ML20062G547
| ML20062G547 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/26/1990 |
| From: | Clifford J Office of Nuclear Reactor Regulation |
| To: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| REF-GTECI-A-35, REF-GTECI-EL, TASK-A-35, TASK-OR GL-90-04, GL-90-4, NUDOCS 9011290311 | |
| Download: ML20062G547 (4) | |
Text
. _ _. - _
Novenber 26, 1990 l
Docket Nos. 50-445
-DISTRIBUTION and 50-446.
<553EETUe7
-JC11fford a
.NRC & Local.PDRs OGC Mr. William J. Cchill, Jr.
BBoger.
EJordan Executive Vice President, Nuclear MVirgilio
'ACRS(10)
-l TU Electric Company Elmbro DChamberlain-400 North Olive Street, L.B. 81 EPevton RScholl Dallas, Texas 75201 PDIV.2 Reading.
.DM111er.
Dear Mr. Cahill:
SUBJECT:
UNIMPLEMENTED GENERIC SAFETY ISSUES AT COMANCHE PEAK STEAM ELECTRIC STATION.-UNITS 1 AND 2 On April 25, 1990, the= NRC. staff issued Generic Letter (GL) 90 04 which requested information concerning the implementation status of designated.
1 generic' safety issues (GSIs) at your facility.= Based on your response;to this l
GL, dated June 26, 1990- our own records, and discussions with yours staff, we-have updated our data base on GSI implementationistatus. The results of this effort were presented to the Comission at a meeting on October 25, 1990.'
The enclosure to this letter sumarizes'the NRC staff's understanding of the current status d those GSIs that remain unimplemented at Comanche Peak, Units 1 and 2.. We appreciate the assistance-that you provided in responding-to GL'90 04.
We also encourage your timely completion of the GSIs listed in the enclosure for L
Unit 1. 'We understand that 111'the generic issues outstanding.for Unit 2 will beimplementedpriortofuelload,withtheexceptionofGSIA-35(MPAB023),-
Adequat.y of Offsite Power Systems, as discussed in the enclosure, l
Please contact me at (301) 492-1323 if you have any questions or comments about the enclosed information.
Sincerely, (ORIGIR'.L SIGNED BY).
' James W. Clifford, Project Manager Project Directorate IV.2 Division of Reactor Projects III/IV/V-Office of Nuclear Reactor ' Regulation-
Enclosure:
y As stated cc w/ enclosure:
.See next page t,v. b d 0FC.
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0FFICIAL RECORD COPY
~ Document'Name: CP1 GSI CLOSEOUT LETTER 9011290311 901126 Q f0l y
PDR ADOCK 03000445 P
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' Mr. William J. Cahill, Jr. *
(
cc:
Senior Resident Inspector Jack R. Newman Esq U.S. Nuclear Regulatory Commission Newman&HoltzInger.-
c P. O. Box 1029 1615 L Street, N.W.
i Granbury, Texas: 76048 Suite 1000 Washington, D.C.
20036 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Chief, Texas Bureau of Radiation Control 611 Ryan Plaza Drive, Suite 1000 Texas Department of Health Arlington, Texas 76011
-1100 West:49th Street-Austin, Texas 78756 Ms. Billie Pirner Garde, Esq.
Robinson, Robinson, et al Honorable George Crump l'13 East College Avenue County Judge-AFpleton, r!isconsin 54911 Glen Rose, Texas.-76043 Mrs. Juanita'Ellis, President Citizens Association for Sound Energy-1426 South Polk Dallas, Texas ~75224 E. F. Ottney P. O. Box 1777 Glen Rose, Texas 76043 l
Mr. Roger D. Walker Manager, Nuclear Licensing
(
Texas Utilities Electric Company 400 North 0 live Street, L.B. 81=
Dallas, Texas 75201 t
Texas-Utilities Electric Company c/o Bethesda Licensing 3 Metro Center, Suite 610 Bethesda, Maryland 20814 l
William A. Burchette,' Esq.
Counsel for Tex-La Electric i
Cooperative of Texas Heron,'Burchette, Ruckert & Rothwell' 1025 Thomas Jefferson Street N.W.
Washington, D.C.
20007 GDS Associates, Inc.
Suite 720 1850 Parkway Place-Marietta.: Georgia 30067-8237 9
.~.
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Enclosure STATUS OF UNIMPLEMENTED GENERIC SAFETY ISSUES.
COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 1
)
PROJECTEDL IMPLEMENTATION GSI(MPANo.) TITLE DATE REMARKS 43 (B107)
Reliability. of Air (U2)1/93 Systems 51(L913)
Improving the Reliability (U2) 1/93 of Open-cycle Service Water Systems, 67.3.3(A017) Improved Accident (U2)1/93 Monitoring 75 (B086)
Item 2.2.1 - Equipment (U2)1/93 i
Classification for a
Safety-related Components 3
75(LOO 3)
Item 2.2.2 Vendor-(U1) 12/90
- 1. Will be closed' Interface for Safety-(U2)12/90=
Related Components
.when completed response to GL 90-03 submitted by-12/3/90.
- 2. Status different than 6/26/90 letter.
3 75(8078)
Items 3.1.1 & 3.1.2 -
(U2)1/93 Post-Maintenance Testing-(ReactorTri Components) p System 75(8079)
Item 3.1.3'- Post-(U2)1/93 Maintenance Testing-Changes to Test L
Requirements (Reactor.
. Trip System Components) h 75(8087)
Item 3.2.1 & 3.2.2
^
(U2)1/93:
l Post-Maintenance Testing (All Other Safety-Related. Components)-
75(B080)'
Item 4.1.~- Reactor Trip-(U2)1/93
.(ystem Reliability j
S Vendor-relatea j
l-Modifications) 91-
+-
m m
w - - --
me
.y 3
5 2-l SiATUS OF UNIMPLEMENTED GENERIC SAFETY ISSUES 4
PROJECTED-IMPLEMENTATION 1
GSI(MPANo.) TITLE DATE-REMARKS
)
75(8093).
Items 4.5.2 & 4.5.2 -
(U2)1/93 Reactor Trip System
]
Reliability-Test j
Alternatives and Intervals (System-FunctionalTesting) 93 (B098)
Steam Binding of Aux-'
(U2) 1/93 -
111ary Feedwater Pumps 99(L817)
RCS/RHR Suction Line (U1) 7/91~-
To be completed' Valve Interlock on-(U2) 1/93 on-Unit 1 prior PWRs to entry,into the -
-first reduced-1 inventory con-
' I ditions (Mid-loop operation)
A-13(B017)
Snubber Operability (U2)1/93 Assurance - Hydraulic Snubbers A-13(8022)
Snubber' Operability (U2)1/93 Assurance - Mechanical Snuhbers A-35(B023)
Adequacy of Offsite Power (U2)6/93(est)
_ Complete after Systems voltage measure-ments taken prior _ to :
-initial full power operation B-63(B045)
Isolation of Low.
(U2) 1/93 Pressure Systems Connected to the Reactor Coolant System Pressure Boundary i
o i
ag
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e m-s.,