ML20024H253
| ML20024H253 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 05/23/1991 |
| From: | Checca A COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-57198, TAC-63250, TAC-64029, TAC-64056, NUDOCS 9105310038 | |
| Download: ML20024H253 (3) | |
Text
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Commonwoalth Edison 1400 opus Place a
yg Downers Grove, lit 6nois 60515 May 23,1991 Dr. Thomas E. Murley, Director Office Of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 TAC Nos. F7198,63250,64029,64056 Regulatory Guide 1.97 Compliance NRC Docket.Nos,_50:454/455 and 50-450/457
Reference:
(a) February 27,1987 K.A. Ainger letter to H.R. Denton (b) September 1,1987 S.C. Hunsader letter to T.E. Murley (c) November 6,1987 L, Olshan letter to L.D. Butterfield (d) December 28,1987 S.C. Hunsader letter to T.E. Murley (e) May 5,1988 L. Olshan letter to H.E. Bliss (f) July 27,1988 S.C. Hunsader letter to T.E. Murley (g) May 19,1989 S.P. Sands letter to T.J. Kovach (h) June 19,1989 R.W. Cooper letter to T.E. Murley (i) July 24,1989 R.W. Cooper letter to Cordell Reed (j)
August 1,1989 S.C. Hunsader letter to T.E. Murley
Dear Dr. Murley:
Reference (a) provided Commonwealth Edison's (Edison) preliminary evaluation of the Byron and Braidwood instrumentation for comaliance with Regulatory Guide 1.97, Revision 3. Reference (b) provided the results of Edison's final evaluation which were included as Attachments to that letter. Attachment A to reference (b) provided an update of Table 51. Attachment B to reference (b) provided the revised Human Factors Engineering Review. These supplemented the information provided in reference (a) and, together, constituted Edison s
- Final Report" concerning Regulatory Guide 1.97 compliance for the Byron and Braidwood Stations.
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' D Thomas E. Murley May 23,1991 Reference (c) provided the results of the initial NRC review and evaluation of a
references (a) and (b). Edison's response to these was provided in reference (d). In reference (e), the NRC staff indicated that it had completed its review of Edison's submittals and had concluded that Edison's justification for the exceptions to Regulatory Guide 1.97, Revision 3 for some items was acceptable. However, for other items, additional justification was required.
i in response to the NRC staff's review, reference (f) provided the additional
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justification or provided an appropriate response to the NRC staff's concerns.
Subsequently, reference (g) was issued that reported final results of the NRC Staff review of Edison's submittals.
Reference (h) provided corrected pages to two (2) of Edison's submittals as identified during the NRC Inspection at Braidwood during the week of June 12,1989.
Reference (1) provided the results of the NRC inspection at Braidwood Station during the week of June 12,1989 (456/457 89018) which included an inspection of the implementation of Reg Guide 1.97. Reference (j) provided justification for the continued use of the existing Spray Additive Tank Levelindication and provided the implementatirn schedule, requested in Reference (g). In reference (g), all open items had been accepted by the NRC staff with the exception of the following:
1 Accumulator Tank Level and Pressure 2
Containment Sump Water Temperature 3
RHR Heat Exchanger Outlet Temperature 4
Ouench Tank Temperature Attachment A provides the status and actions taken for these items.
Please address any questions regarding this submittal to this office.
Very truly yours, IC t.cx n.
Allen R. Checca Nuclear Licensing Administrator Attachment cc: R.M. Pulsifor Pr<: Ject Manager, NRR i
A.H. Hsia Proiect Manager, NRR W. Shafer-Chief, NRR W. Kropp-Senior Resident inspector-BY S. Dupont Senior Resident inspector-BW ARC / sci:lD767:31
ATTACHMENT A BYRON /BRAIDWOOD UNITS 1 AND 2 REGULATORY GUIDE 1.97 REV. 3 COMPLIANCE STATUS AND_ACIloN_
SUMMARY
The NRC Staff issued the Byron /Braldwood Safety Evaluation Report (SER) regarding compliance to Regulatory Guide 1.97 Revision 3 on May 14,1989. All justifications have been accepted by the NRC staff except for four (4) items. The following describes the status and the applicable implementation schedule for
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upgrading these items:
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1.
ACLU.MULAIOB IANK LEVEL ANDERESSURE The NRC staff is continuing to review and determine on a generic basis, the need to replace this instrumentation. Since this is the case, no action is being taken at this time.
2.
CONIAIN M E NI_ S UM P_WAIE B_T E M EE RATU B E The NRC staff is continuing to review and determine on a generic basis, the need to replace this Instrumentation. Since this is no case, no action is being taken at this time.
3.
B HILH E AT_ EXC H AN G E B_O.VIL ELT E M E EB AT_U R E The existing RHR heat exchanger outlet temperature instrumentation has been replaced with environmentally qualified instrumentation.
This modification has been completed on Byron Unit 2 and Braidwood Unit 1.
Byron Unit 1 and Braidwood Unit 2 will be completed during the next refueling outages, which are scheduled for September,1991.
4.
QUENCILIANK_TEMPERATUBE The pressurizer relief tank temperature instrumentation was replaced with environmentally qualified instrumentation that contains the appropriate temperature range scale:
This modification has been completed on Byron Units 1 and 2 and Braidwood Unit 1.
Braidwood Unit 2 will be completed during the next refueling outage, which is scheduled for September,1991.
ARC /scl:lD767:32
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