ML17249A880
| ML17249A880 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/18/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-10, TASK-RR NUDOCS 8005070006 | |
| Download: ML17249A880 (10) | |
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APR i 8 1880 Docket No. 50-244 Nr. Leon D. Mhite, Jr.
Yice President Electric and.Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, Hew York 14649
Dear fear. White:
DISTR IBUTION Docket NRC PDR Local PDR ORB Reading NRR Reading DEisenhut RYollmer OELD OI&E (3)
DLZiemann JShea MSmith NSIC TERA gee'Cid
SUBJECT:
AUXILIARYFEEDlNTER SYSTEM REgUIRBtENTS (Ginna)
Ite are continuing our review of the Auxiliary Feedwater System and request your response to the comments contained in the enclosure tq this letter.
Your response is requested s>ithin 30 days of your receipt of th4s letter.
,Sincerely, "original Signad b7 ghomas V. Wambach" Dennis L. Ziemann, Chief Operating Reactors Branch P2 Division of Operating Reactors
Enclosure:
As stated cc M/enclosure:
See next page
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- U.S'VERNMENTPRINTING OFFICE:.1979.289-369
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Mr-Leon D. White, Jr.
.pri1 18, 1980 CC Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby E MacRae 1757 H Street, N.
W.
Washington, D.
C.
20036 Mr. Michael Slade
'2 Trailwood Circle Rochester, Hew York 14618 Rochester Comnittee for Scientif ic Information Robert E-Lee, Ph-D.
P.
O. Box 5236 River Can@us, Station Rochester, Hew York 14627 Jeffrey Cohen New York State Energy Of ice Swan Street Building Core 1, Second Floor Emp ire State P 1 az a
- Albany, New York 12223 Director, Technical Development Programs
- State of New York Enerog Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 R och es ter Pub 1 i c L i bra ry 115 South Avenue Rochester, New York 145'34 Supervisor of the Tcwn of Ontario 107 Ridge Road Mest
- Ortario, Hew York 1451g Dir ctor, Technical Assessment Division Office of Radiation Programs
{AW-450)
U-S. Environmental Protection Agency.
Crystal Mall 2
Arlington, Yirginia 20460 U. S. Environmental Protection Agency Region II Office ATi'N:
E IS COORD IHATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman At~ c Saf ety and Licensing Board U-S.
Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing. Board U. S. Nuclear Re'gulatory Cormission Washing.on, D.
C.
20555 Dr. Erm.th A-Luebke Ato~ic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washing on, D.
C.
20555 Mr. Tho.-.zs B. Cochran Natural Resources Defense Counci 1, I nc.
1725 I Street, N.
W.
Suite 600 Mashing. on, D.
C.
20006
Robert E. Ginna Nuclear Plant, Unit 1
Auxiliary Feedwater System Requirements X.4.3.1 Shoril Term Recommendations 1.
Recommendation GS-3 Your response to this recormendation is 'acceptable provided your response to Enclosure 2 of our letter dated October 22, 1979, adequately supports your conclusion that 200 gpm is sufficient to remove decay heat.
You should expedite your response to Enclosure 2.
2.
Recommendation Plant S ecific Your response to this recommendation is acceptable for the short term provided you implement interim emergency procedures for a complete loss of AC power that require an operator to be stationed at the turbine driven pump to monitor bearing oil temperatures and notify the control room if limits are exceeded.
This will allow for on-off operation of the pump to.pr event-excessive oil temperatures if necessary.
k 3.
Recommendation GS-6 a.
En your response to this recommendation it is not clear that the AR< align-ment checks following periodic tests or maintenance are performed twice by independent personnel.
Verify that the testing personnel perform the first alignment check and that the alignment check performed by the Opera-tions personnel is the second check
~
b.
Your response to this recommendation is acceptable.
- However, we widh to clarify that an extended cold shutdown should be considered for any refueling outage and any cold shutdown in excess of 30 days.
4.
Recommendation GS-7 Your response to this recomnendation is currently under review.
X.4.3.2 Additional Short Term Recommendations l.
Your response to this recommendation is acceptable provided the redun-dant indication and alarm circuitry you install-.have redun'dancy all the way from the detectors to the indicators including their power supplies.
They also should be powered by emergency busses with at least one ci rcuit backed by a battery source.
Yerify that your design will meet the above recommendations.
2.
Recommendation No.
2 Me have revised this recommendation such that a 48-hour test may be performed rather than the 72-hour test.
The attached revised Addi-tional Short Term Recommendation No.
2 should be used instead of the original.
Follow the provisions of the revised AFM pump'endurance test and submit the requested test information.
3.
Your response to this recommendation is currently being reviewed and evaluated by the Lessons Learned Implementation Task Force..
4.
This recommendation does not apply to the Ginna Nuclear Plant.
X.4.3.3 Lon Term Recommendations 1
~
Recommendation GL-3 Your response to this recommendation is acceptable.
Also see the plant specific short term recommendation No. 2.
2.
Recommendation Pl an S ecifi c Me will review and evaluate your response to this recommendation at a
later date.
3.
Recommendation GL-5 See short term recormendation GS-7.
4.
8 5:
These long term items will be reviewed as part of the Systematic Evalua-tion Program.
Revision to Pe~, en~ation Ho.
2 of "Additiona~ort Term deco;..-..enda t ions" Pe&ding Auxilia ry Feedwa ter Pump %durance Test The 1 ic nsee shoul d per form a n endurance tes t on al 1 AFW system pumps., The test should continue for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after achieving the following
'est condi t ions:
Pump/dr iver operating at rated speed Pump developing rated discharae pressure and flow or some higher pressure at a reduced flow but not exceeding the pump vendor '
maximum permi t ed di scha rge pr essure value for a 4S-hour t es For turbine drivers, steam temperature should be as close to nor-al operating steam temperature as practicabl e but in no case should the temp rature be less than 400'F.,
Foll owiflg the 48-hour pump run, the pumps should be shut down and all owed to cool down until pur p temperatures reduce to within 20'F of their val ues at the start o, the 48-hour test and at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. have elapsed.
Following the cool down, the pumps shoUld be restarted and run for one hour.
Test acceptance cr i.eri a should include demonstrating that the pumps rema in within des ion 1 imits wi th res pect to bearing/bearing oil tempera-tures and vibration and hat ambient pump room conditions (temperature, hut midi.y) do not exceed environmental qual ifi cation 1 imits for sa fety-rel a ted equi pment in the roor<<.
The licensee s houl d provide a
su~
., ary of the condi tions and resuI ts of the tes s.
Tne summary should incl ude the following:
1 )
A brief doser iption o
t he test ethod
( incl udi ng flow schematic diagram) and how the test
0 t
s instru-...en ed e
. i (i.e.,
~here and how be'r ng temperatures
~ere measured).
- 2) n discussion o, hog'he test conditions (pump flow, heaC, speed and e iperature) compare to desi on oper a=ing conCitions.
- 3) Plots o f bearing/bearing oil temperature vs. tim for each bearing o,
each AFM pump/driver demonstrating that tempera=ure design limits were not exceeded.
4)
A plot of pump room ambient temperature and humidity Ys.
time demonstrating that the pump room a-.bi nt conditions do not exceed environmental qualification limits for saf..y-reiat'ed equipnent in the room.
5)
A statement confirming tha.
~he pump vibration did. not exceed allowable limits during tests.
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