ML17348A372
| ML17348A372 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/05/1990 |
| From: | Edison G Office of Nuclear Reactor Regulation |
| To: | Goldberg J FLORIDA POWER & LIGHT CO. |
| References | |
| TAC-69023, TAC-69024, NUDOCS 9007090012 | |
| Download: ML17348A372 (6) | |
Text
Docket Nos.
50-250 and 50-251 Mr. J.
H. Goldberg Executive Vice President Florida Power and Light Company P.O.
Box 14000 Juno Beach, Florida 33408-0420
Dear Mr. Goldberg:
July 5, 1990 DISTRIBUTION i DDDF.
NRC
& LPDRs PD22 Rdg File SVarga 14/E/4 GLainas 14/H/3 HBerkow GEdison DMiller OGC EJordan MNBB-3302 BGrimes 9/A/2 MWaterman 8/H/3 JJoyce 8/H/3 SNewberry 8/H/3 ACRS(10)
MSinkule RII
SUBJECT:
TURKEY POINT UNITS 3 AND 4 - REQUEST FOR ADDITIONAL INFORMATION ON EMERGENCY POWER SYSTEM ENHANCEMENT PROJECT (TAC NOS.
69023 AND 69024)
The purpose of this letter is to request additional information regarding the Emergency Power System (EPS)
Enhancement Project so that we can complete our review in a timely manner.
In your submittal dated June 23, 1988, as supplemented April 3, 1989 and June 4, 1990 you provided the EPS Enhancement Report to the NRC staff.
In order to complete our review of the report, the staff requires the additional information described in the enclosure.
The questions in the enclosure were discussed with Mr. M. Schoppman of your staff on June 29, 1990.
Please provide your response to the requests in the enclosure by July 23, 1990 so that the staff can complete its review in a timely manner.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Any questions concerning the enclosed comments should be directed to me.
Sincerely, Original signed by
Enclosure:
As stated PM: PDII-2 GEdison:jkd
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r Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation D:
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Mr. J.
H. Goldberg Florida Power and Light Company Turkey Point Plant CC:
Harold F. Reis, Esquire Newman and Holtzinger, P.C.
1615 L Street, N.M.
Washington, DC 20036 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. K. N. Harris, Yice President Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 County Manager of Metropolitan Dade County Ill NN 1st Street, 29th Floor Miami, Florida 33128 Senior Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear Regulatory Commission Post Office Box 57-1185
- Miami, F 1ori da 33257-1185 Mr. Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Minewood Blvd.
Tallahassee, Florida 32399-0700 Intergovernmental Coordination and Review Office of Planning
& Budget Executive Office of the Governor The Capitol Building Ta 1 1ahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.M. Suite 2900 Atlanta, Georgia 30323 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102
RE(VEST FOR ADDITIONAL INFORMATION TURKEY POINT UNITS 3 AND 4 EMERGENCY POWER ENHANCEMENT PROJECT Enclosure The following questions address the Load Sequencer (LS}, the Programmable Logic Controllers (PLCs) that comprise the LS, and implementation of this system in the Turkey Point Plant.
Refer ences:
1.
"Turkey Point Emergency Power System Enhancement Report (EPSER}, Supplement No.
1 - Testing," Florida Power
& Light Company Report JPN-PTN-SENJ-89-018, Revision 0, March 1989.
2.
ASNI/IEEE-ANS-7-4.3.2.-1982, "American National Standard, Application Criteria for Programmable Digital Computer Systems in Safety Systems of Nuclear Generating Stations."
3.
US NRC Regulatory Guide 1.152, Criteria for Programmable Digital Computer System Software in Safety-Related System of Nuclear Power Plants,"
November 1985.
questions:
Describe your plans for performing or reviewing the verification and validation (Y&V) of the Allen-Bradley PLCs. If the Y&V has been performed, provide the documentation of the Y&V results.
If there is no Y&Y, how will FPL assure the adequacy of the A-B PLCs for IE applications7 2.
Describe your plans for performing or reviewing the V&Y of the United Controls Inc. LS. If the Y&V has been performed, provide the documentation of the V&V results.
If there is no V&V, how will FPL assure the adequacy of the LS for 1E applicationsl 3.
Reference 1 implies the existence of a procedure for checking control cabinet instruments and logic.
Provide a discussion of the acceptance criteria addressed in this procedure.
4.
Reference I states the LS function wi 11 be tested "continuously".
Provide the frequency of this testing algorithm, and discuss coordination of testing with normal LS operations.
5.
Describe the methods by which a loss of'S function is detected and mitigated, to include the steps required to recover LS function.
For
- example, are watchdog timers included in the LS design7 6.
Provide the PLC Surge Mithstand Capability (SMC) specification, and justify the margin between the SMC and expected surges.
Describe the PLC power sources.
'L
7.
Provide the PLC Electromagnetic Interference (EHI) specification, and justify the margin between the EMI specification and expected EHI.
8.
NRC RG 1.152, which endorses Ref. 2, is not included in Section 8.0 of Ref. 1.
Provide documentation of the acceptance criteria for the LS
- system, and justify differences between the FPL acceptance criteria and the Ref.
2 criteria.
9.
Class 1E certification of the PLCs was not discussed in the FPL submittal.
Provide this certification.
10.
Describe FPL's configuration control after LS installation.
11.
Describe site acceptance/preoperational testing; specifically address loss and restoration of power to the PLCs during standby or operation.
Describe memory-retention capability.
12.
Are there any methods installed to manually bypass the PLC and load the EDGs'?
13.
Provide MTTF and MTTR documentation for the PLCs.
14.
Describe interfaces with non-1E systems (e,g., annunciators).
Discuss methods of isolating 1E systems from non-1E systems.
15.
Provide a description of the devices used in the LS (e.g.,
programming
- language, compiler, microprocessors, etc.).