ML20235J176
| ML20235J176 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/06/1989 |
| From: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| To: | William Cahill TEXAS UTILITIES CO. |
| Shared Package | |
| ML20235B074 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8902240200 | |
| Download: ML20235J176 (7) | |
Text
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. February 6. 1989 Docket Nos. 50-445 j
and 50-446
.Mr. W. J. Cahill, Jr.
f Executive Vice President, Nuclear l
Texas Utilities Electric Company 400 North Olive Street, L.B. 81 Dallas, Texas 75201
Dear Mr.'Cahill:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO FSAR s
CHAPTER 7 ISSUES AND REGULATORY. GUIDE 1.97, REVISION 2 The staff's review of Chapter 7 of the Comanche Peak FSAR, including compliance with Regulatory Guide 1.97, Revision 2, has resulted in a number of areas-for which additional information is needed as described in the
. enclosure.to this'1etter. Please provide the information identified by March 17, 1989.
Should you have any questions regarding(this request please contact either of our project managers, Mel Fields at 301)492-0765 or Melinda Malloy at (301)492-0738.
The reporting requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is not required under P. L.96-511.
Sincerely, (originalsignedby)
Christopher I. Grimes, Director-Comanche Peak Project Division Office of Nuclear Reactor Regulation i
Enclosure:
Request for Additional Information with attached Technical Evaluation Report cc: See next page
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I Dock'etLNos. 50-445 and 50-446 Mr. W. J. Cahill, Jr.
Executive Vice President, Nuclear.
Texas Utilities Electric Company 400 North Olive Street, L.B. 81 Dallas, Texas 75201
Dear Mr. Cahill:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION PERTAINING T0 FSAR CHAPTER 7 ISSUES AND REGULATORY GUIDE 1.97, REVISION 2.
The staff's review of _ Chapter 7 of the Comanche Peak FSAR, including compliance with Regulatory Guide 1.97, Revision 2, has resulted in a number of areas for which additional-information is needed as described in the enclosure to this letter.
Please provide the information identified by-
~
March 17. 1989..
Should you have any questions regarding this request please. contact either
- of. our. project managers, Mel Fields at (301)492-0765 or Melinda Malloy at (301)492-0738.
The reporting requirements contained in this letter affect fewer than ten respondents;'therefore OMB clearance is not required under P. L.96-511.
Sincerely, (original signed by)
Christopher 1. Grimes, Director Comanche Peak Project Division Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information with attached Technical Evaluation Report cc: See next page DISTRIBUTION Docket File JLyons SNewberry BMarcus NRC PDR RWarnick JNorberg R. Giardina Local PDR JHWilson EJordan ADSP Reading MMalloy BGrimes
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g February 6,1989 -
3; Docket Nos. 50-445 and 50-446 Mr'. W. J. Cahill', J r.
Executive Vice President, Nuclear
'j)'
' Texas Utilities Electric Company 400 North Olive Street, L.B. 81 Dallas, Texas 75201 t
Dear'Mr. Cahill:
j
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO FSAR CHAPTER 7 ISSUES AND REGULATORY GUIDE 1.97, REVISION 2 The staff's review of Chapter 7 of the Comanche Peak-FSAR, including compliance with Regulatory Guide 1.97, Revision 2, has resulted. in a number of areas: for which additional information~ is needed as described in the l
enclosure to this letter.
Please provide the information identified by-March 17, 1989.
this request please contact either Should you have any questions regarding(301)492-0765 or Melinda Malloy of our project managers,-Mel Fields at at'(301)492-0738.
The ~ reporting requirements contained in this letter affect fewer than ten respondents; therefore OMB clearance is not required under P. L.96-511.
Sincerely, VM Christopher I. Grimes, Director Comanche Peak Project Division Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information with attached Technical Evaluation Report cc:
See next page 1
l i
i r
sl W. J.-Cahill,'Jr.
Comanche Peak Steam Electric Station Texas Utilities Electric Company Units I and 2 cc:
Jack R. Newman Esq.
Asst. Director for Inspec. Programs Newman & Holtzinger, P.C.
Comanche Peak Project Division Suite 1000 U.S. Nuclear Regulatory Commission 1615 L Street, N.W.
P. O. Box 1029 1
Washington, D..C. 20036 Granbury, Texas 76048
' Robert A.. Wooloridge, Esq.
Regional Administrator, Region IV Worsham, Forsythe, Sampels &
U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive, Suite 1000 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011 Dallas, Texas 75201 Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute
.a Director of. Nuclear Services 1324 North Capitol Street Texas Utilities Electric Company Washington, D.C.
20002 Skyway Tower 400 North: Olive Street, L.B. 81 Ms. Billie Pirner Garde, Esq.
Dallas,-Texas 75201 Garde Law Office 104 East Wisconsin Avenue Mr. R. W. Ackley Appleton, Wisconsin 54911 Stone & Webster Comanche Peak Steam Electric Station David R. Pigott, Esq.
.P. O. Box 1002 Orrick, Herrington & Sutcliffe
! Glen Rose, Texas 76043 600 Montgomery Street San Francisco, California 94111 Mr. J. L. Vota Westinghouse Electric Corporation E. F. Ottney P. O. Box 355 P. O. Box 1777 Pittsburgh, Pennsylvania 15230 Glen Rose, Texas 76043 Susan M. Theisen George A. Parker, Chairman Assistant Attorney General Public Utility Committee Environmental Protection Division Senior Citizens Alliance of P. O. Box 12548, Capitol Station Tarrant County, Inc.
Austin, Texas 78711-1548 6048 Wonder Drive Fort Worth, Texas 76133 Mrs. Juanita Ellis, President Citizens Association for Sound Energy 1426 South Polk Dallas, Texas 75224 Ms. Nancy H. Williams CYGNA Energy Services 2121 N. California Blvd., Suite 390 Walnut Creek, CA 94596
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o W. J. Cahill,'Jr.
- 2;-
Comanche Peak Electric Station Texas Utilities Electric Company -
Units I and 2 cc:
' Joseph F. Fulbright
- Fulbright & Jaworski 1301 McKinney Street Houston, Texas 77010 Roger D._ Walker Manager, Nuclear Licensing Texas Utilities Electric Company Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Texas. Utilities Electric Company c/o Bethesda Licensing 3 Metro Center, Suite 610 Bethesda, Maryland 20814 William A. Burchette, Esq.
Counsel for Tex-La Electric Cooperative of Texas.
Heron, Burchette, Ruckert & Rothwell Suite 700
-1025 Thomas Jefferson Street, NW Washington, D.C.
20007 GDS ASSOCIATES, INC.
Suite 720-1850 Parkway Place Marietta, Georgia 30067-8237 l
.=
[
t ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION COMANCHE PEAK UNITS 1 AND 2 FSAR CHAPTER 7 ISSUES AND REGULATORY GUIDE 1.97, REVISION 2 1.
The attached report, prepared by INEL and reviewed by the staff, concludes that TU Electric has provided an explicit commitment on conformance to R. G.1.97, with the exception of those items which were identified by the:
applicant.
Further, it is concluded.that the applicant's justification for exceptions to R. G. 1.97 for some items is acceptable.
However, there are some items for which INEL could not conclude that adequate justification Please was provided and has identified those as unjustified exceptions.
respond to the unresolved issues as identified in the attached report and provide any other comments if this report includes any incorrect assumptions I
or reflects a commitment which you believe is beyond the intent of your previous response.
After further review of FSAR Section 7.2.1.1,2, the staff has identified an 2.
The FSAR overtemperature N-16 trip signal discussion apparent' discrepancy.
indicates the use of T-avg as an input variable for the required setpoint calculations.
However, the equation provided in the FSAR (Section 7.2.1.1.2.2.a) does not show T-avg to actually be included as part of the setpoint-develop-ment for this reactor trip.
Provide clarifying information to address this apparent discrepancy.
The information presented in the September 5,1985 letter (TXX-4546) in-3.
dicates that during a meeting held on October 11, 1984 between representatives of Texas Utilities, Westinghouse, and the NRC, it was agreed that the total Transit Time Flow Meter (TTFM) uncertainty shou'Id be increased to a certain value on a single loop basis.
The increase was deemed necessary by the staff to cover additional perceived uncertainties in the TTFM Azimuthal Velocity Profile which is one parameter in the overall uncertainty analysis.
This resulted in the application of an "NRC conservatism factor" for the TTFM uncertainty calculation.
From review of the September 5, 1985 letter, it is not clear that the "NRC conservatism factor" was appropriately in-corporated into the cold leg volumetric flow uncertainty calculations prior to statistically combining with the elbow tap uncertainty.
In this regard, provide clarifying information (step-by-step correlation) to describe how the required NRC conservatism value was factored into the reactor coolant system flow measurement uncertainty analysis for generation of the Comanche Peak Technical Specifications.
FSAR Section 7.3.2.2.8 indicates that control switches for ESF final actuators 4.
for pumps are of the spring-return-to-automatic type.
This FSAR section also indicates that when operating conditions necessitate, the operator can manually override the automatic operation of individual components.
Speci-fically, it is stated that the operator can stop a safety-related pump which has received an auto-start signal from the ESF sequencer by holding the control switch in the "stop" position.
After the sequencer has cycled, the pump will not restart when the operator releases the control switch.
- However,
(
-2 other information in this FSAR section indicates that the alternate operating mode is provided with permissives or operator lockouts that prevent the operator from intervening with the automatic operation of the final actuation device when the ESF sequencer is in operation.
The manual override control design feature noted above appears to allow the operator to prevent (through a single manual action) a required automatic safety action from going to completion subsequent to actual initiation of the protective function. This manual override of an auto-matic protective action before completion of the mitigative function could degrade the mitigation of a design basis event even though the initiating signals have not cleared.
In view of the above, provide a discussion which addresses each of the following:
Identify each ESF pump and associated system which a.
incorporates the manual override control design feature.
b.
Describe how the manual override control design feature has been factored into the emergency operating procedures for responding (operator action) to each postulated design basis event analyzed in FSAR Chapter 15.
Describe how the manual override control design feature c.
for pumps relates to permissives and operator lockouts that prevent the operator from intervening with automatic operation of the final actuation device.
Supplement this discussion with selected attendant electrical schematics for the final actuator circuitry.
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