 Replace in its entirety 1 Section 2.0 Replace in its entirety Section 3.0 Replace-in its entirety.

Section 4.0 Replace in its entirety Section 5.0 Do not remove (unchanged)'

Section 6.0 Replace in its entirety Section 7.0

-Do not remove (unchanged)1 Drawings Replace.

D-356343 Sh. 1 D-356347 Sh. 1 Replace D-356347 Sh. 2 Replace All others

'Do not remove (unchanged)

_-_.