ML20095L176: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 6
| page count = 6
| project = TAC:55625
| stage = Other
}}
}}



Latest revision as of 15:11, 24 September 2022

Requests Relief from Inservice Insp Program for ASME Code Class 1,2 & 3 Components by 850301,to Allow for Performance of Insp Activities During Sixth Refueling Outage Scheduled to Begin 850405.Fee Paid
ML20095L176
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 08/06/1984
From: Mcdonald R
ALABAMA POWER CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
TAC-55625, NUDOCS 8408300169
Download: ML20095L176 (6)


Text

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Mailing Address ~.

Alabama P;wer Comp;ny 600 North 18th Street i**' E ~ Post Office Box 2641.

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'. Birmingham, Alab.=ma 35291

.- Telephone 205 783-60SO R. P. Mcdonald

. Senior Vice President

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AlabamaPower Docket No. 50-348 """'*'"""'"'

August 16, 1984 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 1 Inservice Inspection Progren for ASME Code Class 1, 2 and 3 Components Gentlemen:

Alabama Power Company's Inservice Inspection (ISI) Program has been previcusly submitted to the NRC along with requests for relief where certain ASME Code requirements were found to be impractical.

The NRC reviewed the ISI Program and granted relief as discussed in letters dated December 7,1979, August 24, 1983 and February 10, 1984.

Alabama Power Company has performed a detailed review of the ISI Program and the Safety Evaluations transmitted with the NRC letters referenced above. As a result, it has been determined that three additional relief requests are needed. One relief request was previously granted, however, Alabama Power Company has subsequently determined that a portion of the alternative examination is impractical. The two remaining relief requests were not identified at the time of the previous submittals for Unit 1.

The NRC Safety Evaluation dated December 7,1979, item I.B.6 granted relief to perfonn the volumetric examination of the charging pump casing weld whenever the pumps are disassembled for maintenance reasons. 'Upon additional review, Alabama Power Company has determined that the geometrical configuration of the casing weld is such that a meaningful volumetric examination cannot be performed. It is requested that the alternative examination originally granted be revised to permit surface and visual examinations to be performed in

~ lieu of the volumetric examination. The revised relief request e incorporating this proposed change is included as Attachment 1.

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Docket No. 50-348:

Director, . Nuclear Reactor Regulation -

August,16~,;1984 Page 2l n ,

The' ASME Code,'Section XI,1974 Edition through the Summer 1975 Addenda', requires that a surface examination be. performed on 100% of the major' load bearing components ofL th'e charging pump ' integrally

- welded supports. '_Upon additional- review,1 Alabama: Power Company has determined that the geometrical: configuration 'of the charging pump supports is such that' a 100%' surface examination is impossible to perform, . At least 80% -of;each support is-accessible for surface examination, which-will be performed in accordance with the ASME

' Code.- L A summary of the relief request is included as Attachment 2.

This- same ~ relief request was granted for Unit 2 by Item II.B.7 of the.

NRC Safety Evaluation dated -September 22, 1983.

.The ASME. Code, Section.XI, 1974 Edition through the Summer 1975

~ Addenda, requires Class 2 components tc be hydrostatically tested for four hours at.1.25 PD . Item II.B.7 of the NRC Safety' Evaluation dated February 10, 1984 granted relief from the hydrostatic test requirements for Class 2 components based on the 1980 Edition through the Winter 1980 Addenda of the ASME. Code,Section XI. This relief permits the reduction of' hydrostatic test pressure from 1.25 PD to 1.25 Psv where Pp is the design pressure and Psv is the lowest safety valve setting for the system. In addition it is noted that for the secondary side of the steam generator, Westinghouse recommends holding the hydrostatic test pressure at 1.25 PD (1356 psi) for a maximum of.30 minutes, and then reducing the pressure to 1.0 PD (1085 psi) for the remainder of the ' required four-hour hold time. .The safety valve setting (1075 psi) for the secondary side of the steam generator is only 10 psi lower than the design pressure (1085 psi).

The hydrostatic test -pressure at 1.25 Psv (1343 psi) is :only' slightly less than 1.25 P D :(1356 psi). Therefore, additional relief is -

requested to perfonn the hydrostatic test at 1.25 Psv for up to 30' minutes and reduce the pressure'to 1.0 PD for the. remainder of the four-hour hold time based on the previously granted relief for Class 2 components and on the current Westinghouse recommendations.

Westinghouse has developed this. recommended hydrostatic testing procedure to prevent undue. stress 'on the steam generator. A summary of the relief request is . included in Attachment 3.

Pursuant to the requirements of 10CFR50.55 a(g)(6)(1), Alabama Power Company hereby requests that relief be granted from certain .

r'equirements of'the ASME Code,Section XI,-1974 Edition through the Summer 1975 Addenda.- It-is respectfully. requested that these relief 1

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~ Docket No. 50-348 Director... Nuclear. Reactor Regulation August;16,1984; 4 .Page 3 m- -

r.equests be granted by March 1,1985.- The ISI: activities required to be performed:during.the Unit.1 sixth refueling outage, tentatively scheduled to-begin April' 5,1985, may include some of these impractical: inspections.

This reliefirequest is designated asia ' required approval 'in accordance with 10CFR170.21 requirements. Enclosed is the application fee of $150.

'If you have any. questions or need additional information, please advise.

Yours very ,

s' /

R. P. Mcdonald

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, ATTACISENT 1

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RELIEF' REQUEST - RELIEF IS REQUESTED FROM THE- VOLUMETRIC EXAMINATION O

. CHARGING PUMP CASING WELDS. -(ITEM C3.1, CATEGORY C-F OR C-G)

EXAMINATION REQUIREMENT:

Table IWC-2600 Item C3.1 requires volumetric examination of pump casing pressure retaining welds.

BASIS FOR RELIEF:

The pressure' retaining weld's' in the charging pump casings are not normally-

- accessible for examination as required by IWC-2600. Examination of the charging pump casing weld, Item C3.1,- by ultrasonic, radiographic or surface examination requires complete disassembly of the pump casing and removal of the inboard seal housing and rotor assembly. It has been recently determined that, due to geometrical limitations of the casing weld (i.e., weld crown), volumetric examinations cannot be perfcrmed.

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ALTERNATIVE EXAMINATION:

Surface and visual examinations of each pump casing weld will be conducted, once per inspection interval, when a pump is disassembled for maintenance reasons. If no such occasion arises, the_ examinations will be performed at or near the end of the ten year interval, e -

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, ATTACitENT 2

- RELIEF RE(iUEST - RELIEF IS REQUESTED FROM PERFORMING 100% SURFACE EXAMINATION ON THE INTEGRALLY WELDED. SUPPORTS OF THE CHARGING PUMPS.

(ITEM C3.3 CATEGORY C-E-1)

EXAMINATION REQUIREMENT:

Table IWC-2520, Category C-E-1 and IWC-2600, Item C3.3 require surface examination of 100 percent of the major load bearing elements of the integrally welded supports.

BASIS FOR RELIEF:

Due to component and support designs, approximately 20 percent of each integrally welded support is inaccessible for examination.

ALTERNATIVE EXAMINATION:

The accessible portion of each support will receive visual and surface examinations.

c; ., . ; p e-L ATTAC K NT 3

RELIEF REQUEST - RELIEF IS' REQUESTED FROM THE HYDR 0 STATIC TEST OF THE CLASS 2 PORTIONS OF THE STEAM GENERATORS AND RELATED PIPING AT 1.25 Po EXAMINATION REQUIREMENTS:

.IWC-5220:of the ASME Code,Section XI,1974 Edition through Summer 1975 Addenda requires that the hydrostatic test pressure be at least 1.25 PD

- for Class 2 components.

BASIS FOR RELIEF:

In order to prevent undue stress on the steam generators, Westinghouse recommends that the hydrostatic test of the secondary side of the steam generators be conducted at 1.25 PD for a minimum of 10 minutes and maximum of 30 minutes, and then reduced to operating pressure,1.0 PD for the ' balance of the four-hour holding period. The related Class 2 piping is hydrostatically tested along with the steam generator.

ALTERNATIVE EXAMINATION:

The hydrostatic test of the Class 2 portions of the steam generator and related piping will be hydrostatically tested at 1.25 Psv (based on previously granted relief for 1.25 Psv vice 1.25 P D) for a minimum of 10 minutes and a maximum of 30 minutes. The test pressure will then be reduced to l.0 PD for the remainder of the required four-hour holding time.

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