ML18030A286
| ML18030A286 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/15/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-780, NUDOCS 8105190273 | |
| Download: ML18030A286 (4) | |
Text
V;pr'EGULATO 1Nf-ORNAT ION DISTR I BU T ION TEN (R IDS)
ACCESSION Ni3R:8105190275 DOC.DATE: 81/05/15 NOl'ARIZED:
NO DOCKET FACIL:50-387 Susquehanna Steam Electric Station>
Unit 1< Pennsylva 0500 50 388 Susquehanna Steam Electric Stationi Unit 2< Pennsylva 00 d8 AUTH'Ai4lE AUTHOR Af-'FiLIATION CURTISrN.nr.
Pennsylvania Power 8 Light Co ~
RE C I P ~ N ArlE RECIPIENT AFFILIATION YOUNGBLOODiB~ J ~
Licensing Branch 1
SUBJECT:
Responds to SER Outstanaing Item 79 'est simulating loss of ac power condition for reactor 8 containment sys will be Performed'est may cause certain conditions inconsistent w/NHC requir ements
~ Commitment closes open item.
DISTRIBUTI N
CODE:
8001S COPIES RECEIVED:LTR ENCL SIZE:
TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES;Send ICE 3 copies FSAR It al 1
amends
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Send ICE 3 copies FSAR 8 al 1
amends.
1 cy:Br R LRG PH(L ~ RIB) 050003d7 05000388 ACTION:
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ACr05190 g,7$
PENNSYLVANIA POWER IL LIGHT COMPANY
Mr. B. J ~ Youngblood Page 2
(c)
Loss of power to plant instrumentation will not be simulated.
To accomplish the major goal of this test, instrumentation will be maintained functional for proper data collection.
This constraint is also considered necessary to insure plant safety.
Training of licensed operators in response to the loss of all station AC condition will be provided at PPGL's plant specific simulator.
This will provide the opportunity to experience the instrumentation blackout condition without placing the plant in jeopardy.
(d)
Plant AC busses will remain energized, the emergency diesel generators will be available 'or operating, and breakers to safeguards equipment will not be racked out.
These precautions are considered necessary for plant safety.
(e)
Test termination criteria will be established for parameters such as reactor vessel temperature limits, containment pressure and temperature, reactor vessel level, suppression pool temperatue, HPCI and RCIC room temperatures, and CRD temperatures.
The test will be conducted at a convenient point during the first fuel cycle, with the constraint that adequate decay heat exists to provide a valid test.
Several options are being explored for test initiation (e.g. turbine trip from 5% power following load reduction, turbine trip from 85% power, etc.)
It is our position that the method finally selected will have little bearing on the test, since plant performance during the initial state of such transients is adequately tested in startup tests.
The commitments previously made in response to Item I.G.l for additional testing and training will be fulfilled, as it is felt that valuable input will be obtained for the loss of AC power test.
The test may cause certain conditions which are inconsistent with NRC requirements.
We therefore will provide NRC with the test plan and pertinent documents for review and approval.
Performance of this test is contingent upon a favorable safety evaluation and obtaining appropriate commission approvals.
Since the NRC has indicated that they may not require a test at SSES if results from a test at another plant resolve their concerns, PPGL's commitment is contingent on a continuing NRC requirement for this test.
Very truly yours, N.
W. Curtis Vice President-Engineering 6 Construction-Nuclear DPM/mks cc:
R.
M. Stark