ML20216K118
| ML20216K118 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/07/1990 |
| From: | Long R GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20216K121 | List: |
| References | |
| 4410-90-L-0078, 4410-90-L-78, C-90-1126, C000-90-1126, NUDOCS 9011200061 | |
| Download: ML20216K118 (2) | |
Text
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GPU Nuclear Corporation f
Nuclear
=,o m a r ao Middletown, Pennsylvania 17057 0191 l
717 944 7621 i
TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8400 g
November 7, 1990 4410-90-L-0078 C000-90-1126 y
US Nuclear Regulatory Commission
-Washington, DC 20555 Attention: Document Control Desk
~
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating _ Licen se No. DPR-73.
Docket No 50-320 in
- Post-Defue1 % ;.Menitored-Storage Safety Analys's Report Amendment 9
Dear Sirs:
Attached is Amendment 9 to the Post-Defueling Monitored Storage-(PCMS) t Safety Analysis Report (SAR).
This amendment-(1) incorporates the results E
of the Defueling Completion Report (DCR) as augmented by GPU Nuclear D
. letter 4410-90-L-0026, "Results of. Post-Lower Head Sampling Program Cleanup",
. dated April 12.-1990, (2)l responds to the NRC questions dated August 6,.
1990, and (3)' reflects,an overall review of the PDMS SAR based on current l;
conditions.
q L.,
In accordance with,the data provided in the-DCR and the GPU Nuclear letter
,0
. mentioned -above, the -residual-fuel values contained in SAR Chapter 4
't Twere updated with a> resultantJimpact on the SAR Chapter 8 routine and unanticipated' release analyses. The results of the updated analyses B
are included.
In addition, the SAR Chapter 9 Technical Specifications-were expanded-to include.the NRC-imposed 93 kg Safe. Fuel Mass Limit (SFML).
for the Reactor Vessel.
The -description' of the Special Nuclear Material (SNM) Accountability ' Program was also revised to reflect the' actual' methods
.being used for the final SNM accounting.
f The. decontamination' goals. for the Reactor, Auxiliary, and Fuel Handling
-Buildings.were revised based on updated information concerning radiological g
conditions. -In.some cases,.the existing conditions are reflected rather than-a future goal.
Further decontamination / cleanup in these areas is i
to be evaluated on.a caseby case basis.
In addition, internal contamination-was noted in~a~few facilities and systems where none-was previously expected.
9011200061 901107 PDR ADOCK 05000320 s
P PDC
@\\
GPU Nuclear Corporation Is a subsidiary of the General Public Utilities Corporation
C o
6.
Document Control Desk i
4410-90-L-0078
{
C000-90-1126 i
Page Two Various changes were made to the GPU Nuclear Corporate Organization contained in SAR Section 10.5 to reflect the latest organization plan.
Subsequent alterations to this section are expected before entry into PDMS although none are currently planned.- Finally, the responsibilities of the Independent Onsite Safety Review Group (IOSRG) were defined in the SAR Chapter 9 Technical Specifications.
l Notwithstanding this extensive revision to the SAR text, the conclusion i
that TMI-2 can be placed in a safe, stable configuration remains unchanged.
l Further, the calculated dose to the maximally exposed individual for routine releases = remains a small fraction of the 10CFR50 Appendix I limits i
and, for the maximum unanticipated release, the calculated dose remains j
less than the Appendix I limit which is the TMI-2 administrative limit for PDMS.
Sincerely, R. L. Long Director, Corporate Services /
l Director, TMI-2
. EDS/kms cc:
T. T. Martin - Regional Administrator, Region I.
M. T. Masnik - Project Manager, TMI-2,.PDNP Directorate L.-H. Thonus - Project Manager, TMI Site F. I. Young - Senior Resident Inspector, TMI I
I
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