ML19296B364
| ML19296B364 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/15/1980 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| TAC-12868, NUDOCS 8002200468 | |
| Download: ML19296B364 (4) | |
Text
e D38 (412) 456-6000 435 Sixth Avenue Pittsburgh, Pennsylvania n2n Feb ruary 15, 1980 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
A. Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Relief Request for Inservice Inspection Examinations Gentlemen:
Enclosed are three (3) signed originals and thirty-seven (37) copies of a request for relief from ASME Section XI code requirements as permitted under 10 CFR 50.55a(g)(5)(iii) and for which relief should be granted in accordance with 10 CFR 50.55a(g)(6)(1).
This request pertains to certain requirements for non-destructive examinations (NDE) which were part of our October 10, 1977 Inservice Inspection Program.
The proposed change has been requested because of ALARA considerations related to high radiation levels present in the areas to be examined; i.e.,
the reactor vessel closure head, the interior of the pressurizer and the interior of the prinary side of the steam generators.
Our Technical Specification change request dated October 10, 1977, requested that Appendix A Technical Specification pages 3/4 4-30a through g be deleted from the Technical Specification as representing an unnecessary repetition of a portion of the ASME XI Inservice Inspection Program.
Furthermore, we have now completed the special inspection requirements described on page 3/4 4-30h for the reactor vessel safe ends. No reportable defects were found; we, therefore, have determined that page 3/4 4-30h should also be deleted.
Safety Evaluation There is no decrease in the safety posture of the Beaver Valley Power Station as a result of the proposed change to the Inservice Inspection Program.
The design of the closure head and the vessels accounts for the stress loads i
R7 800m
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Relief Request for Inservice Inspection Examinations Page 2 to be adequately accommodated by the ferritic base material.
These base materials are examined volumetrically as required by other examination categories.
In addition, cladding examinations are no longer required in later editions of ASME Section XI.
In accordance with the requirement of 10 CFR 170.22, we are enclosing a check in the amour.t of $4,000 for this Class III change.
Very truly yours,
C+/A
~
C. N. Dunn Vice President, Operations Attachment
Specific Relief Request for Inservice Inspection Program Beaver Valley Power Ftation, Unit No. 1 Docket No. 50-334 Request relief from performing visual and surface or volumetric examination of the reactor vessel closure head cladding and visual examination of the pressurizer and steam generator vessel cladding.
(Items Bl.13, B2.8 and B3.7, Examination Categories B-I-l and B-I-2).
Code Requirements Visual and surf ace or volumetric examination of the reactor vessel closure head cladding shall include at least six patches (each 36 sq. in.)
evenly distributed in the closure head.
The examinations performed during each inspection interval shall cover 100% of the patch areas.
Visual examination of the pressurizer and steam generator vessel cladding shall include at least one patch (36 sq. in.) near each manway in the primary side of the vessel. The examinations performed during each inspection interval shall cover 100% of the patch areas. The examination of the patch areas in the pressurizer and steam generator may be performed at or near the end of the inspection interval.
Basis for Requesting Relief The design of the vessels and the closure head accounts for the stress loads to be adequately accommodated by the ferritic base material which is examined volumetrically as required by other examination categories. Additional technical guidance is provided by later editions of ASME Section XI where cladding examinations are no longer required.
The examination of the reactor vessel head cladding patches and the pressurizer and steam generator vessel cladding patches is impractical to perform because of the relatively high radiation levels prest. in the areas required to be visually examined. Other examinations which will be performed on these comp /nents will give more meaningful data about the structural acceptability of the components.
(CORPORATE SEAL)
Attest:
Jf YLW H. W. Staas Secretary-COMMONWEALTH OF PENNSYLVANIA)
) SS:
COUNTY OF ALLEGIENY
)
On this M
day of
- 1980, a Notary Ptfbiic in and for said before me, q7ppv g,gmEcgEp Commonwealth and County, personally appeared C. N. Dunn, who being duly sworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.
Y G. ST0ECKER, Notary Public Pittsburgh, A:legter:y County, Pa.
M Ccmm;ssicn Enires
/
february 20, 1982