ML20151F904
| ML20151F904 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/14/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | Tison Campbell ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8807280006 | |
| Download: ML20151F904 (4) | |
Text
'
[po ssog I
o UNITED STATES E 3 # N NUCLEAR REGULATORY COMMISSION g
-p WASHINGTON, D. C. 20555 g
,/
July 14,1988
+....
Docket No. 50-313 Mr. 7. Gene Campbell Vice President, Nuclear Operations Arkansas Power and Light Company Post Office Eox 551 Little Rock, Arkansas 72203
Dear Mr. Campbell:
SUBJECT:
NRC EVALUATION OF BWOG GENERIC REPORT "DESIGN REQUIREMENTS FOR DSS AND AMSAC" l
l The purpose of this letter is to provide the staff's evaluation of B&W Document i
I 47-1159091-00, "Design Requirements for Diverse Scram System (DSS) and ATWS Mitigation System Actuation Circuitry (AMSAC)," prepared by Babcock and Wilcox for the Babcock and Wilcox Owners Group (BWOG) ATWS Committee. This BWOG generic report was subritted by letter dated October 9, 1985 (from J. Ted Enos, Chairman BWOG ATWS Comittee to Hugh L. Thompson, NRC) pursuant to requirements specified in the Code of Federal Regulation (CFR), Section 10 CFR 50.62, "Requirements for Reduction of Risk from ATWS Events for Light-Water-Cooled Nuclear Power Plants."
The BWOG generic report provides the generic design basis for ATWS modifications of B&W type nuclear power plants required by 10 CFR 50.62.
Subsequent to the generic report sebmittal, the staff met with members of the BWOG ATWS Standing Comittee, on October 28, 1987 to discuss potential open items which were raised during the staff review of the generic report.
Following this meeting, the BWOG submitted another set of responses to the remaining open items by letter dated December 1, 1987 from J. Ted Enos (BWOG) to Frank J. Miraglia (NRC).
Based on our review of the infonnation provided in the BWOG generic report and the supplemental letter of December 1, 1987, the staff concludes that most sections of the generic report are acceptable for providing generic guidelines for plant-specific design submittals.
However, some areas of the generic design are still of concern to the staff. Therefore, the staff has presented several designrequirementsintheenclosedSafetyEvaluation(SE)whichshouldbe followed by the utilities when considering their plant-specific DSS and AMSAC designs. Following are the areas of concern that plant-specific submittals must
- address, o The BWOG generic report is not acceptable where addressing the use of power supplies for DSS and AMSAC.
In this regard, the staff suggests that special attention be given to the acceptable methods as presented in Section 5.6 of the SE.
o The use of qualified isolation devices should also be addressed in detail in the plant-specific submittals. Whether diverse or existing 8807280006 880714 M(g f PDR ADOCK 05000313 Vf P
PNU.
l
- isolators are used, the staff. suggests that the utilities use Section 5.1 and 5.2 of the SE for guidance when addressing this issue in their submittals, o The plant-specific submittals must provide detailed information which describes how a total loss of feedwater flow will be detected and why the reasurements chosen are indicative of a total loss of feedwater flow. Section 6.5 of the SE provides additional guidance that the plant-specific submittal should consider when addressing the input parareters which have been chc3en to initiate DSS and/or AMSAC.
o Other areas of concern to the staff include:
(1) bypasses and displays, and (2) surveillance and testing.
Specific guidance for plant-specific submittals are presented in Sections 5.9 through 5.12 and 5.14 for "Bypasses and Displays" and Section 6.4 for "Surveillance and Testing" of the SE.
Design details such as physical and operational characteristics of those DSS and AMSAC components which are not addressed in either the BWOG generic report or the plant-specific submittals and way influence the staff's conclusions concerning compliance to requirements of the ATWS 50.62 "rule" will be reviewed and inspected on a plant specific basis.
In sunmary, the staff requests that licensees of B&W designed nuclear power plants who are part of the BWOG and are connitted to the requirements specified in the ATWS 50.62 "rule" provide plant-specific submittals which address these requirements and schedules for installation of the equipment no later than 90 working days from the date of receipt of this Safety Evaluation. With this acceptance of the proposed generic design, we would now expect each licensee to proceed with implementation of the ATWS modifications.
Should you have any questions concerning the matters discussed above or the content of the attached SE, please contact Vincent Thomas of our staff on (301) 492-0786.
Sincerely,
)
Jcse A. Calvo, Director Proiect Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
DI BUTION See next page
@6cket File NRC& Local PDR PD4 Read.
L. Rubenstein J. Calvo P. Noonan C. Harbuck OGC-WFN E. Jordan B. Grimes V. Thomas ACRS(10)
PD4 Plant File PDIV:PM @Eb PDIV:D g
PDIV:
CHarbuck:
JCalvo Yl' PNoona 7/p//
q /d /88 1/W/88
a
' isolators are used, the staff suggests that the utilities use Section 5.1 and 5.2 of.the SE for guidance when addressing this issue in their submittals.
o The plant-specific submittals must provide detailed information which describes how a total loss of feedwater flow will be detected and why the measurements chosen are indicative of a total loss of feedwater flow.
Section 6.5 of the SE provides additional guidance that the plant-specific submittal should consider when addressing the input parameters which have been chosen to initiate DSS and/or AMSAC.
o Other areas of concern to the staff include:
(1) bypasses and displays, and (2) surveillance and testing. Specific guidance for plant-specific submittals are presented in Sections 5.9 through 5.12 and 5.14 for "Bypasses and Displays" and Section 6.4 for "Surveillance and Testing" of the SE.
Design details such as physical and operational characteristics of those DSS and AMSAC components which are not addressed in either the BWOG generic report or the plant-specific submittals and may influence the staff's conclusions concerning compliance to requirements of the ATWS 50.62 "rule" will be reviewed and inspected on a plant-specific basis.
In sumary, the staff requests that licensees of B&W designed nuclear power plants who are part of the BWOG and are comitted to the requirements specified in the ATWS 50.62 "rule" provide plant-specific submittals which address these requirements and schedules for installation of the equipment no later than 90 working days from the date of receipt of this Safety Evaluation. With this acceptance of the proposed generic design, we would now expect each licensee to proceed with implementation of the ATWS modifications.
Should you have any questions concerning the matters discussed above er the content of the attached SE, please contact Vincent Thomas of our staff on (301) 492-0786.
Sincerely, 4,
d W
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
a Mr. T. Gene Campbell Arkansas Nuclear One Arkansas Power & Light Company Unit Nos. I and 2 cc:
Mr. Dan R. Howard, Manager Mr. Charles B. Brinkman, Manager Licensing Washington Nuclear Operations Arkansas Nuclear One C-E Power Systems P. O. Box 608 7910 Woodmont Avenue Russellville, Arkansas 72801 Suite 1310 Bethesda, Maryland 20814 Mr. James M. Levine, Executive Director Site Nuclear Operations Mr. Frank Wilson, Director Arkansas Nuclear One Division of Environmental Health P. O. Box 608 Protection Russellville, Arkansas 72801 Department of Health Arkansas Department of Health Nicholas S. Reynolds, Esq.
4815 West Markham Street Bishop, Liberman, Cook, Little Rock, Arkansas 72201 Purcell & Reynolds 1200 Seventeenth Street, N.W.
Honorable William Abernathy Suite 700 County Judge of Pope County Washington, D.C.
70036 Pope County Courthouse Russelville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Senior Resident Inspector U.S. Nuclear Regulatory Commission 1 Nuclear Plant Road Russellville, Arkansas 72801 Ms. Greta Dieus, Director Division of Environmental Health Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852