ML20098F591
| ML20098F591 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 09/24/1984 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 9212N, GL-82-83, NUDOCS 8410030167 | |
| Download: ML20098F591 (5) | |
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'T Commonwealth Edison
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,) one First Natiorul Plaza Chicfgo. Ilknois t
~k O ~J AddrIss R: ply to: Post Offica Box 767 N
/ Chicago, tilinois 60690 September 24, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Sub ject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 NUREG-0737, Supplement 1 Requirements for Emergency Response Capability (Generic Letter No. 82-33)
NRC Docket Nos. 50-454/455 and 50-456/457 References (a):
December 17, 1982 letter from D. G.
Eisenhut to Licensees and Applicants.
(b):
December'6, 1983 letter from Cordell Reed to H. R. Denton.
Dear Mr. Denton:
This letter provides updated implementation schedules for specific improvements in emergency response capability required to satisfy the requirements of NUREG-0737, Supplement 1, which were imposed in reference (a).
These updated schedules supersede all previous schedules, the last of which.were provided in reference (b).
Attachme'nt A to this letter contains the updated schedules for Substantive completion of the NUREG-0737, Supplement 1 requirements.
changes have been highlighted with a vertical bar in the righthand margin.
A calendar date has been specified for operability of the Byron 1 Safety Parameter Display System (SPDS) rather than the deadline of commercial service used previously.
The Byron 2 and Braidwood SPOS's will be operational by fuel load..The implementation schedules for the revised E0P's have also been respecified based on an understanding that the NRC will be approving. revision 1 of the EPG's in late 1984.
The implementation of.the A-model has been postponed to provide adequate time to implement the necessary hardware and software changes.
Adequate alternate dose calculation techniques are available as described in reference (b).
Please address questions regarding these changes to this office.
One signed original and fifteen copies of this letter and the attachment are provided for NRC review.
Very truly yours, I h-DR O
O 00 54 F
PDR T. R. Tramm Nuclear Licensing Administrator i i cc:
Byron Resident Inspector i
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ATTACHMENT A Revised Section 9 Byron /Braidwood Schedules 9212N
n SECTION 9 SCHEDULES EMERGENCY RESPONSE CAPABILITY BYRON BRAIDWOOD I '.
SAFETY PARAMETER DISPLAY SYSTEM (SPDS) a.
' Submit Safety Analysis 1)
Criteria for parameter selection including V&V 12-29-63 12-29-83 description 2)
HFR of data display and functions (assumes NRC acceptance of DCRDR final summary report within 2 months) 08-01-87 08-01-87 3).
Verify parameter selection (assumes NRC acceptance of DCRDR final summary report within 2 months) 08-01-87 08-01-87 b.
SPDS 0perational - Defined as design, hardware and software installation, functional testing, and initial operator training complete 03-30-85 Prior to fuel load
-c.
Modifications to SPDS resulting from DCRDR, SPDS HFR, or RG 1.97
- 1) -Submit schedule 08-01-87 08-01-87
-II.
DETAILED CONTROL ROOM DESIGN REVIEW (DCRDR) a.
Submit Program Plan 04-14-83
.04-14-83 b.
Submit Final Summary Report 12-01-86 12-01-86 III. REGULATORY GUIDE 1.97 - REVISION 2 a.
Submit a preliminary report 03-01-87 03-01-87 describing how the requirements of Reg. Guide 1.97 specified in Supplement 1 to NUREG-0737 have been or will be met.
9212N
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' Page 2 -
SECTION 9 SCHEDULES u
EM$RGENCY RESPONSE CAPABILITY BYRON
'BRAIDWOOD b.
. Submit a final report 09-01-87 09-01-87 including a schedule for installation.(assumes NRC acceptance of DCRDR results within;3 months of submittal date of DCRDR summary report for'that Station).
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IV. - UPGRADE EMERGENCY OPERATING PROCEDURES (EOPs) a.
Submit Procedures Generation 3 months 3 months.
Package for WOG EPG Revision 1.
from NRC from NRC approval of approval of Revision 1 Revision 1 guidelines.
~ guidelines.
b.
Implement upgraded E0Ps based 12 months fuel load
.upon Revision l guidelines.
from NRC approval of Revision 1 guidelines V.
EMERGENCY-RESPONSE FACILITIES a.
Technical Support Center (TSC) 1)
Complete with-the exception Prior to Prior to of impact due to RG 1.97 and Fuel Load Fuel Load HFR 2); Modifications to TSC resulting from-RG 1.97 and HFR (assumes NR acceptance of. DCRDR results with
- months of submittal date of DCRD summary report for that station) a.-Submit schedule 06-01-87 06-01-87 o
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~SECTION 9 SCHEDULES
. EMERGENCY RESPONSE CAPABILITY BYRON BRAIDWOOD b.
-Operational Support Center (OSC)
Prior to Prior to
-Fuel Load Fuel Load c.
' Emergency 0perations Facility (EOF)
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1)' Complete with the exception
. Prior to Prior to of impact due to RG 1.97 Fuel Load Fuel Load and HFR, and A-model, and industrial security
..a.
Modifications to EOF resulting from RG 1.97 and HFR
- 1) Submit schedule 06-01-87 06-01-87
- b. Implement A-model 01-01-86 Prior to Fuel load
- c. Implement' Industrial Prior to' Prior to Security including-Fuel Load Fuel Load remote alarm 9212N l
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