ML20024H370
| ML20024H370 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 05/16/1991 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | Tuckman M DUKE POWER CO. |
| Shared Package | |
| ML20024H371 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-79196, TAC-79197, NUDOCS 9106030160 | |
| Download: ML20024H370 (2) | |
Text
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i May 16, 1991 Docket ?!as. 50 413 D I ST R I B UT 10t!-
and EO-414 Dock e tTiTe~
PMarcus NPC & Local PDPs ACPS(10)
Mr. ii. S. Tucknan, Vice h esident PD1!.3 Reading Catawba R/F tluclear Operations SVarga Oute Power Cor'pany JCalvo P. O. Cox 1007 P!ngran Charlotte,tiorth Carolina 2E201-1007 PFartin OGC
Dear fir Tuckman:
EJordan, 3701 SUPJECT:
C0t1 FORT'AtiCE TO REGUL ATORY CUIDE 1.97, PEVIS10fl 2 CUIDAt Cf ON SOLUPLE POR0h CONCEt3 PAT 10t; M0tilTOR1tlG (TAC NOS. 79196,79197)
The Dute Power Company submitted a request by let ter dated October 23, 1990 for a deviation fror: the recornendations of Peculatory Guide (R.G.) 1.9e relating to the reactor coolant systen soluble boron concentration i n s t run:en t e t i on.
Pased on the NRC staff's review, it has been concluded that Dule Power Corpeny's use of the post accident sempling systen (PASS) to raonitor RCS soluble boron concentration is acceptable. The staff's evaluation is provided in the enclosed Safety Evaluation.
This completes our effort s in response to your subraittal of October P3,199C' end it s associated TAC t!os. 79196, 79197.
Sincerely,
/s/
Pobert t!artin, Senior Project t'anager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of tluclear Peactor Regulation
Enclosure:
Safety Evaluation CC:
See next page OFC
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May 16,1991 Docket Nos. 50-413 and 50-414 Mr. M. S. Tuckman, Vice President Nuclear Operations Duke Power Company P. O. Box 1007 Charlotte, North Carolina 28201-1007
Dear Mr. Tuckman:
SUBJECT:
CONFORMANCE TO REGULATORY GUIDE 1.97, REVISION 2 GUIDANCE ON SOLUBLE BOR0tl CONCENTRATION M0ftlTORING (TAC NOS. 79196,79197)
The Duke Power Company submitted a request by letter dated October 23, 1990 for a deviation itom the recommendations of Regulatory Guide (R.G.) 1.97 relating to the reactor coolant system soluble boron concentration instrumentation.
Based on the NRC staff's review, it has been concluded that Duke Power Company's use of the post accident sampling system (PASS) to monitor RCS soluble boron concentration is acceptable. The staff's evaluation is provided in the enclosed Safety Evaluation.
This ccmpletes our efforts in response to your submittal of October 23, 1990 and its associated TAC Nos. 79196, 79197.
Sincerely, hi e
/ Robert !!artin, Senior Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation Cc:
See next page e
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