ML18030A284
| ML18030A284 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/13/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-771, NUDOCS 8105190230 | |
| Download: ML18030A284 (7) | |
Text
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ACCESSION NUR:8105190230 DQC ~ DATE: 81/05/13 NOTARIZED:
NO FACIL:50 387 Susquehanna Steam Electric Station<
Unit 1< Pennsylva 50 3o8 Susquehanna Stedm Electric Station~
Unit 2i Pennsyl AUTH INANE AUTHUH Al FILIATION
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Pennsylvania Power Ir Light Cos REC IP ~ NANAK
'EC IPIh,N t AFFILIAT ION YOUNGBLOODrB.J ~
Licensing Branch 1
SUBJECT:
Forwards info which completes action re St.k Outstanaing Issues 93'5 a
100
>n response to thr ee TYII requir ementso Info repla'ces responses submitted in PLA 659.
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TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEr (215) 770-5151 NORMAN W. CURTIS Vice President-Engineering 8 Construction-Nuclear 770.538t May 13, 1981 Mr. B. J. Youngblood Licensing Project Branch 81 Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ISSUE NOS 93 r 95 r AND 100 ER 100450 'ILE 841-2, -12 PLA-771 DOCKET NOS.
50-387 AND 50-388 Dear'r.
Youngblood:
The attachments provide responses to three TMI requirements.
These responses should replace the temporary responses submitted in PLA-659.
These responses complete our action to close SER outstanding issues 93, 95 and 100.
Very truly yours, N. W. Curtis Vice President-Engineering
& Construction-Nuclear DPM/mks Attachment cc:
R.
M. Stark USNRC PENNSYLVANIA POWER 8
LIGHT COMPANY s losr&QII..eir~~
SER OUTSTANDING ISSUE 93 X.l.52.3 Statement of Res onse The BWR Owners'roup (BWROG) has performed an evaluation and developed'ecommendatj~ons to comply with this requirement.
These recommendations were transmitted by a letter from D. B. Waters to D. G. Eisenhut on March 31, 1981.
This evaluation shows that Crosby SRVs (as will be installed in Susquehanna) have a probability of sticking open which is approximately a factor of ten less than the three stage Target Rock valves.
It is our understanding that the goal of this require-ment is to reduce the probability of a stuck open SRV by a factor of 10 relative to the reference valve, which is the Target Rock valve.
Therefore we meet the intent of this requirement without modifications.
Implementation of the modification proposed by the BWROG will not significantly reduce this failure probability.
Therefore no modifications are necessary in response to this requirement.
SER OUTSTANDING ISSUE 95 K.1.54.3 Statement of Res onse The BWR Owners'roup has completed a generic feasibility study in response to this requirement.
The results were transmitted by a letter from D. B. Waters to D. G. Eisenhut on March 31, 1981.
PP&L has reviewed these results which are summarized below.
The intent of this requirement is to provide additional assurance of adequate core cooling.
(The current Susquehanna design provides several mechanisms to prevent inadequate core cooling.)
No significant increase in reliability can be gained by modifying ADS logic.
However, the reliability of operator performance under degraded plant conditions has been informally demonstrated to increase as= a result of implementing symptom-based emergency procedures and associated training.
Therefore, no ADS logic modifications will be made to Susquehanna.
Symptom-based emergency procedures will be implemented (as required by item I.C.1) and these will give the operator explicit guidance under degraded plant conditions.
The operators receive training on the emergency procedures (as part of their regular training) which provides an awareness and understanding of the plant response.
No additional action is necessary to meet this requirement.
SER OUTSTANDING ISSUE 100 X.1.63.3 Statement of Res onse The BWR Owners'roup (BWROG) has prepared a generic response to this requirement.
The report was transmitted to D.
G. Eisenhut by letter from D. B. Waters on December 29, 1980.
This response summarizes analyses performed to demonstrate the core remains c'overed during an anticipated transient in combination with the worst single failure.
Additionally, it concludes the core will remain covered with proper operator action during transients combined with the worst single failure and a stuck open safety/relief valve.
PPSL has reviewed this response and finds it is applicable to SSES.
Therefore, by reference to the BWROG report, PPSL meets this requirement.