ML20054D515

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Forwards Comments to Be Addressed in Facility Operating Procedure & Training Program.Response to Be Provided by 820530
ML20054D515
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/16/1982
From: Miraglia F
Office of Nuclear Reactor Regulation
To: Maurin L
LOUISIANA POWER & LIGHT CO.
References
NUDOCS 8204230085
Download: ML20054D515 (22)


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Docket No.: 50-382 pg 1

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982u3 b asEN[pffyu::a Mr. L. V. Maurin Vice President - Nuclear Operations a

Louisiana Power & Light Company roc g

142 Delaronde Street 0

Hew Orleans, Louisiana 70174

=

Dear Mr. Maurin:

Section 5.4.3 of the Waterford SSER No. 2 stated that the staff would determine the adequacy of the operating procedures needed to place the plant into shutdown cooling assuming loss of an atmospheric relief valve. The Procedures and Test Review Branch has reviewed this procedure and has concluded that it is adequate provided the enclosed corzients are adequately addressed in the procedure and the trainingpprogram.

Your response to these comments should be provided by liay 30, 1982.

If you have any questions regarding the natter, please contact the p Project flanager Suzanne Black on (301) 492-7119.

Sincerely, Original signed by Frank J. Miras11a

/

Frank J. litraglia, Chief Licensing Branch No. 3 Division of Licensing cc w/ encl: See ne.<t page.

DISTRIBUTION:

Docket File 50-382 LPDR PDR TIC TERA LB## Files JLee SBlack l

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ACRS (16) l 8204230005 820416 PDR ADOCK 05000382 A

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n:c ronu aia no soinucu e24o f OFFICIAL RECOFiD COPY

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  • 'r. L. V. " aurin

,;;TE; m;:3 Vice President

';uclear Operations Lcuisiana Power & Lignt Ccmpany 142 Delaronde Street

es Orleans, Louisiana 70174 W. Malcolm Stevenson, Esq.

"cnroe & Lemann 1424 'n'hitney Building Nes Grieans,' Louisiana 70130 Mr. E. Bl ake Shaw, Pittman, Potts and Tr:-bridge D$C.

2bO36 ig n Mr. D. L. Aswell Vice President, Po.;er Production Louisiana Pc-er & Light C0mpar.y 142 Delarande Street l

New Orleans, Louisiana 70174

" r. F. J. D ru m<.io n d Project Manager - Nuclear Louisiana Pcser & Light Ccapany 142 Delaronde Street New Orleans, Louisiana 70174 Mr. D. B. Lester Production Engineer Louisiana Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Lyman L. Jones, J r., Esq.

Gillespie & Jones P. O. Box 9216 Metairie, Louisiana 70005 Luke Fontana, Esq.

624 Esplanade Ave.

New Orleans, Louisiana 70116 Stephen M. Irving, Esq.

535 North 6th Street Baton Rouge, Louisiana 70502 Resident inspector /Waterford NPS P. O. Box 822 Killona, Louisiana 70066 Dr. D. C. Gibbs Middle South Services, Inc.

P. O. Box 61000 New Orleans, Louisiana 70161 u

COMMENTS ON WATERFORD 3 NATURAL CIRCULATION C00LDOWN PROCEDURE

~

The Waterford 3 Natural Circulation and Cooldown Procedure (0P-901-051) with specific comments is attached.

Additional general comments are as follows:

1.

The operator should be cautioned to verify that adequate feedwater is available or can be made available.

The amount of feedwater needed to achieve cold shutdown should be specified.

2.

The procedure should be expanded and a caution statement added to ensure that the plant is not depressurized during natural circulation at a rate which could result in RCS voiding.

3.

The following steps are recommended to minimize the possibility of developing a void:

(1) Pressure decreases in the RCS should be indication in the idle SG, and (2) It should be based upon TH stressed that a natural circulation cooldown should be performed slowly.

Perhaps (1) and (2) can be combined by stating that plant depressurization should be based upon. the highest of either the idle SG TH or TC or the most conservative incore thermocouple temperature.

4.

The operators should be trained to recognize voiding should it occur.

5.

Verify that the operators have adequate information to determine if natural circulation is occurring in the isolated SG, and provide procedures and training for recognition of this condition.

Caution the operators to be aware that natural circulation is occurring in the isolated SG, and provide remedial actions if it stops.

6.

Verify that all instruments and control functions called for in the procedure are available during loss of offsite power.

7.

Place caution statements prior to the step to which they refer.

If a caution does not make sense prior to the step, refer to the caution in the step and include the caution immediately thereafter.

8.

Do not place action steps within cautions or notes.

If certain action steps should be emphasized, this can be done by preceding them with the word IMPORTANT.

9.

In the table for determining AT, include columns to show:

(1) time after shutdown in minutes.and seconds, (2) shutdown power as percent.

of operating power, and (3) optimum AT.

The table should be identified -

with a heading, and it should include all of the ai values the operator will need.

t

-7 In accordance with IE Circular No. 80-15, consider installation of It a reactor vessel head metal temperature monitoring system.

10.

should aid the operator in preventing a reactor head to bulk coolant temperature differential large enough to form a steam void during If such a monitoring system is natural circulation cooldown.

installed, include its use in the procedure.

Attachment:

Waterford 3 Natural Circulation and Cooldown Procedure (OP-901-051)

S 9

u.:-.Nar:al 0;1ra". n6

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i Revision 0 3 raft 1 N a tu r al ' C i.-cul a ti o n

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TABLE OF CONTENTS 1.0

?UP.?OSE 2.0 SYMPTOMS 30 AUTOMATIC ' ACTIONS 4.0 IMMEDIATE OPERATOR ACTIONS 5.0 SUBSEOUENT OPERATOR ACTIONS 4

6.0 ATTACHMENTS 6.1 Natural Circulation Cocidown Data (1 page) 4 f

6.2 Reactor Vessel Uppet-Head Cooling via Natural Circulation

( ? reliminary) (1 page) 6.3 Decay ?cwer. Curve (?reliminary) (1 page)

-l 70 COMMITMENTS AND REFERENCES LIST 0E EF CTIVE PAGES i

Revision 0 Title 1-18 Revision 0 I

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is in a stable condition by verifying the 5 1.1 Ensure that the plant follcuigg conditions:

subcocied

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5.1.1.1 Reactor Coola::

System (RCS) greater than 50 degrees u-4 4 <- <. 3er near nor=al Operating level 5.1.1. 2 Sba= gen.ra:Or levels at level heater cu:cff of.

5.1.1.3 Pressuri er level grea:er than the icw nQg

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r 5.1.2 Verify tha:

10 =inutes af ter the loss of forced ficw by observing the i=:::.1/

following indications:

RCs cold leg temperature at or appecaching saturation 5.1. 2.1 temperature for the-exist"_ng steam generator pressure 5.1.2.2 Lecp.6.T (Th-Tc) less than 58.2 degrees F 51.2.3 Cold leg temperature constant or decreasing with reduction of steam generator pressure 5.1.2.3 Hot les temperature constant or' decreasing due to eqoldown s

m 5.1. 2. 5 No abnormal. differences be: ween hot leg \\RTD's anc co?s exit h

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.;hermocoup es removal by observing the fo11s ings 5.1.2.5 Verification of heat parame ter s :

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3.

Steam generator level C.

Steam genera:ce pressure N

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Na ural' Circulation 5.1.6 To maintain the plant in ho standby on natural circulation ficw perf orm the fellcwing:

.10..

n Parameter response as the result of change during natural circulation will be slow (5 ~ O nin.)

as (6-12 sec.).

compared to forced ficw response Continuously =onitor :he indica icns of natual circulation 5.1. 6.1 listed in step 5.1.2.

5.1.6.2 Maintain steam generator levels at nor=al opera:ing levels utilizing the main or e=ergency feedwater system.

5. /. 6. 2.

f92g tga.t w cm % Q CAU?!O.N

. eedwater-additions to _the. steam generator s saould. be made in a sicw, controlled =anner.

Avoid rapid feecwater transients.

C10 TION If the sain f eedwater syste= causes excessive cocidown or is unable to maintain stea= generator level, utilize the emergency feedwater system.

as possible Maintain pressuriner pressure as near to.2250 psia 5.1.6.3 u:ill:ing the pressurizer heaters and auxiliary spray.

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iatural C1.-culation

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is necezzary If operatien of auxiliary spray whert the & ~ between the RCS and pressurizer recorc the operacion in 7

exceeds 200 degrees.,

l accordance with 0?-903-083, :ece-d'-e cf 3---sort e-Sr-9v

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desirec, proceed Oc sec--

If a cooldown on natural circulation is 5.1. 7

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Of f. :::r: 21 Opers;:.ng crac w.e Revision 0 Draft 1 Natural Circulation 5.2 NATURAL CIRCULATION CCCLDC*riN 52.1

?erfor: NE-5-003, Sh"tdev- 'S-efa v a ' ce ti c-and borate the RCS to the ccid shutdown boron concen: ration.

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i AiCsr If conditions per=it, co=plete the-RCS boration cooldcwn. (Ifnce, prior to cocmencing plant the =ari=um possible rate while borate at cooling down.) @ & M [

5.2.1.1 If conditions permit, equalize the RCS and pressurizers baron concentration by utilizing pressurizer heaters and auxiliary spray.

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CAUTION

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1 tdcurYin service 0-is pr 9 -'bla ~2 / :

the when using auxiliary spray to =ini=1:e i

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pressurbtransient.

pg 5.2.1.2.

Notify the Chemistry Depart =e::t to sample the RCS a: least once every thirty =inutes to ensure equilibriu= boron concentra:1:ns are achieved throughout the RCS.

5. 2.1. 3 If conditions permit, verify baron concentration by sample analysis prior to initiating cooldown.

CAUTION a =axi=um The Technical Specifications per=it RCS cocidewn of 100 degrees F in any one ' cur n

period.

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F 5.2.2 If both stea= generators are available, establish a ~~

2:

urbine

. pee-eeer cooldown rateh y either =anually controlling :he or by use of the bypass valves if the condenser is available, at=ospheric du=ps..

refer :o section.

TE one of the stear generators is isciated, 5. 2. 2.1' c.,. 2,.

Maintain RCS pressure as near to 2550 psia as possible curing 5.2.2.2 the cooldown.

Utili=e pressuriner heaters and auxiliary spray.

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CAUTION A rapid increase in pressurizer level while operating auxiliary spray is indicative of a void in the reactor vessel head.

If voiding 1:r the RCS is experienced, the folicwing directionai guidelines should be applied.

M 1.

Stopvcepressurization and cocidown.

2.

Place pressurizer level control in MANUAL.

3 Energize pressurt:er heaters as necessary 9

to raise RCS pressure.

Collapse of the void will be indicated by a rapid decrease in pressurizer level to near pre-void level.

4 Verify 50 degrees F subecoling =argin.

A:

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rip 5.2.2.3 Reset pressurizer pressure and steam generator pressure se: points during cooldown and depessurizacion in accorcance wi:h t

i OP-3-00~, "19nr 5-craction Sv? ten.

5.2.2.4 If cesired, co==ence de-gas of the RCS in accorcance with OP-2-00 5, CS ami c s 1 and V c ' *2m a C"--ci Sv?ter.

Lcwer RCS te=perature to approxi=ately 330 degrees F anc soak in 5.2.3 accorcance with A:tacn=en: 5.2.

Do. = cc==ence cepressurizati:n l

until the scak has been cc=ple:ed.

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Off,-6cr=al Opert ans Frectcu.e F.evision 0 Draft 1 Na: ural Circulation CAUTION a =aximum The-Technical Specification persi:

pressurizer cocidewn o:' 200 degrees F in any one hour period.

Depressurize the RCS to 360 psia by utilining the auxiliary spray.

5 2.4 CAUTION M.,8e.

V le:down in service

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when using the auxiliary spray to =inimize the pressure transient.

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gaer r If operation of the au? liary spray is necessary when the d.T between RCS and recorc the presurizer exceeds 200 d.e.grees F, 0?-903-083, operation in accordance w ih 9ece-di-r cf 3 -e s s u-i c e-Sc-sv

-scetect.

'4 hen RCS pressure decreases to less than 700 psia but greater 5. 2,. 4.1 (SITS) ::

than 650 psia, depressuri e the Saf ety Inj ection Tanks e erv T 4=c-ter 335 m 10 psig in accordance with OP-9-008, S a Svsrem.

bypas's

ne

'4 hen RCS pressure decreases to less than 400 psia, 5.2.4.2.

Lew ?ressurizer Pressure Trip in accordance with 0F-9-007, _:' =-c

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Revicica 0 Jraf t 1 Na" u:-al Circulation 4

unlock and

'4 hen RCS pressure decreases te less than 375 psia, 5.2.4.3 close the SIT outle valve breakers and close the SIT cutle:

valves.

ED W E F.

VALVE S

SI-3311 3T11-3 CIT 8E SI-3313 1113-S CET SH SI-3321 3111-S CKT SM SI-33 23 3113-S CKT Su 5 2.4.1 Stabli:e RCS pressure at approximately 350 psia.

? lace the shutdown cooling system in operatice in accordance with 5 2.5 oP-9-cos, S"u' dew" Ccc14-r sv er.

i

'4ith the shutdowr. cooling syste= in operation, proceed to 5.2.5 o?-10-006, Pince cocidewn.

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CAUTION =-

Do not depressurire the RCS to less than 360 psia until it has been determined that reactor vessel head te=pe'ratures are icw

_enough to preclude voiding.

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5.3 1 Deter =ine decay power as percent of operating power using A -

tach =en: 6.3, Decay ?cwer Curve.s A.A M c

W' AI to be 3ased on the folicwing table de:er=ine the opti=um 5.3 2 saintained. between the 4t;n ;;;;. ;;;r secondary temperatures x

q Ms.Cer-A p h.

CAUT3tl Tnis table is based on scdel analysis.

If =aintaining the AT in this cable does not cool the isola:ec steam genera:ce, the operator should choose a e I slightly less than what is listed.

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3 5% or greater 120 2 10-degrees T 90 2 10 degrees 7 2.2% to 3.5%

50.=. 'T. 5 d e gr ees F 1.1% to 2.25 30 m 5 degrees F less than 1.1".

Cccmence cooldown using the opera ing stea= genera:ce un:il

&,. 5 2 2 f 533 optimus AI is reached.

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5.33 Reduce the cooldown rate to =ain:ain the opeisu= AT.

of operating power decreases with time, adjus: the 5.3 5 As the percent 6.3 op imu= AT as required by Attachsen:

Continue plann cocidown and depressurination in acecrcnace with 5.36 step 5.2.2.

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Natural Circulatica 6.0

~~tC*au?V~S 6.1 Natural Circulation Cecidewn Data.

Heactor Vessel Upper ' dead Cooling via Natural Circulation 6.2

(?relisi=ary)

Decay ?cwe.- Curve (Pr-14 d -ary)-M M w J 4<-

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