ML20127H496
| ML20127H496 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 01/16/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Belair R KIRKPATRICK & LOCKHART |
| Shared Package | |
| ML20127H500 | List: |
| References | |
| FOIA-84-942 CLI-84-08, CLI-84-8, NUDOCS 8505210312 | |
| Download: ML20127H496 (2) | |
Text
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UNITED STATES
[
/3 -
WASHING TON. D. C. 20555 NUCLEAR REGULATORY COMMISSION g
-j
-g
/
W 16 BBS
....+
Robert'R. Belair, Esquire
-Kirkpatrick and Lockhart
.1900 M Street,-NW IN RESPONSE REFER Washington, DC -20036 TO F01A-84-942
Dear Mr. Belair:
This is in partial response to your letter. dated December 21, 1984, in which you requested, pursuant to the Freedom _of Information Act (F0IA), copies of
. documents.related to the issues discussed in the May 16, 1984, Comission order
[
-(CLI-84-8) in the Shoreham proceeding.
The documents listed on enclosed Appendix A are responsive to your request.
Documents 2, 3, 5, 7 and 8 are being placed in the NRC Public Document Roorr t
located at 1717 H Street, NW, Washington, DC 20555 in folder-~FOIA-84-942 in
.your nane.. Documents'1, 4, and 6 are already in the PDR.~The accession number is indicated beside the document description for.each'of those three documents.
Documents subject to your request have been addressed in previous F0IA recuests and are maintained in the following folders in the PDR:
F01A-84-445, Lane; F01A-84-659, Bell; and F01A-84-798, Graber.
'The search for and review of documents related to'your request is cortinuing.
- As.soon as the search and review is completed, we will notify you.
Sin [erely k M. Felton, Director Division of Rules and Records Office of Administration
Enclosure:
As stated 8505210312 850116 PDR FOIA BELAIR84-942 PDR L_
F01A-84-942 Appendix A Ir 07/03/84 Letter from J. D. Leonard to H. R. Denton re: Emergency Diesel sJ Generator Loading - Shoreham Nuclear Power Station - Unit 1 (11
's pages) Acc #8407120096 PDR AD0CK 05000322 2.
07/24/84 Memo from A. Schwencer to M. Srinivasan re: Revised Diesel Generator Loading'at Shoreham (9 pages) 3.
07/27/84 Memo from A. Schwencer to 0. Parr re: Revised Diesel Generator Loading at'Shoreham (10 pages) 4.
09/11/84 Letter from J. D. Leonard to H. R. Denton re: TDI Diesel Generators - Shoreham Nuclear Power Station, Unit 1 (8 pages) Acc
- 8409130374 PDR ADOCK 05000322 5.
09/12/84 Memo from G. W. McCorkle to C. O. Thomas re: Shoreham Nuclear Plant Revised Safeguards SEP Statement (a pages) 1 s
6.
10/01/84 Letter from J. D. Leonard to H. R. Denton re: Shoreham Technical Specifications - Shoreham Nuclear Power Station, Unit 1. (9 pages) Acc A8410040426 PDR ADOCK 05000322 7.
10/10/84 Men.o from M. Srinivasan to various re: Shoreham Proposed FSAP Revision Diesel Generater Loading (11 pages) 8.
10/12/84 Memo from 0. Parr to M. Srinivasan re: Manual Initiation of Selected Pumps - Shoreham Nuclear Power Station (2 pages) b l--
c I
l
s y
3
/7 /gg*O LONG. ISLAND LIGHTING COM PANY SHOREHAM NUCLEAR POWER STATION P.O. Box eis, NORTM COUNTRY RO AD. WADING RIVER. N.Y.11792 JOHN D. LEONARD.JR.
s vict PassiDEset esuchtAR OrtRAN0'es July 3, 1984 SNRC-1065 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclt.ar Regulatory Commission Washington, D.C.
20555 t
Emergency Diesel Generator Loading Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 j
3'
Dear Mr. Denton:
The purpose of this letter is to provide you with the technical guidance and methodology LILCO has used in reducing the emergency diesel generator loads presently shown in the FSAR (Table 8.3.1-1).
A review was performed of FSAR table 8.3.1-1 (revised table attached), which resulted in the following additions and or deletions.
I 1.
EDG 101 and 102 loading should include the fuel pool cooling pumps, 1G41*PO23A&B, one of which will restart when the bus is loaded.
This correction results in an increase of 24 kw
- i for EDG 101 and 102.
i' 2.
EDG 103 loading should not include the RBCLCW Pump, 1P42*
i.
POO5C which is locked out for 10 minutes.
This results in a reduction of 80 kw for EDG 103 during the first ten minutes following an accident signal.
3.
An analysis was performed to assess the feasibility of I
deleting the auto-start logic from one of the two Reactor
.i Building service water pumps powered by EDG 103.
The results indicate that in the 10 minute interval following an acci-dent, one pump per system train will adequately provide the required system flows and pressures without affecting any currently approved safety analysis.
t 0)\\
t a m ::;;e,e40703
$[
PDR ADOCK 05000322 A
SNRC-1065
.Page 2 As a result, EDG 103 loading will be reduced by removing one service water pump, IP41*POO3C or D from auto-start on an accident signal.
This change results in a reduction of 358 kw for EDG 103.
The loading sequence is shown on table 8.3.1-2 (Revised table attached).
The station procedures will be revised to incorporate a manual start of the fourth pump if necessary prior to initiating RBSW zg flow to the respective RHR Heat Exchanger.
Since RHR Heat Exchanger flow initiation is also a manual operation, this 1
additional operation of manually starting a RBSW Pump is not seen y'
=
as a significant departure from our current operational 2
philosophy.
This review and operational change results in the following k
revised loads for EDG 101, 102 and 103.
EDG 101 EDG 102 EDG 103 Total kw (prior to 10 min) 3433.2 3388.6 3442.7 With this load reduction, FSAR paragraph 8.3.1.1.5, Onsite Standby H
Power Supply will be revised as follows:
}
The rating of each diesel generator is 3500 kw.
The required load 1
on each diesel generator is enveloped as follows:
g Continuous 3475 kw 2 hr per 24 hr period 3500 kw j
It should be noted that the accuracy of the diesel loading on 3
Tables 8.3.1-1 and 8.2.1-2 has been verified by recent electrical testing of the major components.
As a result it is our intention that preoperational and surveillance testing be performed using i
1 i
these loads.
'i
{
It is LILCO's position that utilization of these loads during T
l preoperational and surveillance testing will adequately demonstrate the load carrying capabilities of these engines.
i We would greatly appreciate a timely review, comment and concur-
-I rence by you and your staff regarding this item.
Should you or a
your staff have any questions concerning the elements of this load 33 reduction please contact my office.
4 Very truly yours, Se
=
t l
/ f/2 7N '
i l
J. D. Leonard, Jr.
Vice President - Nuclear Operations 2
a I
BRM:ck
'=
cc:
C. Petrone All Parties Listed in Attachment I k
3 Qs YY I W
ATTACHMENT I
. Lawrence Brenner, Esq.
Herbert H. Brown, Esq.
Administrative Judge Lawrence Coe Lanpher, Esq.
Atomic Safety and Licensing Alan R. Dynner, Esq.
Board Panel Kirkpatrick, Lockhart, Hill U.- S. Nuclear Regulatory Christopher & Phillips Commission 8th Floor Washington, DC 20555 1900 M. Street, N. W.
Washington, DC 20036
.Dr. George A. Ferguson Mr. Marc W. Goldsmith
- Administrative Judge Energy Research Group Atomic Safety and Licensing 4001 Totten Pond Road j
Board Panel Waltham, MA 02154 School of Engineering
~ Howard-University 2300 6th Street, N.W.
Washington, DC 20059 Bernard M. Bordenick, Esq.
MHB Technical Associates David A. Repka, Esq.
1723 Hamilton Avenue
['
U.-S. Nuclear Regulatory Suite K l
. Commission San Jose, CA 95125 Washington, D. C.
20555
- For Federal Express Stephen B. Latham, Esqi
}/
-7735- :d Georgetown Road Twomey, Latham & Shea To-Mailroom 33 West Second Street
?
Bethesda, MD 20814 P. O. Box 398 Riverhead, NY 11901 t
. James Dougherty, Esq.
3045 Porter Street NW Fabian G. Palomino, Esq.
4J Washington,EDC 20008 Special Counsel to the Governor Executive Chamber, Room 229 i
Ralph Shapiro, Esq.
State Capitol
.Cammer and-Shapiro, P.C.
Albany, NY 12224 i
9' East 40th Street New-York, NY 10016 i
Secretary of the Commission Atamic Safety and Licensing U.S. Nuclear Regulatory Appeal Board Panel Commission U.S. Nuclear Regulatory i
Washington, D.C.
20555 Commission Washington, D.C.
20555 f
Atomic Safety and Licensing Robert E. Smith Esq.
l-Board Panel Guggenheimer & Untermyer
!l U.S. Nuclear Regulatory 80 Pine Street j.
. Commission New York, New York 10005
. Washington, D.C.
20555 l:t::
4 TDI g..
ATTACHMENT I Attachment I Page Two Jay-Dunkleberger Esq.
Martin Bradley Ashare New York State Energy. Office Attn:
Patricia A. Dempsey, Esq.
Agency Building 2 Suffolk County Attorney Empire State Plaza H. Lee Dennison Building.
Veterans Memorial Highway
-Albany,--NewcYork 12223 Hauppauge, New York 11788
. Jonathan'D. Feinberg, Esq.-
Dr. Peter A. Morris New York' State Administrative Judge Department of.Public Service Atomic Safety and Licensing Three Empire State' Plaza Board Panel
' Albany, New York 12223 U.S. Nuclear. Regulatory Commission Washington, D. C.
20555~
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p3po.2 patruse Note 4 Loade
.o elue Nose l4 Loads o
o mu.o
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_g _
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2'**
I total hw tafter 10 minutes)
,g s,JJ. 2.
.33066 2 2 tu. 5' tE11U durings the 0-90 mereste period af ter a doelen beste loss of cootent accident seestnum coincident demand. eliowet occure (LOC 4).
1(ilowatt loade given are f rom morastecturer's saeta for the C5. IIIIII. service water paaepe. motor-generator sets, sesv5 ceillier tant te pews all motore sprester t hast 800 lb.
On lose of offelto power, it le riecessary to go to e cold stustafrnwn coeuiltIon if 00-103 does riot start. etnce the three retystred service water gumsps will siot be avellatale. Note tinal only two service water pumpe are roepaired for a doe syn ;
t,ae le LOCA conallt lori.
(only one pa g to connected automatically to 0G-103 the utner may tne connec te'd setuselly neity. )
4*
Two isnt to are started ort DG-801.
One unit to etust down estien it le determined whicts section of the system well be used.
+
Ihese rionclose 15 componeente oro emot. reepstred for a safe seustssown. toedirig Insllcated for verlous modes of operet ton le
{
ases tratile, althosegh not essential. All remaining cossponente are Class St.
telntmum safe.ohutdown respairements f or a suct ton lirie tareak. Actual pump recpstrements s$epesed on break lascallon (see Sec t loss S.3.3).
X Isullcates load respalred.
"* 1hese loads are tripped Intentionally (automat teally) on a LOCA.
These loads are not riormally operating and receive rio automatic start signal efter a LOCA.
1hese riveisef e ty related loads leave seal-In type control circuito that strop out on a toes of offefte power pefor to cosissect ing to the d8esel generators.
These BellV's are connected to their respective diesel tsasses tuut do tion osserete espon a LOCA.
n o.
Ilie load to be carried by the Il-G 5ete cunalet of certain mot **r-operated velves. On Usett 903, one set operates et full load eeus orie set operates unloaded.
Iliese loads are automat Ocelly tripped when diesel generator starte.
lensee londe are prevented f rom stortIng sentil SO mirustee et ter a LOCA signet.
Luede leposed tsy Isat tery cliergere are beood on the oc loeding of the bettery cleargere.
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f.250 1.390 5.644 999
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1.250 8,290 5.644 999
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450 400 4,eeir A o A 2.
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service wetoe Owe and We$vS chltlere receive etert algriele f rom the tsus progree et 12 sec se shown, lhewever. ether Interlocke may delay motor start boyaul thle point.
q 11.e time ohnwn in lebte to time ef ter tlie dicoal generator tsreaker closes to Its associatest 4 kV tsue.
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