ML14191A311
| ML14191A311 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/18/1987 |
| From: | Eccleston K Office of Nuclear Reactor Regulation |
| To: | Utley E Carolina Power & Light Co |
| References | |
| TAC-65905 NUDOCS 8712240194 | |
| Download: ML14191A311 (4) | |
Text
- ISTRIBUTION:
1987 Docket Fil E. Jordan S1987NRC & Local PDRs J. Partlow Docket No.:
50-261 PD 21 Reading Wanda Jones S. Varga E. Butcher G. Lainas ACRS (10)
Mr. E. E. Utley, Senior Executive P. Anderson GPA/PA Vice President K. Eccieston ARM/LFMB Power Supply and Engineering & Construction OGC-Bethesda R. Diggs Carolina Power & Light Company D. Hagan Post Office Box 1551 T. Barnhart (4 cys for each Docket Raleigh, North Carolina 27602 No.)
Dear Mr. Utley:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION -EVALUATION OF REDUCTION OF STATION SAFETY-RELATED BATTERIES DUTY CYCLE FROM EIGHT HOURS TO ONE HOUR (TAC No. 65905)
Reference:
May 22, 1987 letter from G.P. Beatty, Jr. (CP&L) to Dr. J.N. Grace (USNRC)
The reference letter transmitted a copy of an evaluation performed by CP&L pursuant to 10 CFR 50.59 to support a reduced battery duty cycle of one hour in lieu of the eight hour duty cycle stated in the Final Safety Analysis Report (FSAR) for Robinson 2.
Our review of this evaluation indicates that sufficient technical information was not provided to support such a change. Accordingly, we have developed the enclosed request for additional information in order that we may complete our review.
Please provide your response within 30 days of receipt of this letter.
This request for information affects fewer than ten respondents; therefore, 0MB clearance is not required pursuant to Public Law 96-511.
Sincerel Kenneth T. Eccleston, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects I/Il Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
8712240194 f 7121B See next page PDR ADOCe (o00U261 p
PDR_
nAME
- KEccleston ame e
o y
st in t F
Se
)ATE :9/ 1/87 8
/7 iI-~
7 ReportL (SR) frR obno 2.
Mr.;E. E. Utley Carolina Power & Light Company H. B. Robinson 2 cc:
Mr. R. E. Jones, General Counsel Mr. Dayne H. Brown,Chief Carolina Power & Light Company Radiation ProtectionBranch P. 0. Box 1551 Division of Facility Services Raleigh, North Carolina 27602 Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008 Mr. McCuen Morrell, Chairman Darlington County Board of Supervisors Mr. Robert P. Gruber County Courthouse Executive Director Darlington, South Carolina 29535 Public Staff -
NCUC P.O. Box 29520 Mr. H. A. Cole Raleigh, North Carolina 27626-0520 Special Deputy Attorney General State of North Carolina P.O. Box 629 Raleigh, North Carolina 27602 Mr. D. E. Hollar Associate General Counsel Carolina Power and Light Company P.O. Box 1551 Raleigh, North Carolina 27602 U.S. Nuclear Regulatory Commission Resident Inspector's Office H. B. Robinson Steam Electric Plant Route 5, Box 413 Hartsville, South Carolina 29550 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Suite 2900 101 Marietta Street Atlanta, Georgia 30303 Mr. R. Morgan General Manager H. B. Robinson Steam Electric Plant Post Office Box 790 Hartsville, South Carolina 29550 Mr. Avery Upchurch, Chairman Triangle J Council of Governments 100 Park Drive Post Office Box 12276 Research Triangle Park, NC 27709
Enclosure REQUEST FOR ADDITIONAL INFORMATION (H. B. ROBINSON UNIT 2 - EVALUATION OF REDUCTION OF STATION SAFETY-RELATED BATTERIES DUTY CYCLE FROM EIGHT HORS TO ONE HOUR)
- 1) The DC power system is acceptable when the system has the required redun dancy, meets the single failure criterion, is protected from the effects of postulated accidents, is testable, and has the capacity and capability to supply DC power to all safety loads. Section 8.3.2 of your FSAR notes that "Each of the two safety-related station batteries is sized to carry its expected shutdown loads following a plant trip and a loss of all AC power for a period of 8 hrs without battery terminal voltage falling below 105 volts." In view of your proposed reduction of safety-related battery duty cycle from eight hours to one hour, provide a justification for this proposed change.
- 2) With respect to NRC requirements (NUREG-0611/0737, Items II.E.1.1 & 2) for Auxiliary Feedwater (AFW) system reliability after the Three Mile Island Unit 2 accident, there were two requirements (GS-5 and GL-3) regarding capability to provide the required AFW flow for at least two hours from one AFW pump train independent of any AC power sources (i.e., relying on only DC power). We found H. B. Robinson Unit 2 in compliance with our short term requirement (GS-5) pending justification of the procedure (manual initia tion by the operator). As for the long term requirement (GL-3) which requires an automatic initiation of the AFW system flow, your response indicated that the requirement (not a backfit) was unwarranted since H. B. Robinson Unit 2 had never experienced a loss of offsite power in the past 20 years and an extra (dedicated shutdown) diesel generator has been installed. Further, it stated that "CP&L disagrees with the position that loss of all AC power is a credible event at H. B. Robinson." In view of a
-2 recent loss of offsite power event that occurred with one diesel (B) out of service on January 28, 1986 and a reduction of battery duty cycle to one hour, we believe that TMI requirement GL-3 is valid. Provide an analysis acceptable to the staff to justify your position or proposed plant modifi cations to support the plant power requirements for safety systems.
- 3) In the licensee's 10 CFR 50.59 review, credit was taken for implementation.
of the Emergency Operating Procedure (EOP) network which requires AC power to be restored to at least one of the two associated safety-related battery chargers within thirty minutes whenever a battery is in-service, thereby assuring full power source capability to at least one battery bus.
Our review of your Technical Specification contains no Limiting Condition for Operation (LCO) provisions regarding inoperable battery or battery charger.
Our brief survey of single unit plants such as Robinson (Palisades, R. G.
GINNA, and Fort Calhoun), which have a similar offsite design feature and were licensed in the same time frame (1970-74), indicates that all have such LCOs. Furthermore, our Standard Technical Specification requires such LCOs. We believe that the Robinson Technical Specification should include the same LCO. Provide a justification for not having the LCOs in your Tech nical Specification or propose a technical specification revision.