ML20126C153

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Rev STR-1 to Procedure Tp 600/2, Controlling Procedure for Once-Through Steam Generator Repair Testing
ML20126C153
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 09/15/1983
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20126B295 List: ... further results
References
FOIA-84-897 TP-600-2-REV-ST, NUDOCS 8506140329
Download: ML20126C153 (6)
v • d • e


Text

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CW STARTUP TEST PEVISION t

DATE 09/15/83 TESTPROCEDURETITiE CONTROLLING PROCEDURE TP NO. TP 600/2

, FOR OTSG REPAIR TESTING REV. NO. STR-1 REASON FOR CHANGE : (a) To clarify method of establishing Feedwater flow rate.

- (b) To change to two (2) RCP's during cooldown vs. three (3).

Two (2) RCP's is normal procedure for OP 1102-11.

(c) To assure Chemistry Manager reviews and approves OTSG chemistry prior to commencing cooldown.

INSTPUCTION FOR ENTERING CHANGE Remove: Cover Page, Rev'0; Table of Effective Pages, i; Pages 16a, 17 and 87.

(

Insert: Cover Page, STR-1; Table of Effective Pages, i; Pages 16a, 17 and 87,

)

Effective Page STR-1 CEANGES ENTERED I certify that, all changes have been accurately entered into the test procedure:

The following replaced pages of the Official Field / Office Copy are attached:

OFFICIAL FIELD COPY DATE OFFICIAL OFFICE COPY DATE Page of 8506140329 850125 PDR FOIA DETJEN84-897 PDR j

//,s

/6

THREE MILE ISLAND UNIT 1 g g3 -1 CONTROLLING PR0CEDURE IF.1BER TP 600/2 FOR OTSG REPAIR TESTING REVISION STR-1 PREPARED: -Cognizant Engineer

~

Date 9//[N RESPOSS5BLE TECHNICAL REVIEWER: '

Signature N b 'Date 9-//-[3 UfPLEME's'TATION APPROVAL:

Signature -M Date 9 - / ~

05M DIRECTOR CONCURRENCE: ~

Signature ~

Date '

U i

APPROVAL OF TEST RESULTS:

S'U S'T Represent'ative Date C; CLOSURES:

1. T,est Execption and Deficiency List lA. Questions for Test E:<ception Acceptability
2. Quality Control Witness Signoff Sheet
3. OP 1102-1, Plant Heatup to 532 F (Modified by TP 600/2)
4. OP 1102-11, Plant Cooldown (Modified by TP 600/2)
5. EP 1202-5, OTSG Tube Leak / Rupture (Modified by TP 600/2)
6. OTSG Repair Testing Sequence
7. Heatup and Cooldown Computer Points
8. OTSG Leak Rate Data Sheets
9. General Emergency Operating Guidelines for HFT Program e

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- *L ' .; , .,; ,

i  %

x TABLE OF EFFECTIVE PAGES

,PAGE EFFECTIVE PAGE PAGE- EFFECTIVE PAGE- -PAGE EFFECTIVE PAGE -

1." 'O~ 32' O 63 0 2'- .0 - 33 0 64' 0-34 0-65 0

],. $ '

E4- 0 35' O 0

5- 10 36 .0 67 0 6 .0' 68 0 L37 0

'38 0:

  • 69 0-

'g-8 O 39 O 70 0 ,

'9 ~ 0 40- 71 0 0

-10 0 41- 0 72 0 11 0 42 0. 73 0

. '12 0' 43' 74 0-

0 13 0~ 44 0 75 0

-14 0 45' 76 0 O

15 0 77 0

46. 0 ,

15a' 0 78 0 s .16 0 47 ~0 3" kN k 48 0 79 'O 18 0 49 -80 0 0

II9 0 50- 81 0 0 ,

' 51 82 0

_20 '0 0 21 0' 52' 0 83 0 22- 0 84 -0 53 'O

23. 0 54 0 85 0 24- 0 55 86 0 0

25 0 87 STR-1 56 0 25 0 88 0 57 0 27 0 58 0 89 0 28-0 90 0 59 0 ,

29 0 60 91 0 0

0 61 0 92 0

30. ~

31 0 93 0 62 0

- D1I UNIT I TP 600/2

-- t 1.

9 4

19.0 TEST METH0'D (Cont'd.)

9.5.3 'To accomplish the desired cooldown rate and approach the 140 F AT , limit proceed' as follows:

NOTE: . Ensure MFW. flow is not interrupted to both steam generator MFW nozzles.

~

9.5.3.1 At hot shutdown conditions and three RC pumps run-

-ning, reduce MFW flow-to approximately 30 to 40 gpm

-per OTSG by establishing stable OTSG' level with FW-V-85 A/B and with FW-V-16 A/B closed. Start the-fourth RCP and boil water down~to. low level setpoint.

When.the low level setpoint is reached, trip one (1) STR-1 RCP and place FW-V-16 A/B in auto level control mode.

Maintain constant OTSG pressure and constant RCS T,y, during the boildown.

Hold conditions with three (3) RCP's operating and OTSG at the low. level setpoint until plant conditions and chemistry are stable.

Unit 1 Chemistry Manager has reviewed and approves v

OTSG chemistry for cooldown.

Signature Date

~

(Chemistry Manager)

NOTE: Place main steam line rupture detection enable / defeat

. switches (four) in ' defeat prior to reaching 600 psig. -

9.5.3.2 Secure one RCP and using the startup valves in auto, adjust TB valve setpoint to smoothly decrease each

. OTSG pressure from 900 to 600 psig in first 30 minutes.

, This shoul.d cause T,y, to decrease at approximately 90F/ hour.

9.5.3.3 Monitor (Step 9.5.1) average shell temperature, T,y,,

and tube-to-shell AT every ten (10) minutes, and be sure AT never exceeds 140F.

9.5.3.4 Continue lowering steam pressure so that T,y ,de-

- creases at 90F/ hour. After several minutes, the shell temperature will start to decrease but at a rate less than 90F/ hour. TMI UNIT 1 TP 60.0/2

, Effective Page STR-1 Page 16a b" I

y _.

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' . e' .p ; ; s

~ p' af 1 ?%

2 3 .-

. v -. ,., .

9.0};TESTMETHOD(Cont'd.)'

(g , , _- .; NOTE: If a minimum bypass-flow of-main'feedwater

. ^s 3

,y , ,has been' established to keep the main feed-

. water nozzles.;(and flanges) from cycling

-tihermally, the water level in each OTSG may rise above the low level setpoint

.This.

~

will:be acceptable.

9.5.3.5 .When tube-to-shell AT reaches 140 F, decrease the a

.cooldown rate to maintain the tube-to-shell AT'at 140 F.

STR-WhenRCSTh,4350Fstop'reducingsteamgenerator

. pressure and begin a gradual repressurization and-refilling of each steam generator.

29 5.4 'All necessary OTSG tube leakage monitoring data-has been

.' -recorded ~and attached:to this procedure.- '

o ,

Section 9.5 Accomplished: SAT UNSAT S'ignature- Date b

9.6- Third' Plant Heatup . to 532 F,: 2155 ' ps'ig 9.6.1 Initiate the PPMP computer data collection (Enclosure 7) every-

. . ten (10) minutes prior-to initiation of the heatup and program 4

to collect data-every ten (10) minutes. The time should also be recorded when either RC pumps or Decay Heat pumps are turned-

-on or off. The data should be taken throughout the heatup

until hot standby ~ conditions are reached ar< at the completion

~

. of the heatup print out the data collected. Mark up the computer printouts with the following: St'ep number, TP number, initials, date, page number, and attach as part of Enclosure 7.

. TMI UNIT 1

, TP 600/2 i ,

Effective Page STR-1 Page 17

1102-11 a' ~ **

  • Revision 37
14. Manning Requirements shall be in compliance with-

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- Administrative Procedure 1029.

13. The boron requirements necessary to maintain the required shutdown margin shall be considered to insure that an adequate *
baron concentration will be maintained prior to placing any Makeup and Purification demineralizer in service. -

3.0 - 0PERATING PROCEDURE 3.1 Prerequisites' for Cooldown (Indicate satisfactory completion of steps below by initiating next to each step and sign name at end of applicable section).

1. Reactor coolant at 1 percent aK/K S/D boron concentration secured (three TP 600/2

' at 70*F and with one reactor coolant pumpjrunning)p,,.

j STR

  • Sect. 9.3 1 44ep and necessary safety rods withdrawn. only i
2. Degassing of reactor coolant system is complete in accordance with plant shutdown as per Operating Procedure 1102-10. If additional degas is needed during cooldown refer to degas Operating Procedure 1102-12.
3. Heat dissipatio,n using steam generators is in progress using turbine bypass valves.
4. Sufficient boric acid solution and reactor grade water  !

\

av.ailable~ to makeup for reactor coolant system during l

. cooldown. Required final boron concentration determined TMI UNIT 1 TP 600/2 l Enclosure 4, 9/23 l 8.0 Effective Page STR-y Page 87 i p .

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