ML18219D892

From kanterella
Jump to navigation Jump to search
Advising Intent to Supply Steam for Initial Test of Unit 2 Feedpump Turbine & Main Turbine Generator Using Steam from Unit 1. Scheduling Unit 2 Feedpump Turbine Roll on 9/19/1977 & Main Turbine Roll on 11/7/1977
ML18219D892
Person / Time
Site: Cook  
Issue date: 08/26/1977
From: Maloney G
Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: Case E
Office of Nuclear Reactor Regulation
References
Download: ML18219D892 (10)


Text

AFTER ISSUANCE OF OPERATING LICENSE NRC FQRM 190 U.S. NUCLEAR REGULATORYCOP'ON I2-76)

NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DO ET NUMBER FILE NUMBER Mr. Edson G. Case FROM:

Indiana G Michigan Power Co.

New York, N. Y.

10004 G. P. Maloney DATE OF DOCUMENT 08/26/77 DATE RE CEI VE D 09/02/77 ETTE R

RIG INAL COPY NOTOR IZED NCLASSIFIED PROP INPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTIONAdvising of Licensee intent to supply steam for the initial test of the Unit 2 feed-pu)bprturbine and the main turbine generator usin steam from uh~t 1...and Trans The Following:

1p Consists of info regarding Unit 2 Turbine-Generator Initial Opera%ion Using Steam From Unit 1 NSSS.

2p ICOS[)jaggy DONALD C COOK UNIT g 1

jcm 09/02/77 SAFETY BRANCH CHIEF:

7 FOR ACTION/INFORMATION G FILE INTERNALD ISTRI BUTION I

G E (2)

OELD HANAUER CHECK STELLO EISENHUT SHAO BAER BUTLER GRIMES J.

COLLINS LPDR'IC NSIC 16 CYS ACRS SENT CATE 0 EXTCRNALDISTRIBUTION CONTROL NUMBER

~ggg5 iPOC Qy

J 0

P 4 k

~

A t

L I

k

~-

INDIANA II MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 Relt~ulatorx

~Fila 0)+i.

August: 26,, 1977 Donald C. Cook Nuclear Plant Unit 1 Docket No. 50-315 DPR No.

58 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 v~

'll h

"<<~7vpg

~

Spy ~

.u,,p i

.0, 7

lg

'.co~ ~a

(<

geeI~i410g I RI~e

-Irutf~

t9

Dear Mr. Case:

This is to advise you that it is our intent to supply steam for the initial test of the Unit 2 feedpump turbine and the main turbine generator using steam from the Donald C. Cook Nuclear Plant Unit 1.

We are currently scheduling the Unit 2 feedpump turbine roll on September 19, 1977 and the main turbine roll on November 7, 1977.

Section 10 of our Final Safety Analysis Report describes the crosstie between the Unit 1 and Unit 2 steam supply systems to be used for this purpose.

A description of our intended mode of operation is included in the attached document entitled, "Cook Nuclear Unit 2 Turbine-Generator Initial Operation Using Steam from Unit 1 NSSS."

We have reviewed the attached document with both Westinghouse Electric Corporation, the original NSSS supplier, and Exxon Nuclear Company, the Unit 1 reload fuel supplier.

, Both organizations advised us that our intended mode of operation is enveloped by the safety analyses which have been performed for the plant and, hence does not constitute an unreviewed safety question regarding Unit 1 operation.

~

~

t I

~

lf I ( f II tt I (

e

~, 'l(

a f e e<<h

",Itt I'I,("

hi ct%fi,r',)

t f a

D fI'f(

ye tt'f, l

~

fl>>

Ii *'F'>>h' I

hit lt (

tl eI'P (L

Fi, r'

I c>>t(

c

"~f F

~:,

e If(

fl I

(p I

I>>F l, h,r he C' c)vf IF

'Lff

('et L

>>TP,,

'F rc I>>>>

I c

h,cf R th 4'hf rf

Mr. Edson G. Case August 26, 1977 Xn light of the above, we have concluded that our intended mode of operation is based upon systems described in the FSAR, does not constitute an unreviewed safety question, does not require a change to Technical Specifications, and will not adversely affect the health and safety of the public.

Hence, it is our intent to proceed with testing of the feedpump turbine and the main turbine generator in accordance with the above mentioned schedule.

Very truly yours, GPM:mam

. Maloney Vice President Sworn and subscribed to before me on this 2 ~

day of August 1977 in New York County, New York Notary P GREGORY h'I.

GURICAM Notary Public. State of flew York No. 31-4643431 Qualified in New York County Commission Expires hlarch 30, 19.?2 cc:

R. C. Callen P.

W. Steketee R. Walsh G. Charnoff D. V. Shaller Bridgman R.

W. Jurgensen K. R. Baker Bridgman R. J. Vollen

1

'A p

0 (A(

~

~

(

~

P A

h

.I A1

, <v'(I I

II, (

p 4

f%

)I J[

y I

~

I,

~ (

- (

ll

')f.,(IA f'(ll 1P Il i'(

fy II C

I'g '

~ (

KV<

g V

A P 0

y

~ t

(,

IPl/,

J

COOK NUCLEAR UNIT 2 TURBINE-GENERATOR INITIALOPERATION USING. STEAN FROi~l UNIT I NSSS Ne are planning to make a series of test runs of the feed pump turbines (FPT) and the main turbine-generator of Cook Nuclear Unit 2 using steam from Cook Nuclear Unit 1.

These test.

runs are to be made prior to the completion of Unit 2 NSSS; their purpose is to check out, dynamically balance the turbines if necessary, set the turbine controls, check generator excitation, check oversoeed trios and run other pre-operational tests so that these machines will be ready for operation as. soon as Unit 2 NSSS is comoleted and licensed for power operation.

During these test runs, each FPT will be run, one at

=a time, uncoupled from its feed-pump, to its rated. speed of.5300 rpm and to its overspeed trio setting of 5670 rpm.

Each feed-pump turbine will also be run, coupled to its feed pump,, to approximately 5300 rpm.

'These tests on the FPT's are scheduled to be run during the weeks of September 19 and 26, 1977.

The main turbine-generator will be run to its rated speed of 1800 rpm but will not be loaded or electrically connected to the power system.

The machine will also be run up to its over-soeed trip setting of 2016 rpm.

These test runs on the main turbine-generator are scheduled to be'un during the 'weeks

'f November 7 and 14, 1977.

The steam from Unit 1 is to be suoplied,to Unit 2 through a temporary cross-tie pipe of 12" diameter which connects Unit 1 turbine by-pass header with Unit 2's main steam lead and turbine by-oass header.

'he maximum steady state flow expected through the cross tie is aoproximatelv 30,000 lb/hr during the,couoled FPT runs and approximately 925,000 lb/hr durina the main turbine runs.*

Momentary flow spikes above these flows may be needed in order to rapidly acCelerate the main turbine through its critical soeeds,near

590, 800, 990 and 1600 rom. It is not possible to predict the maanitude or duration of these flow spikes but they are not exoected to exceed 75K of the steady state flow'rior to the spike and their duration is not exoected to exceed 2-minutes each.
  • Unit 1 Hain Steam flow at 100% power (3250 Klt) is 14,206,000 lbs/hr.

44 l

P

(

~

~

The steam crosstie is equipped with a manually operated shut-off valve at both the Unit 1 and Unit 2 ends.

A flow metering orifice of 8.536" is installed. in the line.

vi In the event that Unit 2 turbine cohtrol 'valves open more than desired. or there is a steam line break at the Unit 2 end of

'he

crosstie, the maximum steam flow through the crosstie is calculated to be approximately 2.67 x 10 lb/hr at, which point the flow is choked.

This is based on a Unit 1 main steam pressure of 830 psia, saturated, corresponding to approximately 60% power, and does not take credit for the resistance of the flow metering orifice.

~

The entire main steam system piping of Unit 2 will be pressurized, through the crosstie, back to the Steam Generator Stop Valves which will be closed and remain closed during these test runs (i.e. Unit 2 Steam Generators will not be pressurized)

Valves in the branch lines from Unit. 2 main steam s'stem to the reheaters, to the auxiliary steam system,and to the turbine steam seal syste'm will be closed and remain closed during the test

'uns.

All but' or 3 of the Unit 2 turbine by-pass valves will be kept closed and their block valves will be closed.

The 2 or 3 valves which remain operational will be used, as needed, to regulate. steam flow through the crosstie.

The 12 inch temporary crosstie between the Unit 1 turbine by-pass header (36 inches) and the Unit 2 turbine main steam lead (30 inches) is shown on FSAR Diagrams Figure 10;2-lA and 10.2-1B.

During this testin,g, power operation will be restricted to 60% or less.

Condensate for return to the Unit 1 condenser hotwell will be supplied by either t~e normal Unit, 1 make-up system or by pumping it back from the Unit 2 condenser.

'e above testing operation was reviewed by Westinghouse Electric Corporation, the original NSSS suoplier.

Nestinghouse found that the proposed mode of operation is acceptable and is bounded by the analyses of he "xcessive Load Increase and Steamline Rupture Incidents presently included in the FSAR.

Exxon Nuclear Company our reload fuel supplier, has also reviewed our intended mode of operation and has also concluded that the indicated operation is enveloped by the safety analyses which have been performed on the plant.

RECFIVED 00cuI IEHT PROCESSING UNIT 8rI St=.F 2

AM 10 4o