ML19332D891
| ML19332D891 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/30/1989 |
| From: | Trzyna G COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-***, TASK-OR 0422T, 422T, 442T, GL-89-21, NUDOCS 8912060007 | |
| Download: ML19332D891 (5) | |
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1 N Commonwealth Edison 4 -
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_- Address Reply to: Post Office Box 767 -
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- Chicago, lihnces 60690 0767
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Director of.' Nuclear Reactor Regulation U.S. Nuclear. Regulatory Commission Mail Station PI-137
'. Washington, DC 20555
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Subject:
_ Responses to Generic Letter 89-21 NRC Docket Nos. 50-295 and 50-304 s
Reference:
October 19, 1989 Letter from J.G. Pantlow
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to'All Holders of Operating Licenses D' ear Sir:
- Generic Letter 89-21 was-issued-as part of the NRC's continuing c
Leffort to validate staff understanding regardir.g the implementation of responses to Unreviewed Safety Issues (USI). 'One aspect of this effort is to
. ensure that the licensee and NRC personnel agree on,the status of USI re resolution implementation at-each facility.
This letter provides Commonwealth-Edison's response, in part,- to the USI's. However, some of these issues have required extensive research and the responses for those are not available at-this time.- Specifically,- the responses to VSI's A-'1,
-3, -12 and -43 are i
y still under review and will be provided later.
In a telephone conversation on B
November 29, 1989 between P. Shemanski (NRR) and G. Trzyna (CECO)', it was agreed that the submittal of the additional information for these open USI's
/
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could be rleferred until December 13 1989.
- The Attachment to this letter provides the status of the items in a table that completes Enclosure 1 of the Generic letter,
. Please direct any further questions that you may have regarding this
. 1ssue to this office.
Very truly yours,
) C. Y = A p G.E. Trzyna
. fL Nuclear Licensing Administrator cc: Senior Resident Inspector - Zion Chandu Patel - NRR 0422T hlA t
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8912060007 891130 PDR ADOCK 05000295 P
W ZION'CENERATING' STATION ATTACHMENT,
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-UNRESOLVED SAFETY ISSUES FOR WHICH A FINAL' TECHNICAL-RESOLUTION HAS BEEN ACH
-USI/MPA NUMBER TITLE REF. DOCUMENT
' APPLICABILITY STATUS /DATE*
REMARKS
)
A-1 Water Hansner SECY 84-119
-All NUREG-0927, Rev. I Response will.be provided-NUREG-0993 Rev. 1 by 12/13/89.
NUREG-0737> Item I.A.2.3 SRP revisions A-2/
Asymmetric R1owdown NUREG-0609-PWR
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MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Internal CECO review pre -
i Coolant Sys^ ems formed-in April, 1984
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verified that acceptable, A-3 Westinghouse Steam NUREG-0844 W-PWR leak detection equipment Generator Tube Integrity.
SECY 86-97 was installed & no response.
SECY 88-772 was necessary.
y GL 85-02 Re8Ponse will be provided:
(No requirements).
by 12/13/89.
A-4 CE Steam Generator Tube NUREG-0844, SECY 86 CE-PWR Integrity SECY-88-272 NA' GL 85-02
{
(No requirements)-
A-5 B8W Steam Generator NUREG-0844, SECY 86-97 B&W-PWR NA Tube Integrity SECY 88-272 GL 85-02 (No Requirements) i I
E
%-6 Mark I Containment NUREG-0408 Park I-8WR NA j
Short-Term Program l
C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I - INCOMPLETE E - EVALUATING ACTIONS REQUIRED
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33 ZION CENERATING STATION
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.. fF ATTACHMENT?
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~USI/MPA STATUS /DATE*
REMARKS NUMBER TITLE REF. DOCUMENT APPLICABILITY A-7/
Mark I long-Term-NUREG-0661 Mark I-BWR NA'
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D-01 Program NUREG-0661 Suppl. 1-GL 79-57 A-8 Mark II Containment-
- NUREG-0808 Mark II-BWR NA Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.10 GDC 16 September 8,11989 letter from'-
A-9 Anticipated Transients
- NUREG-0460, Vol. 4 All I
CECO to NRR transmitted Without Scram 10 CFR 50.62 implementation dates:
Spring 1990 - Unit:2 A-10/
BWR Feedwater Nozzle NUREG-0619 BWR NA -
Fall, 1990 - Unit l' MPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11
- December.20, 1985 letter from A-11 Reac+0r Vessel Paterial NUREG-0744, Rev. 1 All-CECO to ' RC advised that !50 f t-:
N E
Toughness 10 CFR 50.60/
lb date will be 1994.. ' This 82-26 date could change as'new specimens are withdrawn.
A-12 Fracture Toughness of NUREG-0577, Rev. 1 PWP
- November 13, 1989 letter from.-
Steam Generator and SRP Revision CECO to NRR transmitted recent:
Reactor Coolant Pump 5.3.4 Unit 2 speciman data.:
uppo M l
Response.will.be provided by 12/i3/89.
A-17 Systeme Interactions Ltr:
DeYoung to All
.1 licensees - 9/72-station response was trasmitted:
NUREG-1174, NUREG-in IPE response'to GL88-20 1229, NUREG/CR-3922, on October 27, 1989.
NUREG/CRJ761, NUPEG/
CR-4470s GL 89-18 (No requirements)
C-November 21, 1984 letter from-A-24/
Oualification of Class NUREG-0588, Rev. 1
- All NRC to CECO trans:nitted SER MPA B-60 IE Safety-Related SRP 3.11 First Regional inspection of Equipment 10 CFR.50.49-program in January 1985.
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ZION" GENERATING STATION-x ATTACHMENT' USI/MPA I
NUMBER TITI.E REF. DOCUMENT'
" APPLICABILITY STATUS /DATE*'
REMARKS:
A-26/
Reactor Vessel Pressure DOR Letters to-PWR C
Tech. Specs.were. implemented;.
_ Licensees 8/761 on. April 28, 1980. ~ They were,
.NUREG-0224 recently revised by Amendment.
MUREG-0371 No. 110/99.
SRP-5.2 GL 88-11 A-31 Residual Heat Removal NUREG-0606 A11:0Ls After NA i
i Shutdown Requirements RG 1.113, 01/79.
-NUREG-0612 All c 2 C
9 CEC tran i ti C-10, Near Spent Fuel SRP 9.1.5 SER. ' Phase.I provided C-15 GL 81-07, GL:83-42,
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suf ficient protection froin GL 5-1 4
dropped loads.
Eisenhut dated 12/22/80 A-39 Determination of SRY IlHREG-0802 BWR NA Pool Dynamic loads NUREGs-0763,0783,0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C A-40 Seismic Design SRP Revisions, NUREG/
All NA Addressed in accordance with Criteria CR-4776, NUREG/CR-0054, response to USI-A-46.
NUREG/CR-3480, NURES/
CR-1582; NUREG/CR-1161, NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/
Pipe Cracks in Boiling NUREG-0313, Rev.-1 BWR NA MPA 8-05 Water Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01.-
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- 1 ZION GENERATING STATION
.. ATTACHMENT-sw USI/MPA
. J
' NUMBER TITLE' REF.' DOCUMENT-APPLICABILITY STATUS /DATE*
-REMARKS u.
A-43 Containment Emergency
'All
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Response will be providedj Sump Performance NUREG-0869, Rev. 1 by 12/13/89.
NUREG-0897,'R.G.I.82 (Rev. 0), SRP 6.2.2 GL 85-22 No Requirements ~
~
A-44 Station Blackout RG'1.155 All E
. Review of proposed modifica-NilREG-1032
' tion is scheduled to be NUREG-1109 completed by June, 1990..
^
A-45 Shutdown Decay Heat SECY'R8-260 All L. E Letter submitted to NRC~on
Removal Requirements NUREG-1289 October.27, 1989 in' response to IPEGL88-20.
NUREG/CR-5230; SECY 88-260 (No requirements)
E Generic Safety Evaluation' A-46 Seismic Qualification NUREG-10?O All of Equipment in NUREG-1211/
was issued on July'29, 1988.
Operating Plants GL 87-02, GL 87-03 Several plant walkdowns.
are pending'through 1992.
A-47 Safety Implication NUREG-1217, NUREG-All E
' Response due to NRC by.
of Control Systems 1218 March, 1990.
GL'89-19 A-48 flydrogen Control 10 CFR 50.44 All, except
.NA Measures and Effects SECY 89-172 PWRs with.
of Hydrogen Burns large dry.
on Safety Equipment containments A-49 Pressurized Thermal PGs 1.154, 1.99
'PWR E-
'Sevegalleg$belongsNoaters
$$$we*nCEC chock SECY 82-465 SECY P.3-288 B&W - Owner's Group which-SECY 81-687.
.has been established to 10 CFR 50.61/
address the' issue scheduled GL 88-11 to update NRR in February, 1990.