B14926, Provides Addl Info on GL 93-05 as Requested by NRC During 940726 Telcon & to Modify 940602 Proposed Rev to Ts.Proposed TS Per GL 93-05 & Various Administrative Changes Retyped Pages Encl
| ML20072L308 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/25/1994 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20072L311 | List: |
| References | |
| B14926, GL-93-05, GL-93-5, NUDOCS 9408310194 | |
| Download: ML20072L308 (3) | |
Text
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i Northeast 107 seiden street, Berlin, er 06037
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(203) 665-5000 August 25, 1994 Docket No. 50-423 B14926 Re:
GL 93-05 i
10CFR50.90 j
U.S.
Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Generic Letter 93-05, Additional Information The purpose of this letter is to provide additional information on Generic Letter (GL) 93-05 as requested by the NRC Staff during a conference call on July 26, 1994, and to modify our submittal of June 2,
- 1994m, Northeast Nuclear Energy Company (NNECO) has determined that eleven of GL 93-05 recommendations are compatible with plant operating experience
- and, therefore, are appropriate to incorporate into the Hillstone Unit No. 3 Technical Specifications.
With regard to NNECO's position on the partial implementation of the proposed change suggested in Section 7.1 of GL 93-05, NNECO has done so since the boron concentration of the Millstone Unit No.
3 refueling water storage tank (RWST) is covered under a
separate technical specification (i.e.,
specification 3.5.4).
This specification's minimum boron concentration is higher than the minimum boron concentration of the accumulator (i.e.,
specification 3. 5.1).
Therefore, NNECO has concluded that it is unnecessary to verify that the RWST boron concentration is equal to or greater than the accumulator boron concentration as suggested by Section 7.1 of GL 93-05, and as a result, has only incorporated a portion of the suggested change into Technical Specification 3/4.5.1, " Accumulators."
It is noted that the remaining changes to the Millstone Unit No. 3 Technical Specifications transmitted via letter dated June 2, 1994, and retransmitted via this letter, are consistent with the GL 93-05 guidance.
(1)
J.
F.
Opeka letter to the U.S.
Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications, Generic Letter 93-05, and Various Administrative Changes,"
dated June 2, 1994.
9408310194 940835 PDR ADOCK 0500042,3 8
PDR I
,i U.S.
Nuclear Regulatory Commission B14926/Page 2 August 25, 1994 With this submittal, NNECO is also retracting certain administrative technical specification changes which were included in our letter dated June 2, 1994.
NNECO has determined that certain of these proposed administrative changes would involve significant procedural modifications without a
commensurate safety benefit.
These changes involve:
(1) Index Page x will continue to be revised to add Table 4.7-2 which was missing, and to renumber the pages in the index, but the proposed deletion of Tables 3.7-4 and 3.7-5 and Sections 3.7.12 and 3.7.13 and the ensuing renumbering of the remaining table numbers and section numbers that was proposed previously will not be done; (2) Index Page xv will be revised to remove an extra carriage return and to correct the page number of Section 3/4.9.14, but will not be revised to delete Sections 3/4.7.12 and 3/4.7.13 and renumber Section 3/4.7.14 as was requested previously; (3)
Section 3/4.7.14 and Basis Section 3/4.7.14 will not be renumbered as Section 3/4.7.12 and B 3/4.7.12 as previously requested, but these sections will be repaginated; (4)
Table 3.7-6 will not be renumbered as Table 3.7-4, but this table will be repaginated.
The attachment contains a complete set of the retyped technical j
specification pages.
These pages reflect the most current technical specifications for Millstone Unit No.
3.
These pages reflect the currently issued version of the technical specifications.
They do not include changes previously proposed in submittals dated April 18, 1994,0) and May 6, 1994.0)
Therefore, NNECO suggests that the NRC Staff check with'NNECO for continuity with the Millstone Unit No. 3 Technical Specifications prior to issuance.
It should be noted that the safety analysis, significant hazards consideration, and environmental impact discussion previously included in the June 2,
- 1994, amendment request remains valid.
(2)
J.
F.
Opeka letter to the U.S.
Nuclear Regulatory Commission,
" Millstone Nuclear Power Station, Unit No.
3, Proposed Revision to Technical Specifications, Area Temperature Monitoring Surveillance Requirements,"
dated April 18, 1994.
(3)
J.
F.
Opeka letter to the U.S.
Nuclear Regulatory Commission,
" Millstone Nuclear Power Station, Unit No.
3, Proposed Revision to Technical Specifications, Reactor Trip System Instrumentation Surveillance Requirements Functional Unit 21, Reactor Trip Bypass Breakers," dated May 6, 1994.
r
F.~
.].
o U.S. Nuclear Regulatory Commission B14926/Page 3 August 25, 1994 We believe the above information, coupled with the information provided in our June 2, 1994, submittal provides a complete basis for approval of the requested amendment.
Should the NRC Staff require any additional information, please contact Mr. R. G. Joshi at (203) 440-2080.
Very truly yours, l-l NORTHEAST NUCLEAR ENERGY COMPANY Itd. 4 -
J.
F. Opejd 1)
Executive Vice President cc:
T. T. Martin, Region I Administrator V.
L.
Rooney, NRC Project Manager, Millstone Unit No. 3 P-D.
Swetland, Senior Resident Inspector, Millstone Unit Nos.
1, 2,
and 3 Subscribed and sworn to before me this day of h/s//xb 1994
& ((n a A d!A X e y
Date Commission Expires:
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