ML20054C449
| ML20054C449 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/19/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8204210100 | |
| Download: ML20054C449 (2) | |
Text
....
THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P o BOX 5000 m CLEVELAND. OHIO 44101 e TELEPHONE (216) 622-9800 m ILLUMINATING BLDG e 55 PUBLIC SOUARE Serving The Bect Location in the Nation Dalwyn R. Davidson
- ; r AlblCE NT s <S TE V E *. LNE ERNG AND CONSTRUCTION O
9 April 19, 1982 RECElVEO kb a
Mr. A. Schwencer
- seg, engg a
//
Chief, Licensing Branch No. 2 Egg b
Division of Licensing U. S. Nuclear Regulatory Commission g
Washington, D. C.
20555 Perry nuclear Power Plant Docket Nos. 50-440; 50-441 Operational 0. A. Program
Dear Mr. Schwencer:
This letter and the enclosed information is submitted to provide further clarification to our responses of March 26, 1982, regarding the items covered by our operational quality assurance program.
Please advise us if we can be of any further assistance.
Very Truly Yours,
/
Dalwyn R. Davidson Vice President System Engineering and Construction DRD:
mlb cc:
John Stefano Max Gildner Jay Silberg, Esq.
Jack Sprahl 61 I
i 8204210100 820419 PDR ADOCK 05000440 PDR A
...e 260.6
Response
The following item responses have been revised since our March 26, 1982 submittal. The item responses listed below supercede our earlier responses.
a.19 There are no foundations for seismic category 1 electrical duct banks and manholes. The safety-related duct banks and manholes are constructed of rein-forced concrete, backed by seismic category 1 fill, and will be added to Item XXXIV.
a.20 The site grading is not safety-related; however, major modifications to final plant site grading which could significantly affect site drainage will be subject to the pertinent requirements of the operntional quality -
assurance program.
C.4
~II.B.3 The post-accident sampling system design has not been finalized, but it is not required to be safety-grade.
Surveill ance testing and system operation will be controlled in accordance with plant operating procedures.
(See NOTE 1)
C.21 III.A.l.2 Emergency support facilities are not safety-grade and are not included in Table 3.2-1.
The emergency response facilities equipment and applicable documentation is l
controlled in accordance with the pertinent requirements I
of the operational quality assurance program.
(See NOTE 1)
C.22 III.D.3.3 Inplant 1 radiation monitoring equipment is not safety-2 grade and will not be included in Table 3.2-1.
The use l
of this equipment will be controlled in accordance with plant operating procedures.
(See NOTE 1) i
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