ML17317B346
| ML17317B346 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dolan J INDIANA MICHIGAN POWER CO. |
| References | |
| NUDOCS 7907250229 | |
| Download: ML17317B346 (4) | |
Text
CEN RAL R(E8 JUL 20 t979 Noeket Io. $0-31S
~ 'I)eoket No. $D-516
@aerican Ileetric Power Servgoe Corporetion Indiana ead Hie~pan Pod~ Coapeay ATXN! Xr. John B. Dolen Vice Chaizaan Iagiaeerinl end Ccmetnaethm 2 broedwey New.York, IY 10004 Oentle)sane IE Ic)tlletin No. 79-14 ie revised to lait the ecope of <<erk rapd.red.
Yhe ahaaeee are iadioated oa tbe <<anioeed replee~t page for the bulletin.
Xf you desire edditioasd. iaforaetion reserding thie <<atter, yleeee oonteot thee offiae.
Sincerely, Aaaao 0. Keppler Direotor Raeloeeres YS baUetin Io. 84-14, page 2, lerloioa 1
ee <</encl 1 Mr. D. Vo Q)eller, Plant Manager Central Alee Otreetor, IIIJDPM
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~NRC Form 31$ 8 (R.QZ) gl-'Td) NRCM 02d0
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OVERNMENT PRINTING OFFICE: 1979-289-237 I
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IE Bulletin No. ?9-14 Revis1on 1
July 18, 1979 Page 2 of 3 Action to be taken by Licensees and Penn)t Holders:
All power reactor facility licensees and construction permit holders are requested to verify, unless ver1fied to an equivalent degree with1n the last 12 months, that the seismic analysis applies to the actual configura-tion of safety-related piping systems.
The safety related pipfn~ fncludes Seismic Category I systems as defined by Regulatory Guide 1.29,
'Seismic Design Classf ficatfon" Revision I ~ dated August 1, 1973 or as defined in the applicable FSAR.
The action items that follow a l
to all safet related i in 2
1 2-inches in ameter an reater an to sexism c Cate or
~
n re ar ess o
s ze w c
was nam ca 1
ana ze com u er.
or o er ants, where Se sm c Category I requ rements did not ex st at the time of icensfng, it must be shown that the actual configuration of /+jan safety-related systems, utilfzin 1 in 2
1 2 inches in diameter and reater meets des1gn requirements.
Specifically. each 11censee fs requested to:
1.
Identify inspection elements to be used fn verffyfng that the seismic analysis input information conforms to the actual configuration of safety-related systems.
For each safety-related
- system, submit a list of design documents, including title, identification number. revision, and date, which were sources of input information for the seismic analyses.
Also submit a description of the seismic analysis input information which 1s contained in each document.
Identify systems or portions of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3. Submit all of thfs information within 30 days of the date of this bulletin.
2.
For portions of systems which are normally accessible~,
inspect one system in each set of redundant systems and all nonredundant systems for con-formance to the seismic analysis input information set forth in design documents.
Include 1n the inspection:
pipe run geometry; support and restraint design, locations, function and clearance (including floor and wall penetration);
embedments (excluding those covered 1n IE Bulletin 79-0P.); pipe attachements; and valve and valve operator locations and weights (excluding those covered in IE Bulletin 79-04).
Nthfn 60 days of the date of this bulletin, submit a description of
'he results of this inspection.
Mhere nonconformances are found which affect operability of any system, the licensee will expedite completion of the inspection described in Item 3.
NNHy lli f
t th f
h pl t II*1 5
during reactor operation.
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