ML17249A806

Submits Deferred Response to NRC Re long-term Recommendation X.4.3.3-2 for Auxiliary Feedwater Sys.Water Source Capabilities Will Provide Required Flow by Gravity Feed to Pump Suction

ML17249A806
Person / Time
Site:	Ginna
Issue date:	03/28/1980
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Ziemann D Office of Nuclear Reactor Regulation
References
TASK-10, TASK-RR NUDOCS 8004010355
Download: ML17249A806 (17)

Text

SUBJECT:

Submits defer ed response to NRC 79102? ltr re long term requirement~ X.4.3.3 2 for auxiliary feedwater sys.Hater source capabil.ities will provide required flow by gravity feed to, pump suction.

DISTRIBUTION CODE:

A042S COPIES RECEIYED:LTR ENCL~

SIZE:

TITLE'. Resp to: Lesson Learn Task Force Comb Eng L 50 267 I

NO~Es.'J += Z'WE5'~MACK ~ AQ<N++KE RECIPIENT COPIES RECIPIENT

.COPIES

~'D CODE/NAME:

L~TTR ENCL ID CODE/NAME LTTR 'ENCL ACTION A 08 BC OE8 ~

7 7

r-~

INTERNALS 1

1 1

1 2

2 1

1 1

1 1

1 1

0 1

1 2

2 1

1 1

1 1

1 1

1 1-1 2

2 02 NRC PDR Ob ANDERSONgC, 15 I L

E" j.9 ENG BR 21 PLANT SYS BR 23 EFLT TRT'YS OELD 05

NELSONgC, 07 CHfALINAp G ~

18 CORE'ERF<<'R 20 REAC SFTY BR 22 EEB IMBROgG ~

TELFORDpJ,T, REGULATOR NFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBA 8004010355 DOC SEDATE: 80/03/28 NOTARIZED'O DOCKET 0'

FACIL!50-244 Robert Emmet Ginna Nuclear Planti Unit ii Rochester G

05000244'UTH, NAME AUTHOR AFFILIATION NHITEgL,D~

Rochester Gas L Electr ic Corp.

RECIP ~ NAME RECIPIENT'FFIL'IATION ZIEMANNtD ~ L ~,

Operating Re'actors Branch 2

EXTERNAL: 03 LPDR 24 ACRS 1

1 16 16 04 NSIC

, gqgQ gi4 TOTAL NUMBER OF COPIES REQUIRED:

LTTR ~

ENCL

0

~

t

'l 4

~

~

1 V

I tl

. ! ztusuz Isiruz

'7 rig zez!iz

!ice IIuzizziz ROCHESTER GAS AND ELECTRIC CORPORATION N[V

,5Zx:.,"

I o

89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.

VICE PIIESIDENT TELEPHONE AIIEA CODE TIE 546 2700 March 28, 1980 Director of Nuclear Reactor Regulation Attn:

Mr. Dennis L. Ziemann, Chief Operating Reactors Branch N2 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

NRC Requirements for Auxiliary Feedwater'ystems R.

E.

Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Ziemann:

A letter from Darrel Eisenhut dated October 22, 1979 requested that we evaluate our auxiliary feedwater system against the applicable requirements contained in Enclosure 1 to that letter.

Our letter to you dated November 28, 1979 responded to Mr. Eisenhut's letter and provided all the information requested in Enclosure 1

except for response to long-term recommendation X.4.3.3 2,

which was deferred until April 1, 1980.

The purpose of this letter is to provide the deferred response.

Long-term recommendation X.4.3.3 2 requested that we evaluate the water source capabilities available to the turbine driven auxiliary feedwater pump suction to assure that there is a water source sufficient to supply the required auxiliary feedwater flow for two hours independent of any AC power source.

We have examined our water source capabilities and determined that 22,500 gallons total inventory in the condensate storage tanks will provide the required flow by gravity feed to the pump suction.

The basis for our determination is contained in Attachment A.

Other water sources, including the condenser hotwell and service water, are normally available to supply the auxiliary feedwater system.

The service water pumps can be powered by the emergency diesel generators and the service water system, including the power supply, meets the single failure criterion.

Nevertheless, these design features have been ignored in establishing the minimum required condensate storage tank quantity.

l

'9 ooo4oxo 355

I.

I ll P

, ~

ROCHESTER GAS AND ELECTRIC ORP.

DATE March 28, 1 980 Mr. Dennis Ziemann, Chief SHEET NO.

Our present technical specifications require that at least 15,000 gallons of water be maintained in the condensate storage tanks even though our practice is to maintain much more.

An application to amend our technical specifications will be filed in the near future.

Xn the interim an administrative order will be issued to maintain at least 22,500 gallons of water in the tanks.

Sincerely yours, L. D. White, Jr.

lI

'C l

ATTACHMENT A The quantity of water necessary to supply the required auxiliary feedwater flow for two hours has been determined by comparing decay heat generated during the two hour period with the heat which can be released by relieving steam through the steam generator power operated relief valves.

The amount of decay heat generated following shutdown is given in the basis for Technical Specification 3.3 and is as follows Time After Shutdown Deca Heat

% of Rated Power 1 min.

30 min.

1 hr.

8 hrs.

4.5 2.0

1. 62

0. 96 It will be assumed that. immediately following reactor trip decay heat is 9% of full power.

Decay heat is plotted as a piece-wise linear curve on Figure 1.

The integral of this curve from 0 to 120 minutes is 250% power minutes.

The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> integrated decay heat is:

(1520 x 10 watts/100%

power)(250%

power min)(5.69 x 10 Btu/min/watt) 6 2

8 2.16 x 10 Btu Following reactor trip saturated steam wil be released from the steam generator power operated relief valves at a pressure of 1050 psig. It is asumed that the condensate storage tank temperature is 70'F.

From steam tables the change in enthalpy of the auxiliary feedwater as it is converted to saturated steam is:

1190 Btu/ibm 41 Btu/ibm = 1149 Btu/ibm The mass of water required to remove the first two hours of decay heat as saturated steam is:

2.16 x 10 Btu/(1149 Btu/ibm)

= 1.88 x 10 ibm 8

5 Converting this mass of water to gallons yields:

(1.88 x 10 ibm)(0.016 ft /ibm)(7.48 gal/ft

)

= 22,500 gallons 5

3 Thus, the quantity of water necessary to supply the required auxiliary feedwater flow for two hours following reactor trip is 22,500 gallons.

P

NO.

341 I 1044t4 DIETZGEN GRAPH PAPCR 10 X 10 PER HALF INCH EUGENE DICTZGKN CO.

MAOC IN U. S. A.

3>>

3)!)ij fft 4 EC

>>p HE f ~ 4 CU Ejj

'I

3) tr, 14 jg>>

ifj 4.4 44j" ftf 4

tt I

4>>

3 44ff

~ iiti i f'3 fl ~f t

ifit jji>>

34>>t.

I ~ f

>> ~ t

>>ii t ~ I

~ If I

3)t)

~ )f

'tt 1 ~ 1

!il'lil 1 ~

J

-I ~

-tjj)j ij

!Ilf Ilt!

!!ilI I jj)i j i' 4

I!lft!Ii

~ )ff it t.

jki.~

~ift

-tij ftit ijtf li 4

!ftj I,,

~ I

~

tijj )jj::

~ ~ ~. ~

I!!I!"I I'}IJI',

+)>>'

ji.

i!!ill!i ft,'< ',g

)N f'))3 3)), if,'j 114 1-4$

f4f a

I ~ I

~ I tw ja I

f>>ft tjP 4tglJj:I

) fj" fj)'I!}

I HI li IIII I IIff If il ill!I'II j jj'j,",':E t'>>fj

'1! l}l l!'4 ffA

)it>>

'Jt4 tt f4 3)j 41 J

~ J4 I

~ ~ 14 fl ~ f Sj

~

)

~ 4 II>>

'L>>'4 I

14 QJ I>>f 44 1

ijt>>

14i Lijl ttf 11 Jj.

Itft 4ff-Tttii

'If'i3

!3)3

>>f.tt

~ f t.J t>>1 f 1 1 ~

F 44'l!I f ).j'.

)T 1 Ii 4

t l.j>>

44 I

j) t4 4T tti fir>

1, ~

'-t f-I ~jt I>>

4 ~ ~ ~

~ f ~ ~

~ f t jest 4 tj-I

~ 4+I I ~ 4 f!41 44 t f

~ ~ 44 I ~ If

~ll~

4jf I t 4~.1 J

lent 4 4 'I'

~ Jl j-I>>I 4444 jp jg 3

4 5

6 7

8 Time After Shutdown (hours)

Y 4

O 8o Oa ovoo 6V

,jMlll.AP1MCK FiK lmp)

Docket No. 50-244 ter.

Leon D. White, Jr.

Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East

.Avenue'ochester, Hew York 14649

Dear Mr. White:

'AR 2 6 1980

SUBJECT:

TENDON INSPECTION AND LIFT-OFF VERIFICATION FOR GINHA NUCLEAR POWER STATION.

We are continuing our review of the report attached to your letter dated Decem-ber 12, 1979 relating to tendon inspection and lift-offverification for Ginna and have found that the following information is needed within 30 days of your receipt of this -letter.

1.

Concrete Shrinka e (p.3)

The shrinkage of concrete is an important factor which contributes to the loss of prestress.

The magnitude of, the shrinkage must be calculated with reasonable accuracy.

The best method of estimating the amount of concrete shrinkage for the use of any structural design is through the use of shrink-age tests.

Only in the case where no test has been performed, can the sug-gested shrinkage strain preseoted in Regulatory GuiM 1.35.'J be used to establish a tolerance band.

At Ginna, shrinkage tests in accordance with ASlld C-494 weae performedIQAPItteburgh TeetIng Laboratory In 1967 uIth re suits greater than 100 x in/in.

Explain why this has not been taken into the consideration.

Also prdvide the mix design of the in-placed con-crete and discuss the significance of the water quantity and humidity en-vironment.

2.

Time when shrinka e starts (p.4)

It is usually assumed that no shrinkage would take place during.curing if concrete is kept wet.

This may be impossible for large placements.

Regu-latory Gaide 1.35.1 suggests that shrinkage starts 10 days after pouring the concrete.

Provide the basis for assuming that shrinkage starts one hour after concrete placement.

Also, discuss the construction time effect on the shrinkage.

3.

Some specific creep curves were ised in the calgolation of prestress loss ue QFFIUS o creep.

. for..the. Gin ovs e

ese c rves, e ass a.containment and.the..test.

c a e

concr

~sulks.

e m x es gn SURNAME OATE$..

NRC FORM 318 (9-761 NRCM 0240 4U.S. GOVERNMENT PRINTING OFFICE: 1979'289 369

jag q ~ HktY

&44 C I

r h

I

~

I 4

/

~ I.

~

4 KI

~

'I ~

II 4 f

~

tl

~'

I

'I 3

~

IIp

~

4 II 4

44 I

r

,I

~

~-

4 I

44

~

4 r

4 tl 4

/

I 4

4

• /'

4th I 4

4 4

Lh I

Il 4'-

4

~I rh 3

~

4

'g I

4 4

4 4

I

~

3 4

'I Kl I

4 I

Pl 4

F

'lI I.

I

~,

I KK

~.r t

4 I

I "t/f

~ <

I' I ~ I \\ 'k 3"r. Leon D. White, Jr. larch 26, 1980 CC Harry H. Voigt, Esquire

LeBoeuf, Lamb, Leiby 5 HacRae 1757 H Street, t<.

W. Washington, D. C. 20036 Yir. Yichael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Comnittee for Scientific Information Robert E. Lee, Ph.D. P. 0. Box 5236 River Campus , Station ~ Rochester, New York 14627 Jeffr'ey Cohen New York State Energy Office Swar: Street Building Core 1, Second Floor Empire State Plaza

Albany, thew York 12223 Director, Technical Development Programs State of Hew York Energy Office Agency Building 2 Empire State Plaza

Albany, t(ew York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontari o 107 Ridge Road West

Ontario, Hew York 14519 Director, Technical Assessment Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Hall P2 Arlington, Virginia 20460 U. S. Environmental Protection Agency Region II Office ATTN: E IS COORD INATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C. 20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C. 20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C. 20555 Mr. Thomas B. Cochran Natural Resources Defense Council, Inc. 1725 I Street, N. W. Suite 600 Washington, D. C. 20006