ML20246E631
| ML20246E631 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/07/1989 |
| From: | Malloy M Office of Nuclear Reactor Regulation |
| To: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8907120326 | |
| Download: ML20246E631 (7) | |
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Docket No. 50-445 MEMORANDUM FOR: Christopher I. Grimes Director Comanche Peak Project Division Office of Nuclear Reactor Regulation
@forProjects THRU:
s H. Wilson, Assistant Director r
' Comanche Peak Project Division Office of Nuclear Reactor Regulation FRON:
Melinda Malloy, Project Manager Comanche Peak Project Division Office of Nuclear Reactor Regulation
SUBJECT:
FORTHCOMING MEETING
- WITH TU ELECTRIC REGARDING THE COMANCHE PEAK STEAM ELECTRIC STATION De.te & Time:
Wednesday, July 12, 198f 1:00 pm - 5:00 pm Location:
One White Flint North 11555 Rockville Pike Rockville MD 20852 Room 14B-13
Purpose:
To discuss Comanche Peak Unit 1 Technical Specifications (see attached agenda)
Participants *:
NRC TU Electric i
F H. Wilson F. Allenspach J. Kelly M. Malloy L. Kopp R. Walker R. Each W. LeFaye J. Seawright R. Giardina C. Li N. Hood, et al F. Ashe If nda Malloy, Project Ma r
Comanche Peak Project Divi n
Office of Nuclear Reactor Regulation
Enclosure:
Proposed agenda cc: See next page CONTACTS:
M. Malloy (301)492-0738 or M. Fields (301)492-0765
- Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, interveners, or other parties to attend as observers pursuant to "Open Meetings and Statement of NRC Staff Policy " 43 Federal Register 28058, 6/28/78.
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8907120326 890707 DR ADOCK 05000445 PDC-
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Asst. Director for Inspec. Programs Joseph F. Fulbright Comanche Peak Project Division fulbright & Jaworski U.S. Nuclear Regulatory Connission 1301 McKinney Street P. O. Box 1029 Houston, Texas 77010 Granbury, Texas 76048 Roger D. Walker Regional Administrator, Region IV Manager, Nuclear Licensing U.S. Nuclear Regulatory Commission Texas Utilities Electric Company 611 Ryan Plaza Drive, Suite 1000 Skyway Tower Arlington, Texas 76011 400 North Olive Street, L.B. 81 Dallas, Texas 75201 Lanny A. Sinkin Christic Institute Texas Utilities Electric Company 1324 North Capitol Street c/o Bethesda Licensing Washington, D.C.
20002 3 Metro Center, Suite 610 Bethesda, Maryland 20814 Ms. Billie Pirner Garde. Esq.
Garde Law Office William A. Burchette. Esq.
104 East Wisconsin Avenue Counsel for Tex-La Electric Cooperative Appleton,' Wisconsin 54911 of Texas Heron, Burchette, Ruckert & Rothwell Susan M. Theisen 1025 Thomas Jefferson Street, NW Assistant Attorney General Washington, D.C.
20007 Environmental Protection Division P. O. Box 12548, Capitol Station GOS ASSOCIATES, INC.
Austin, Texas 78711-1548 Suite 720 1850 Parkway Place Mrs. Juanita Ellis, President Marietta, Georgia 30067-8237 Citizens Association for Sound Energy 1426 South Polk Jack R. Newman Dallas, Texas 75224 Newman & Holtzinger 1615 L Street, NW E. F. Ottney Suite 1000 P. 3. Box 1777 Washington, DC 20036 Glen Rose, Texas 76043 George A. Parker, Chainnan Public Utility Comittee Senior Citizens Alliance of l
Tarrant County, Inc.
6048 Wonder Drive Fort Worth. Texas 76133 l
Mr. W. J. Cahill, Jr.
Executive Vice President. Nuclear Texas Utilities Electric Company 400 No. Olive Street, L.B. 81 Dallas, Texas 75201
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PROPOSED AGENDA FOR NRC/TU ELECTRIC MEETING ON COMANCHE PEAX UNIT 1 TECHNICAL SPECIFICATIONS (TS)
July 12, 1989 1:00 pm - 1:15 pa 1.
Introductions and Opening Remarks 1:15 pm - 2:15 pm 2.
Discussion of several corrections to Unit 1 TS proposed in Attachment 2 of TXX-89169 dated March 14, 1989.
Page/TS Section Staff Position a.
if/Index The' proposal to delete the definition of-1-6/ Definitions
" SOURCE CHECK" is inconsistent with the application of Generic Letter 89-01 to the Unit 1 TS.
b.
3/4 3-11 This proposed change was.previously RTS Instrumentation table discussed as TS change'ID #0123 and notations TU Electric was advised that the staff-consideredittobegeneric(i.e.,ap-plicabletoany4-loopWestinghouseunit).
The staff does not consider this change to be safety significant; therefore, it will not be considered further at this time due to resource constraints.
c.
3/4 3-19 The staff agrees with the proposed changes.
ESF Actuation System except for the ACTION required. The staff Instrumentation table believes ACTION 23 is more appropriate.
d.
3/4 3-19 & 3-22 The staff disagrees with the proposed-ESF Actuation System changes because the addition of Note g would Instrumentation table allow less conservative actions to be and notations taken than presently allowed by Specifi-cation 3.3.2.
e.
3/4 10-5 The proposed changes are considered to Position Indication System-be generic (i.e., applicable'to any Shutdown 4-loop Westinghouse unit).
The staff j
does not consider this change to be safety significant; therefore, it will not be considered further at this time due to resource constraints.
f.
B 3/4 6-1 Bases The correction of maximum allowed leakage Bases 3/4.6.1.2, limits for four of the valves is acceptable.
Containment Leakage The other proposed changes are unacceptable because (1) the change does not clarify that water test is an acceptable alternative to air testing and (2) 10 CFR 50 Appendix J does not allow for combined leakage on isolation valves in parallel.
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PROPOSED AGENDA FOR JULY 12. 1989 i 2. continued-Page/TS Section Staff Position g.
B 3/4 6-3 The proposed changes constitute an-Bases 3/4.6.3, interpretation of the bases which the Containment Isolation staff feels is unnecessary.
i/alves h.
6-4 Changes proposed are unacceptable 6.2.3, ISEG because the Standard TS requires a high-level corporate official which is not reflected in the technical interfaces position.
1.
6-7 The changes proposed are generic in 6.5.1.6o, SORC nature and the staff prefers to retain Responsibilities the wording.of Generic Letter 88-12.
- j. 6-12 The changes proposed are unacceptable.
6.5.3.lc, Technical An exact title is needed to conform Reviews and Controls with the rest of TS Section 6.0.
2:15 pm --2:45 pm 3.
Discussion of two: items from the NRC's independent review of the Final' Draft Unit 1 TS.
Page/TS Section Staff Position a.
None(missing)
SER 5ection 15.T.3.1 (Boron Dilution Events) states that in cold shutdown, the dilution rate is limited to a possible maximum of 10 ppm / min, which corresponds to an unborated primary water flow rate of 150 gpm.
The SER also states that this restriction is administrative 1y car-ried out and is to be implemented in ;te TS.
The Unit 1 TS have no specification covering this SER item. The staff was advised that the flow is limited by design (i.e.,
fixed orifices). The staff has requested TU Electric to advise as to where in the FSAR this design feature is documented.
b.
3/4 6-11 The staff has revised Surveillance 3/4.6.2, Containment 4.6.2.1.c.2 by changing "or" to "and."
As Spray System - Depres-previously written, the surveillance re-surization and Cooling quired spray pump start on only one or System the other (not both) the Containment Spray Actuation test signal and the Safety In-jection test signal, whereas the FSAR indicates that the spray pump starts automatically on each signal. The change brings the TS into conformance with the FSAR.
4 PROPOSED AGENDA FOR JULY 12, 1989 2:45 pm - 3:00 pm 4.
Discussion of staff questions on corrections to Unit 1 TS relating to accident monitoring instru-mentation proposed in Attachment of TXX-89243 dated May 15, 1989.
Page/TS Section Clarifications / Confirmations Needed a.
3/4 3-45 For items 2 and 3 in Table 3.3-6, pro-Accident Monitoring vide the bases for including the Instrumentation table information contained in ACTION 30, item c.
b.
3/4 3-45 Describe the instrumentation for Accident Monitoring auxiliary feedwater flow and Instrumentation table confirm whether the wording under
" Minimum Channels Operable" should be "I each/ Steam Generator" instead of "1/ steam generator."
c.
3/4 3-45 For item 10, explain why " Required Accident Monitoring Number of Channels" is proposed to be Instrumentation tab?e changed from "2" to "N/A."
3:00 pm - 3:45 pm 5.
Discussion of staff questions on responses to staff's request for additional information provided in TXX-89233 dated May 13, 1989 relating to accident monitoring instrumentation.
a.
2-4 thru 2-8 and The response to Question 1 indicates 3/4 3-25 thru 30 that a Westinghouse functional require-l Reactor Trip System ment specifies the range of the turbine l
Instrumentation Trip inlet pressure channels as the equivalent j
Setpoints table and of 0-120% of turbine load. Explain the l
Reactor Trip System technical bases for this requirement.
I Instrumentation table l
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PROPOSED AGENDA FOR JULY 12, 1989 j '
Clarifications / Confirmations Needed
'b.
None The response to question 7 indicates one result of the 1984 Setpoint Study was that the limiting event for the Steam Generator Water Level - low-low 1
setpoint value was the postulated loss of normal feedwater event. More.
recently, postulated events were reanalyzed using revised safety limits.
Further, instrument uncertainties associated with measuring and test equipment have been included in the revised instrument setpoint values.
Given the above, confirm that the postulated loss of normal feedwater event continues to be the limiting event with regard to the Steam Generator Water Level - low-low trip setpoint value.
In addition, identify the specific plant modifications which partially contributed to the total uncertainty for the main feedline break event increasing from approximately 18%
in the 1984 Setpoint Study to 26% in the current Setpoint Study.
3:45 pm - 4:15 pm 6.
Other Topics (as necessary) 4:15 pm - 4:45 pm 7.
Staff Caucus (if necessary)
-4:45 pm - 5:00 pm 8.
Sumary and Closing Remarks
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