ML20126B997

Rev STR-2 to Procedure Tp 600/4, RCS H2O2 Cleanup. Supporting Documentation Encl

ML20126B997
Person / Time
Site:	Crane
Issue date:	03/28/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20126B295	List: 05000289/LER-1981-013, Forwards LER 81-013/01T-0 Re Leaking Found in Steam Generators.Event Reportable Per Tech Spec 6.9.2.A(3). Supporting Documentation Encl IA-84-897, Forwards Safety Evaluation Re Increase in once-through Steam Generator Primary to Secondary Leakage Rate,Per NUREG-1019 & Suppl 1.Rate Acceptable ML20126B293 ML20126B302 ML20126B316 ML20126B321 ML20126B337 ML20126B342 ML20126B358 ML20126B376 ML20126B390 ML20126B412 ML20126B435 ML20126B467 ML20126B475 ML20126B493 ML20126B504 ML20126B513 ML20126B520 ML20126B560 ML20126B563 ML20126B585 ML20126B592 ML20126B610 ML20126B618 ML20126B623 ML20126B635 ML20126B639 ML20126B648 ML20126B650 ML20126B656 ML20126B658 ML20126B667 ML20126B670 ML20126B684 ML20126B688 ML20126B701 ML20126B708 ML20126B716 ML20126B719 ML20126B739 ML20126B751 ML20126B758 ML20126B766 ML20126B784 ML20126B797 ML20126B806 ML20126B825 ML20126B831 ML20126B879 ... further results
References
FOIA-84-897 TP-600-4-REV-ST, NUDOCS 8506140276
Download: ML20126B997 (192)

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THREE MILE ISLAND UNIT 1

't CLASS 1

NUMBER CATECORY A

TP 600/4 RCS H 022 CLEANUP MT'C 600.5.1.9 1

4 REVISION STR-2

'I Cognizant Engineer _

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U-RESPONSi3'LE TECHNICAL REVIEWER:

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IMPLEMENTATION APPROVAL:

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APPROVAL OF TEST RESULTS:

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2 STR-1 32 STR-2 62 0

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10 STR-2 404 -m 0

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11 STR-1 41 0

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17 STR-1 47 0

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23 STR-1 53 0

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PAGE EFFECTIVE PAGE PAGE EFFECTIVE PAGE PAGE

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91 0

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95 0

96 0

97 0

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_99 STR-1'

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- A 1.0 PURPOSE

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1.1 The purpose of this procedure is to provide the controlling sequence-2 for heating.up the Reactor Coolant System, lining up the Makeup and Purification and Decay Heat Removal Systems and chemical cleaning these systems to remove residual sulphur.

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1.2 The' general approach for cleaning is as follows:

1.2.1 The first step in this process is to provide a protective 0

environment for the plant systems as quickly as possible as the plant is filled with borated water. To accomplish this,.

LiOH and NH 0H will be added with the fill water.

4 1.2.2 Next, the system will be heated to about 130*F using the Reactor Coolant Pumps.

System temperature will be controlled using the Decay Heat Removal System. The pressurizer vapor space will be filled with N Pressurized to 307 8 psig.

2 4*7o8orit.AdcI Then, as soon as possible, NH 0H will be added via L4CH 4

37P B3-03y STR-1 Mix Tank per vr 11u*-*?B to adjust the pH to 8-8.5.

Y With'this chemistry con' trol there should be minimum corrosion even if corrosive sulphur. forms are still present. To avoid po-tential problems with corrosion in the pressurizer itself, the i

heaters will not be used.

I H /]{ll TA^lk pll SMALL net" GXeCt~b STR-l 9 7. Feu owtuj Min oH Acorrion.

TMI UNIT 1 TP 600/4 0 E 091 m m COM' Effective Page STR-1 Page 1 DUPUCATE PAGE O

4

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. l. 0 PURPOSE (Cont'd.)'

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1.2.3 After temperature and pressure are stabilized, the introduction of H 0 will begin via 4% Boric Acid Mix Tank (CA-T8), see STR-:

22

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Encl. 6.

The-peroxide will be added to keep the concentrations

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between 15 and 25 p'pm.

It is expected that the peroxide will decompose at a rate of about 5-10 ppm per hour initially.

It may slow down as process, proceeds. When the decomposition takes

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place, oxygen will be formed. This will also assist in the sulphur oxidation process, although it is not as effective as peroxide.

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During the period in which peroxide is maintained in the RCS, 1.2.4 various pumps and valves will be manipulated to get the cleaning solution into as much of the RCS Purification System and Makeup System as possible.

Filters in the Makeup and Purification-System will be switched periodically and the pressurizer spray will be activated on a shift basis. Since the spray operation will introduce. considerable dissolved gas into the RCS, this

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operation will be limited by the total gas limit. The total gas limit is chosen to protect the Reactor Coolant. Pumps from cavitation damage during high total gas operation.

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TMI UNIT 1 DW3 TAGE_

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1.0 PURPOSE (Cont'd.')

l.2.5

'The c'eaning process will-be monitored by periodic analysis of Coolant System sulfate concentration.

It is possible that because of the amount of oxidation and exposure to 4

various flushes,'very little total sulphur will be picked up.

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However, to ensure that most all sulphur will be oxidized and removed, the peroxide treatment will be for a minimum of 400' hours..

1.2.6 During the process, as mentioned previously, gas will-be Eenerated by the decomposition of peroxide and picked up by operation ~of the pressurizer spray. The waste gas will be removed through the normal Vaste Gas Handling System.

Durir.g this operation, the gases in the system will be n'itro-gen and oxygen and a potentially explosive mixture will never exist..To assure that no hydrogen is in the system, p

itwilkbeflushedwithN at the start.of_the cleaning process 2

and the monitors will be used to assure that H is 2

always < 1%, as the process is carried ou't.

TMI UNIT 1 TP 600/4 OFFICIAL 3TRTD COPY sffective Pese 0 DUPUCATE PAGE O

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%.1 1.0' PURPOSE (Cont'd.-)

1.2.7

=At the termination of the t'est, the system will be returned to normal cold shutdown conditions. The 4

oxygen and nitrogen will be removed by degassing in the-makeup tank until 0 is less than 15 cc/Kg and total 2

gas is less than 100 cc/Kg.

Sulfates will be removed by ion exchange through a special anion ~ resin bed in the-

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purification demineralizers. Only o'ne bed of anion resin should be required to remove the sulfates. Ammonia will be removed by ion exchange through special cation beds that will be installed in the purification demineralizers.

It will require several bed changes to reduce ammonia to less than SE' 4W ppm. The final bed will be the one normally used during plant operations.

v.

1.2.8 The Waste Gas System will be purged with N -until oxygen 2

is again less than.1%.

At this point, the plant will be in a condition where it may be started up using normal chemistry control procedures.

TMI UNIT 1 TP 600/4

' OFFICIAL rum COPY sffective Page O DUPUCATE PAGE b

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2. 0. REFERENCES b 2.1 See references on revised OP 1102-1, Plant Heatup to 525*F,.

i-hb.2 Decay Heat Removal System,'OP 1104-4, Rev.

2.3 Mak.eup and Purification System,.OP 1104-2, Rev.

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'RCS H 0 Chemistry Specification. 88V' O 22

% h 2.5" OTSG Operation during RCS Cleanup.,' memo ChE 83-356 dated 05/02/83 J. R. Sipp.

t-I TMI UNIT 1 QQTCg 'gy m yyy TP 600/4 WA Effective Page O CUPUCATE PAGE Q

age 5 m

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- TIME REQUIRED-

.. 3.1- ' Ten (10) men Seventy (70) shifts.

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4 OFFICIAL FIRin COPY 6 70 %

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4.0 PREREQUISITES 4.1 Prerequisite Tests

4. l'.1 Not applicable.

Signature d M Date d U 4.2 Construction Completion Status

'4.2.1 Not applicable.

Signature OM U

Date [-3Y b 4.3 Environmental Conditions

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4.3.1 Not applicable.

Signature M M

'Date [-Z 9-h3 4.4 Technical Specifications 4.4.1 Tech Spec Change Request TSCR# 121 necessary to

?hange chemistry and operating conditions submitted and apprdved by the NRC.

Signature [

Date d"2Y-[f 4.4.2 Safety Evaluation of TMI-l Reactor Coolant System Cleaning Topical Report 10 ap roved prior to commencing cleanup.

Signature # M eI' Date [-2. h b TMI UNIT 1 OFFICIAL FMD COPY Erll[ePageo CUPUCATE PAGE O

5.0 TEST EQUIPMENT

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5.1 Not applicable.

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- OFFICIAL FIRIB COPY TP 600/4 Effective Page 0 O

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6.0 LIMITATIONS'AND PRECAUTIONS 6.1 During chemical additions appropriate clothing andIrespiratory

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. equipment shall be worn and the area well ventilated.

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6.2 Pressurizer heater breakers racked out and tagged open.

6.3 0bserve all limitations and precautions of referenced and enclosed s

procedures.

6.4 Notify Chemistry and Task 9 Chemist prior to shifting major components

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or lineups out of normal procedure.

If plant problems require shifting

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components prior to notifying Chemistry and Task 9 Chemist notification shall be made as soon as possible after shifting lineup.

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6.5 During Reactor Coolant Pump shifting, RCS pressure should be monitored to insure that the pressure is maintained within the curves on Figure 3 of Enclosure'3.

-6.6

' Access to RC Drain Tank room should be limited in the event that rapid depressurization is required since the rupture disc may rupture.

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TMI UNIT 1 TP 600/4 OFFICIAL FMn COPY Effective Page O Page 9 O

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6.0 LIMITATIONS'AND PaECAUTIONS (Cont'd.)

1. r (6.7 During chemical addition if a crud: burst is detected, cleanup will be

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through the~RCET.using OP 1104-29A.

Do not use precoat filters on

'ammoniated RCS water unless special precoat has been approved by Plant

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Chemist'. '

o 6.8 During RCS Cleanup if a' crud burst occurs or chemistry is out'of specifications CRD motion.shall be ceased until crud levelsor

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Cleanup will be I'

chemistry.are back into acceptable levels.

accomplished by letting down to a RCBT and making up from a clean

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RCB*t.

(OP-1104-29A)- Acceptabla crud levels will be determined E. -

by 0 & M personnel.

1.

6.9 During the RCS Cleanup process the following chemistry parameters f

l shall be observed:

6.9.1 The pH shall not exceed 9.4 at any time due to possible.

'RC pump seal damage.

6.9.2 The chloride concentration shall not exceed 0.4 ppm and STR-2 fluoride concentration shall not exceed-0.1 ppm.

6.9:3 The peroxide' concentration shall not exceed 25 ppm.

6.9.4 Boron concentration shall be between 1800-2300 ppm.

6.9.5: Lithium concentration shall.be between 1.8-2.2. ppm.

6.9.6 pH shall be maintained above 8.0.

6.10 Prior to the initial rod movements after N2 pressurization the drive mechanism shall have been vented.

6.11 Do not, shut off valves in lines which contain or may contain H0 at. greater than 1" concentration. 4/s7W e4T' [EL 16)#

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TMI UNIT 1 Q %*

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WF'.JCATE PAGE _

Page 10 h

4 LIMITATIONS'AND PRECAUTIONS'(Cont'd.)

6.0

_6.12.The control rods sho'ld not be intentionally. tripped'except in u

. emergency. conditions or as the Shift Supervisor's may deem necessary.-

7 j6.13 Once H 0 l

18 P aced in the 4% Boric Acid Mix T.ank noiother chemical STR-1 22

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should be introduce'd'into it until end of'the test and the tank and lines have been. flushed. Lithium and ammonia should be added via the' LiOH mix tanu. CF-T-I>4 we'- shouLD Q d-MOHIMO

- - fBt/0Decs%Ly fene Le e PMr CF-V-zsA comes M12. noemw.

0 6.14. If total gas. concentration exceeds 175 cc/Kg, spray in the pressurizer 1

and H 0 additions.should be halted and letdown flow maximized.

22 If total gas exceeds 200 cc/Kg the RC pumps should be shut off, the spray and H 0 addition secured, letdown flow maximized and no-22 r -

further CRD movement out of. core should be allcwed... Normal operation may be reinitiated when total gas reaches 150 cc/Kg following

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operation of one RC pump.

6.15 If pH drops below 8.0, ammonia additions should be started'or in,

creased.

6.16 If pH rises above 9.0 ammonia and H 0 additions should be 22 terminated and feed and bleed established.

If pH rises above 9.2, seal injection flow should be established from a RCBT or other source with pH-less~ than 9.2.

The Task 9 advisor should be contacted for further direction on NH removal.

3 TMI UNIT 1 m ;

TP 600/4

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6.0 LIMITATIONS AND' PRECAUTIONS (Cont'd.)

E *10 6.17 During Rc rump shifting do not attempt to restart a stopped RCP

~ until-40 minutes after stopping.

Do not exceed.150*C limit for motor stator temperature. During starting process plot stator t'emperature every 5 minutes until trend is established and then every 15 minutes until temperature is stabilized.

6.18 Peroxide l'evels must be less than 10 ppm H2 2 prior to any ion exchange operation (WDL-F-1A/B).

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6.19 When any sample taken from the OTSG (upper tube sheet or recirc sample point) reaches 100 ppb oxygen, the recirc system will br isolated on the OTSG and the system pressurized using the alternate N header. Ensure OTSG shell temperatures are greater than 100*F 2

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prior to exceeding OTSG secondary side pressure of 200 psig 6~b (T.S. 3.1.2.2). Jee 5 7-P _J-gs-oo13 6.20 After the steam generator is pressurized to-Reactor Coolant System pressure, the generator will be sampled at the upper tube sheet sample point once per shift and analyzed for dissolved oxygen. When the dissolved oxygen reaches 150 ppb from either generator, the RCS hb cleaning process will be stopped. $st $7 8 _ /-73-d_0%

E-l' l 2I & V"M9 NdN"'M '70 RCM~ Nis w s'a'Y wq CARG~ SM-oseL D d6 % 'f3 VfW.fL6wLy 70 &WWf AC3 PXWC ae tt~

is M4/af % #b mt ACfof*M9 W, TMI UNIT 1 TP 600/4' Effective Page 0 OFFICIAL FWD COPY rage 12 curuan euw o

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7.0 PLANT STATUS

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_7.1_

The plant shall be in a condition to heat up to specified pressut'.2

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and' temperature.

Signature' M M Date dr78-[.3 t

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TMI CNIT 1 TP 600/4 OFFICIAL FM.n COPY

• • ctivePageO Pat S 12 CUPUCATE PAGE O

8.0 PREREQUISITE SYSTEM CONDITIONS 8.1

-All systems shall be operable and available as discussed in Enclosure (3) and 1 ned up accordingly.

Signature M M Date d')O' htc feet of anion resin and Mmffeet E-l/.

8.2 of cation resin on site and available for removal of sulphur and-ammonia after RCS clean p is completed.

d '3d' b Signature O Date 8.3 The following chemicals onsite and available for RCS Cleanup according to Chemical specifications:

l 2000 Gals. Hydrogen Peroxide 670 Gals. Ammonium Hydroxide 35 Pounds ithium Hydroxide Signature Date de 3d' 8.4 Sufficient filters on site and available to change the following filters as necessary:

MU-F-1A/B - 8 (New filters installed prior to Cleanup Process)

MU-F-2A/B - 12 (New filters installed prior to Cleanup Process)

MU-F-4A/B - 30 Signature M Date

['8 Y-8.5 Sufficient shielded fil r storage / disposal casks or containers available.

Signature M I

[-29-b Date TMI UNIT 1 TP 600/4 OFFICIAL FMD COPY Effective Page O Page 1*

DUPUCATE PAGE 9.

8.0 PREREQUISITE SYSTEM CONDITIONS (Cont'd.)

8.6 14 Beds of spent resin storage capacity for the normal as well as special anion and cat n resins used during the RCS Cleanup process.

- (.,.

' Signature N

_I.

Date d 'db 7

r 8.7 Waste Gas Disposal System o]5erable, avail'able and purged with N to 2

.less than 0.5% H ' Tw (2) H analyzers installed and operable.-

2 2

^

Signature M M d-Ekb O

Date T &

8.8 The_ Makeup Tank, MU-T, blanketed with nitrogen.

Signature O M M JJ Date [*I6-(

v 8.9 Plant Chemistry Department personnel, equipment, and procedures are available to support e RCS H 0 cleaning evolution.

22 Signature j Date_ d "20 - U 8.10 Prior to ad'dition of H 0, MU-K-1A will be changed to special anion 22 resin bed and MU-K-1B ill be changed to special cation resin bed.

Signature M M _

[-ZT b Date 8.11 OTSG Tube Sampling modification installed prior to commencing Cleanup.

Signature M M Date d'N-8.12 NI-V-ll8 removed and second regulating valve installed in Nitrogen

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System.

Both regulating valves reset to limit Nitrogen pressure l

in RCS to less t,han 4 5 psig.

Signature.2 Date_d-Z9e[3 OFFICIAL FMD COPY

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O' Effective Page 0 DUPUCATE PAGE r

Page 15 J

f 8.0 PREREQUISITE SYSIEM 'ONDITIONS (Cont'd.)

C 8.13 OTSG's in full wet layup per 1106-16 and secondary water chemistry in spec.

Signature 7, Date d'80' T

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.8.14 Temporary OTSG N Pressurization System and Upper OTSG Tube 2

Sheet Sampling System installed to support RCS cleaning.

Signature M M Date

'88" 8.15 Establish RCDT level at approximately 25% on RCDT level indicator in Control Room to all w sufficient air volume for N2 "*"ti"8'

[d'b Signature M 2

Date A

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8.16 Pressurize OTSG Secondary Side to between 10-75 psig per Reference 2.5 prior to Step 9.2.

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Signature M Date [- Z Ye [ I g, j$

8.17 RCBI filled with acceptable RCS quality fill water with NH 0H addid 4

to elevate pH from 8.0 to 8.5.

Signature 2 M _,

Date 4-3d-[I TMI UNIT 1 TP 600/4 Effective Page 0 OFFICIAL FWD COPY page 16 n

DUPUCATE PAGE L

.f

.-9.0L TEST' METHOD 2

9.l' Plant Heatup and System Line Up T)Sf

.1 Fill and vent the RCS using the marked'up version of.OP 1102-1,

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' *.y c T)s4 C9.1.1.1 During filling add LiOH per OP 1104-4 7B to raise STR-j concentration to 1.8-2.2 ppm. Record on Data Sheet 10.1..

CAUTION: DURING HEATU? TO 130*F AND CLEANUP PROCESS AT 307 PSIC, RAPID DEPRESSURIZATION TO RCDT MAY CAUSE RUPTURE DISC TO BLOW.

1.2 Commence heating the plant to 130' 5'F and 307 2 8 psig using., keeping in mind the components required in Step 9.1.5.

When seal injection filter usage has stabilized proceed with chemical addition in accordance with Step 9.1.3 (See Step 6.7).

gg g d 9.1.3 Add NH 0H to maintain pH to 8-8.5.

This addition will be 4

STP-I-13-Off done by using.C" 1104-475.

Record on Data Sheet 10.1.

STR-1 ne Ah - 9.1.4 Commence chemistry sampling in accordance with tables in data sheets 10.2 and record data in 10.2.

9.1.5 When the plant is at temperature and pressure, perform the following initial lineup of the Reactor Coolant System, Decay Heat Removal System and the Makeup and Purification System and record on Data Sheets.

%b

/D Mut NOTES:

(1) fW The spray valve, RC-V-1,',will be opened five %

+ Lune per ol&l+

V minutes per shift. Operation of the spray valve 5-93 E'n] h will be recorded on Data Sheet 10.3.

Q OFFICIAL FTRT.o God iT TMI UNIT 1 6,S DUPUCATE PAGE h

TP 600/4

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9.0 TEST METHOD (Cont'd.')

(2) When DH-P-1A is in service RC-V-4 (Auxiliary Sprcy l

j Valve) will be opened for five-(5) minutes per shift.

//

Do not open RC-V-4 while normal spray valve is opened.

Y,.

f Operation of the Auxiliary Spray Valve will be re-corded on Data Sheet 10.9.

i CAUTION:

IF TOTAL CAS CONCENTRATION EXCEEDS 175 cc/Kg SPRAY INTO PRESSURIZER SHALL BE STOPPED.

/M N '

9.1.5.i E-/h

'I Reactor Coolant System - RC-P-1A AC P-s 6 h df RC " 1C in operation. Alternate with R C.~ P-I C. er~ R C.-t-lO m 4E.- 22.1

[

RG-r-lL/D every W,and record on-S~

Y 5%} a Sh t }0.3 p

g p,gg ggg 3.yop gwG Rd W STAM THe n:.

wMar c P ses T M 4 r 4 0d e.

IF TOTAL GAS CONCENTitATION EXCEfDS 200 cc/Kg THE RCP's CAUTION:

g 8ce#r M 8"'8 OF SHOULD BE SHUT OFF. NOR M L OPERATIONS SHALL NOT CONTINUE p aus~y AT '7WA* 56Me~

TW Y.

UNTIL TOTAL GAS IS 6 150 cc/Kg.

_ CAUTION:

IF pH RISES ABOVE 9.2 THE RCP SEAL INJECTION WATER SOURCE OF LESS THAN pH OF 9.2 SHALL BE USED (RCBT) UNTIL THE pH IS IN SPEC.

9.1.5.2 Decay Heat Removal System - DH-P-1A and DH-C-1A in operation. 'Alernate with l

D11-P-1B and DH-C-1B every 7 days and re'ord c

on Data Sheet 10.'4.

l TMI UNIT 1 TP 600/4 Effective Page 0 OFFICIAL FTRin COPY Page 18 oueucceeras O

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9.0 TEST METHOD (Cont'd.)

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9.1.5.3 Makeup and Purification System.

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:y NOTE: Makeup Filters MU-F1,A/B, MU-F-2,A/B fy 1-

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and MU-F-4A/B will require several

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'5'

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changeouts throughout the RCS clean--

E up process, therefore it will only

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be necessary to equ lize the time

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each are on line and log each shift and changeout on Data Sheet 10.6.

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' h 5.3.1 Open and lock open -

? f qy 8 MUg){g 2A ///* MU-Vj7B

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, M Mu-v-72B /gq-X-J6A E 1

1. fM,Vg3 E-/f l

MU-V-72C d MU g-J4A

,-pj9A E-/f

'T MU-V-74B /

+ $9B E-/1 d

MU,-p 68A f

MU-V-74C M MU-V;;pA //f, MU-V-6,8B

'v These valves will remain in 7

y3 this position throughout RCS 7-7'T3 Cleanup process.

, r-es M~

Tj=

a

:-g

- 9 '*

e g

!F TMI UNIT 1

1.. f TP.600/4

?3 OFFICIAL FWD COPY g'*%vePage0

,5

'O DUPUCATE PAGE

3

1

/

9.0 TEST METHOD (Cont'd.)

9.1.5.3.2 Close or verify closed -

kb MU-V-14A s

N -V-14B

@ MU-V-41 0

These valves shall not be opened through-out RCS Cleanup unless directed by Shift Supervisor.

D 9.1.5.3.3 Makeup and Purification System "A" train E-n E MU-P-1A D MU-C-1A Block Orifice - on line at all times during RCS Cleanup.

N MU-V opened / throttled M MU-V-70A - opened bA MU-V-70B - closed M d MU-C-2A K

V201 - cracked open for one (1) hour during chemical addition, circula-tion and chemical removal with MU-FlK or 1B on line. Record operation,on Data She.et 10.10'.

~

TMI UNIT 1 TP 600/4 OFFICIAL FIELD CO-- f cf1ective Page O r

O DUPUCATE PAGE (M.

m n-

9 9.0 TEST METHOD (Cont'd.)

j.

/ M.

9.1.5.3.4 Alternate Makeup.and Purification-lineup-f

['

with A, B and C trains every 7 days and record on Data Sheet 10.5.

)

M 9.1.6 Makeup and Purification System Lineup kM 9.1.6.1 Makeup and Purification System - B Train hIA/ _ MU-P-1B D

MU-C-1B MU-V closed N MU-V-109A - opened M h_ MU-V-109B - opened

~

-V opened / throttled such that dcwnstream pressure g

does not exceed 150 psig N

MU-V-201 - closed

@ b MU-V-70A - opened MU-V-70B - closed p k MU-C-2B gjfpf MU-V-110 - cracked open for one (1) hour during chemical addition, circulation and chemical I

removal with MU-F-2A or 2B on line.

Record operation on Data Sheet 10.10.

MU-V cracked open for one (1) hour during chem-ical addition, circulation and chemical removal. Record data on Data Sheet 10.10.

TMI UNIT 1 TP.600/4 Effective Page 0 OFFICIAL FIFID COPY Page 21 n

DUPUCATE PAGE v

9.0.

TEST METHOD (Cont'd.)

M 9.1.7 Makeup and Purification System Lineup

-[

9.1.7.1 Makeup and Purification "C" Train.

>.s MU-P-lc MM MU-C-1A M

MU-V-5-openeb/ throttled

- M M ' MU-V-109A - c.leeed -

o NWek f

MN

__MU-V-109B - r'ared epcsecl

/YN MU-V dieeed OpcNeeA b F.

MU-C-2A CAUTION: DO NOT ALLOW-MORE THAN A MINIMAL FLOW BECAUSE OF POSSIBLE RCP SEAL DAMAGE.

MU-V cracked open for one (1) hour during chemical addition and cracked open for one (1) hour during circulation late in process and cracked open for one (1) hour during chemical removal. Record operation on Data Sheet'10.10.

Section 9.1 Completed Sat.

)(

Unsat.

Signature O. k* -

b Date 7-2f-[3 TMI UNIT 1 TP 600/4 CFF_TCIAL FIFID COPY ES'E""'"**

DUPUCATE PAGE O

r m..

gg

'E-

,6

9. 0. TEST METHOD,(Cont'd.)~

4

?

9.2 : Hydrogen Peroxide. addition and clean up

~

M b.'2.1 Line up the 4%' Boric Acid'Hix Tank to add H 0 to the

+., -

22 Reactor Coolant System per Enclosure 6.

STR-1~

z

.4 v

4 g2.2':

Add.the first batch of H 0.to the RCS. Record. data on

~

22 Data.Sheetc10.'l.

y:.

n CAUTIONi IF_DURING H 0 ADDITION A CRUD _ BURST OCCURS CEASE H 0 22 22.

~

~

f*_

ADDITION UNTIL THE RCS CAN BE CLEANED UP TO ACCEPTABLE

. LEVELS' PRIOR TO' RESUMING H 02 2. ADDITIONS..(See Step 6.7)'

9.2.3 Continue to add H 0 to the RCS~until concentration.is in the-22 range of 15-25 ppm as d'etermined by chemistry sampling. Record y

data on D'ata Sheet 10.1.

N 2.4' When chemistry is stabilized in specifications vent.all CRDM's.

~

.per 1103-2.

9.2.5 When all-CRDM's have been vented, commence control rod cycling og

. within the limits of Encl. ' 5. ~ Do not move more than one.(1)T group of rods.at a time..All rods will be withdrawn to full out position then fully. inserted on a daily basis.. Log' rod.

1

.7 group movements on Data Sheet 10.8.

CAUTION:

IF A CRUD BURST OR CHEMISTRY IS OUT OF SPECIFICATION. I.E...

HIGH CHLORIDES OR FLOlilDES, CEASE OUT ROD MOTION UNTIL CRUD OR.

CHEMISTRY IS BACK TO ACCEPTABLE LEVELS.

l

_ CAUTION:

IF TOTAL GAS CONCENTRATION EXCEEDS 190 cc/Kg ALL ROD GR,OUPS SHOULD BE SLOWLY INSERTED. FURTHER ROD MOVEMENT SHALL NOT BE.I INITIATEDUNTILCONCENTRATIONREACHESf150cc/Kg.

TMI UNIT'l m-M D 'a % N d.

TP 600/4'

- ~. _..

.i.) ',V I I va V

Effective Page STR-1 n

Page 23 CU. UCATi ?AG2 a

j l

y z

i 9.0 TEST METHOD (Cont'd.')

N b.2.6 Commence sampling the RCS using normal sample points in accordance with the requirements of Data Sheet 10-2 or as directed by the Task 9 Chemist. Record analysis of samples

.m, on Data Sheet 10.2.

Completed data sheets shall be returned l

/

h to.the Control Room for inclusion in Section 10 for permanent

. records.

9.2.7

' Inform Task 9 Chemist and remove OTSG tube samples #1 and #2

~

for analysis at approximately 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of H 02 2 "l**"i"8*

/Thk9.2.8 Chemical additions at the direction of the Task 9 representative may have to be made throughout the cleanup process and all data shall be recorded on Data Sheet 10.1.

Completed data sheets shall be returned to Control Room for inclusion in Section 10 for permanent records.

i f/,e 7 > +-O l M 9.2.9 Inform Task 9 Chemist and remove OTSG tube samples #3 and'#4 at approximately 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> of H 0

1. 1**"i"8*

~

22 Ob05 N0 i(

7-O - O cleanupprocesswhendirec/ptodosoby P"M S t L 9.2.10 Terminate the H 0 te y/

23 the Task 9 H O RCS Cleaning Task Group representative.

2 Task 9 Representative h.

2 a n tS m o Date 7-2343

~

n~

Section 9.2 Completed Sat.

M Unsat.

Signature O-

./

Date 7-24-83 TMI UNIT 1 OFFICIAL FIELD COPY H,$('epaye0 O

DUPUCATE PAGE d

page 24

~

9.0 TEST METHOD (Cont.d.)

y, 9.3

.. Removal of SO from RCS 4

/-. M 9.3.1 Prerequisite 8.10 has been completed and MU-K-1A with

g YL;

.Jp;

~~

the special anion resin is ready to be placed in service 4

'per OP 1104-2. Record resin change on Data Sheet 10.7.

-;fs.

,t

.p

.3.2 Line up the Makeup and Purification System flow through MU-K-1A to remove SO.

Continue to recirc through this 4

demineralizer until SO levels are determined acceptable by 4

the Task 9 H 0 RCS Cleanup representative.

Shift the

~

22 lineup of'the RCS, Decay Heat Removal System and the Makeup' and Purification System to ensure all trains have seen the SO Cleanup flow paths. DuringthiscleanupthekCP'sarenot 4

required to be switched. Lineup changes will be required more frequently due to short time for SO removal.

4 Date7!sI!P3 Task 9 Representative vv y

Section 9.3 Completed Sat.

Unsat.

Signature k

J[h7 Date E N-/97.3 -

TMI UNIT 1 TP.600/4 Effective Page 0 OFFICIAL FIELD COPY Page 2S f:N DUPUCATE PAGE U

w-m

9.0 TEST METHOD (Cont'd.)

9.4 Removal of Ammonia from the RCS.

/ 9.4.1 Replace the special anion resin in MU-K-1A with the special f

I cation resin per OP 1104-2 and record resin change on.

I Data Sheet 10.7.

Changeout will be in accordance with OP 1104-540 9.4.2 Lineup the Makeup and Purification System flow through MU-K-1B

' and continue recirc until resin is depleted or A P limit is reached. Depletion will be determined by chemistry.

M

.4.3 Shift the lineup of the RCS, Decay Heat Removal System and the Makeup and Purification System to ensure all trains have seen the ammonia cleanup flow paths. The RCP's need not be switched during this period. Line up changes will be more frequent due to duration of ammonia removal.

/7//

9.4.4 Shift lineup to flow through MU-K-1A and continue circulation as stated in Step 9.4.2.

Record demineralizer shifts and changeouts on Data Sheet 10.7.

M 9.4.5, Continue replacement and shifting of MU-K-1A and MU-K-1B until the ammonia levels are determined acceptable by the Task 9 H 0 RCS Cleanup representative.

22 h!f/fR Task 9 Representat ate u

U Section 9.4 Completed Sat.

Unsat._

Signature

/h

._J!L -

Date d/'!9 3 ((N I

~

j'

//

TMI UNIT 1 TP 600/4

~ OFFICIAL FIELD COPY Effective Page 0 g

Page 26 DUPUCATE PAGE l_)

r.

I

, 9.0 TEST METHOD (Cont'd.)

9.5 Return Plant to Normal ~ Cold Shutdown condition.

//)fA.f 9:5.1 Replace the resins in MU-K-1A and MU-K-1B with normal

l].

' operating resin in accordance with OP 1104-54.

17f/M 9.5.2 Vent all CRDM's' per OP 1103-2 for ten (10) minutes.

M 9.5.3 Slowly vent the primary system to the RCDT via RC-V-28 to reduce N Pressure in a controlled manner and retutTt the plant 2

to cold shutdown per OP 1102-11 starting with Step 29.'

9.5.4 Inform Task 9 Chemist and remove OTSG Sample rig and re-maining tube samples.

/[)/

9.5.5 Remove temporary N regulating valve and reinstall NI-V-ll8 2

relief valve.

9.5.6 Remove temporary OTSG N Pressurization System and OTSG 2

Upper Tube Sheet Sampling System.

f 9.C'l Res*toVE N 0z. Acornount-Tu6tes (fou.euwe Deww WTot FlusoD 2

Beructu CF-V-27A A~D (C-V-/03 9 Section 9.5 Completed Sat.

Unsat.

Signature M A

Date

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' PARAMETERS AND LIMITS DURING THE FINAL ADJUSTMENTS PHASE

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. Parameter Range-Frecuency

' pH 8.0-8.5.

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DATA SHEET' 10.3 REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET T INIT TIME INI RCP_ RC-P- %lC_ ~ RC-P-1B/D [ RC-P-1A/C \\ / 'RC-P-1B/D [ RC-P-1A/C RC-P-1B/D [ q RC-P-1A/C / RC-P-1B/D ,[ \\ RC-P-1A/C / \\ RC-P-1B/D [ \\ RC-P-N N RC-P-1B/D SPRAY VALVE RC-V-1 TIME /DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS f Af,/C 133 ?) i O C 7 *1'8 n }3 - - h .11 t o ~2-14 T3 w kt40 '7-3 1 M />u - h Of fo 7-t$ O N 07 LO 7*2 T 4 > f--O k 1 eS3o7dt3 0 6 ,*2 4 A > W G JfD0 7 J+fS % fic '? 2 4 -f t k \\ 19 in 3 *2+E] tw sq r t 2 -kt h w_ 3 s'c'd ')-2 9 D M .0 0 m ?*3tt -[*! n t, o r> 7 -3 r f5 M A/ / / ?.5 9 /3 l 1 1 w & / D n n--. - A1e d -).1-rn n m01-W 45 W 2'525 7-2 Ys3 % MT7-ts Cfb oolo 7-2C D l'9 p stof '7-L( N 0\\td 7-LT 1 W \\ O 2n( ~)-t ( 0 2LO 7-15 faf.,7 o Soo 7-lf M o 3to 7-t 31 Q D({no1~I.f 6 4 IO 7~ W l TMI UNIT 1 TP 600/4 Effective Page 0 C..._,- -- -naa ::----.s L Pas. s03 b CUFJCATE FAGE n-I- .,....,_.s___,_ ..mm,m., ,.,._,..,-,,,,em. _ mw n, w mv

C ( DATA SHEET 10.3' REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET RCP m RC-P-1AIC'N RC-P-1B/D N / RC-P-1A/C RC-P-1B/D \\/ RC-P-1A/C . \\ RC-P-1B/D / RC-P-1A/C RC-P-1B/D RC-P-1A/C RC-P-1B/D RC-P-Rb-1B/D SPRAY VALVE RC-V-1 TIME /DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS o Geo 2f g_6 oito 7-2.s# M 0L00

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C DATA SHEET 10.3 REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET OF MTM RCP DATE ATE ATE ATE REMARKS RC=NIA/C' RC-P-1B/D [ RC-P-1A/C \\ j RC-P-1B/D \\. [ RC-P-1A/C RC-P-1B/D [ x RC-P-1A/C / RC-P-1B/D \\ RC-P-1A/C / \\ RC-P-1B/D \\ RC RC-P-1B/D SPRAY VALVE RC-V-1 TIME /DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS uoo k -r>e. 2o101H n 2 Iou NS 7tQb %< ( /61to llo n $ fs W04 i n l so ? '/1 b 0No 7-24 f_es E,s4ev $ /,J r,.o ( o 7 02.50 7 24 b n 2.M 7-l4 N o*33o y -2S-b o S Y c 7-Z'- h 64'1o 7-2 4 h o y 4 o 7 - 2. 4 ni'b - 7 t G (-() of4 o 7-26 M oc3o-7/r & 12 oGTo 7-2 6 o7 30 7/t6 M o74o 7/2/, 6 e Bw

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DATA SHEET 10.3' REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET 1 RCP REMARKS RC-P W y RC-P-1B/D RC-P-1A/C \\ RC-P-1B/D \\ / RC-P-1A/C RC-P-1B/D RC-P-1A/C ~ RC-P-1B/D \\ RC-P-1A/C RC-P-1B/D \\ RC-P-M .e. RCh-1B/D SPRAY VALVE RC-V-1 TIME /DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS 14 79 ~% c. Jkt. INO %L 4 n3e %L >$4 19 to 'h.C 8 it se h b I2 to ~'/2 l. h /43o 46 r[J /1 y o ~'/2. 6 N 7 ?/ L & 20 40 'A c & so sa 2 11 30 '/2 L $d it 40 'M $ li n '/n 900 riso Nat M i>W 7/>2 JD iu4 7 h., M '39.- no sR-S M ",in 4 thd"%,, i% .1W"%, s) - MO > r > W fiffA t % M. o .!akS2 "n !!k%c. yn l 7i-- If

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DATA SHEET 10.3 REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET T INIT T DIE INI RCP RC-P W C RC-P-1B/D _[ RC-P-1A/C \\ / RC-P-1B/D \\ [ RC-P-1A/C ^ [ .RC-P-1B/D k RC-P-1A/C _ [ \\ RC-P-1B/D [ \\ \\ RC-P-1A/C / RC-P-1B/D [ \\ RC-P-M \\ Rd-1B/D SPRAY VALVE RC-V-1 TIME /DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS t.ooo 7d7 GCr, ZoLo 7A.7 4 2lco [2,7 b 2.,I L O YL7 1 ro o Y17 Y 111() EL'1 N

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DATA SHEET 10.3 REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET RCP REMARKS RC M /C RC-P-1B/D RC-P-1A/C N [ RC-P-1B/D [ m RC-P-_lA/C RC-P-1B/D [ N \\ RC-P-1A/C / RC-P-1B/D \\ \\ RC-P-1A/C / RC-P-1B/D RC-P-1 W RC $ 1B/D SPRAY VALVE RC-V-1 TI1E/DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS lt 3 y- / 7 2 9 k // sT/7 7ct f 1130f?-2s-N 11 o o 1219 0 4 33 u/? zy / 3 G'o /919 k I4.,s is ->r e% t +sU,->r U~. GD 153Y/4->T' G-k - 1 rw i 1- > r i ILie 9 - > t-W. Iops / y,W t,.n, lt,3 f. 1-3-t-v.v. p 9 tI,. ) 7. >1-t.p, /'i46 7 - F W. /De / 7.>r-c- tirH 7->t-k."- 19u 7W A,9 t14e 4- >r-W y s-a 7O ta p. W* ~t -> r tM R\\2o 7 2%1 /% 2 t > */ 7-2T M

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DATA SHEET 10.3 REACTOR COOLANT PUMP / SPRAY VALVE OPERATION DATA SHEET N TM INI RCP RC-P-1A/C / RC-P-N [ RC-P-1A/C [ RC-P-1B/D y RC-P-1A/C RC-P-1B/D RC-P-1A/C ,[ N RC-P-1B/D \\ RC-P-1A/C / RC-P-1B/D RC-P-M R 1B/D SPRAY VALVE RC-V-1 TIME /DATE ON INITIALS TIME /DATE OFF INITIALS REMARKS 01To 7-27 NM o M. o 7-17 (> o w o,-i n M o 4to 7-21 o 4tfo y-zy b o s to 7.L=z 9 of Ho ~7. L'c (-b OG2o 7-0 nWo/7-2.cl Mb e<cI7h.2.s JA U l l I l I TMI UNIT 1 T "." C 'l TP 600/4

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t t DATA SHEET 10.6 i MAKEUP & PURIFICATION SYSTEM FILTER SHIFT / CHANGE I DATA SHEET TIME CHANGE j TIME FILTER DATE ON Y/N INITIALS DATE OFF INITIALS REMARKS MU-F-1A h-73 'Y (TMih Ok.b1$ !Mb C#fs p du/lti-MU-F-1B tb k ' T\\qh <7hMl SCy [emot/[ h I MU-F-2A - f '> Y N h 1d'b l % k C(k9 du/23 7 MU-F-2B Idt' Th W Mk 7I@Dl M NI 68 l7 #7Y l MU-F-4A Y/ /75 YV f/11Y O bhlV3l ftl) won 4 m gi nQ L pA ),,, W-0 MU-F-4B N-O 7 %h l M ! e1[f} l /M, d 7 MU-F-1A ' hfu I 8'/4-. l l soy R M S-&9 -tm-F-1Bi i l I lMU-F-2A qs1 NO _ lW Nrs s, { l MU-F-2Bl k b k h N hp - l' MU-F-4Al0Y Y Mm. $$ 19s0 lfnt A/ (RyD Bud $2k$ MU-F-4Blb hik !* M* /h) M ln [,i 4% h, h A9 iTG-7-1l, I I l i ! rw-r-lu i I MU-F-2A l ' Mu-r-2B N h V E_.,6

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DATA SHEET 10.8 CONTROL R0D DRIVE CYCLE DATA SHEET SHIFT SUPER-CR-1, CR-2 CR-3 CR-4 CR-5 CR-6 CR-7 CR-8 VISION SIGN. DATE/ SHIFT V V f Y Y f f 7-if $3-11) / / / / bli(%- % 7-1 (ii-v) V"' y V ~7 ( r3.is _) hk 1-to (u 7} l/ V U V O '=% 9 ( 3-II) ~ l ' O 7 lIl G t - 73 f ~ ~ y-ll -f*7-h r ~ V f _/ 7-l I D -l ~~~~~ J~ 4 -12 (If-) v-r 7 / y y / @m 7-/265) L v ibs 7 >-O-1)) M q-ts G t-,S v v ~ [ he 7-IS [7-?) V / L/ ~' / A S.-/3-$3h-ll ^ 5 1-l4-(H-7 ~ ? /Y ~l# .jmn / / ' ~ \\/ M l7-Q-ob -Id ^

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(. ( DATA SHEET 10.9 AUXILIARY SPRAY VALVE OPERATION RC-V-4 DATA SHEET TIME /DATE INITIALS TIME /DATE INITIALS REMARKS on ^ we.tt Ato 7-tf d yts f u r v 841 % :f-M o lo 4 3a AM v v sit a s hb~ o $e e W 1 * *L ~1 a r k- /s m 7-2 7 h k foiz 1-2 T k Illo Mr //su 7-ar-12 r 7 2r' h 123r Mr d n,e Nr g h 1944 hr h 11ta 1sr th in o >lu r f- - no,.,->r /stQ ilu i6otpits } "*~ u a o 'Vs.3 h o OVs )A /1 >a Y2.3 N / E3EO F- ///d YLf N /Sd //7 - 19 /d b N 1,000 La le NV N 21 d 6 M SY*fk bd brEb 6140 Y4 N D 210 $t, M deAQ j O 4s to *) e240 f24 D 0 3 3a Yr6 D o bloYW k 0%oYty M 64yo [2.f. N O OoT24 [-f 7 o C'lo h.4 [$ o G %o 7[ts cGTO [2C h d 7.30 % 4 M TMI UNIT 1 $b.7. 2d[3 C]f V' TP 600/4 Effective Paga 0 CUP'.'C/JE PAGE h Page 46cl y.

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DATA SHEET 10.10 MU-V-110/MU-V-201/MU-V-90/MU-V-92 OPERATION DATA SHEET HU-V-110 HU-V-201 VALVE OPEN VALVE CLOSED VALVE OPEN VALVE CLOSED TIME /DATE INIT. TIME /DATE INIT. TIME /DATE INIT. TIME /DATE 'INIT. N jf)hlu/D >lY bolobllk61 Y /G3Sl2/YG AR0 0YilYU )N) & 111L u n d.oli 7-26t1 h Mz5$3 b nu ,hl b q I e 1 i l l ll HU-V-90 / HU-V-92 VALVE OPEN l VALVE CLOSED l VALVE OPEN gVALVE CLOSED TIME /DATE INIT. ITIME/DATE INIT. l' ITIME /DATE INIT. TIME /DATE INIT. H111-k-9) LM /3/ *) 1 =Lo =91 lU .5!O l? NW$b /f2 ,15 (3 4%. 19.51/rr/r% 105 7 E!!f3 N lle'LS, 24, f 7 ^ 4 I I-i I l 'l l l

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g_ j 11.0 ACCEPTANCE CRITERIA 11.1 Acceptance criteria is listed in Data Sheet 10.2 for chemistry i sampling / addition. 11.2 The remaining data sheets are for recording various system lineups and filter changes. The only requirements to be considered for these data sheets is to insure sufficient circulation throughout the systems / components to meet the requirem nts of the cleanup process. ,11.3 Data sheets and procedure sections completed have been reviewed and are determined acceptable for the purpose and intent of the l' RCS H 0 Cleanup process. 22 hh Task 9 Representative d M __ M Date /a/[- @ =>-4 d b] I 7-/t - O Y-J,c. 7- / t-vs 9c-742 % '1 tt 0 1 THI Ull1T 1 OFFICIAL Fmn COPY TP 600/4 Effective Page O ctJPL!CATE PAGE Page 48

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'l TEST PROCEDURE EXCEPTION & DEFICIENCY LIST -QUESTIONS FOR TEST EXCEPTION ACCEPTABILITY ENCLOSURE 1A 0F TP 600/4 Exception vs. STR - applicable to all Test Exceptions-1. Does this change revise the scope of the procedure as approved? j 2. Does this change revise the intent of the procedure as approved? Safety Evaluation Consideracions - applicability Category A procedures 3. Does this change increase the probability of occurrence or the consequences ~ of an accident or malfunction of equipment important to safety? 4. Does this change create the possibility for an accident or malfunction of a_different type than any evaluated previously in the safety analysis report? 5. Does this change reduce the margin of safety as defined in the basis for any technical specification.? Environmental Evaluation Considerations - applicability Category B procedures 6. Does this change have a significant adverse effect on the environment? 7. Does this change 1nvolve a significant environmental matter or question not previously reviewed and evaluated by the NRC? TMI UNIT 1 TP 600/4 Encl. IA, 1/1 OFFICIAL FN n COPY %g'***3o

• "* "*8*

DUPUCATE PAG ~- 6

~( '( ENCLOSURE 2 OF T. P. 600/4 ,OUALITY CONTROL WITNESS SIGNOFF SP.EET Results witnessed as Satis'factorv Paragraph Sat. Unsat. Signature Date P P 'IMI UNIT I TP 600/4 4 O MICI.Al,.mcrnCOPY !a'N's'!"*"*** cueuc4r5 PAGE h -.,m ,--.v..w, .w..

) $ h d E.i1 , C i O l'.1 C if ( 1102-1 Revision 56 ., y'.

• 5 01/15/83 IMPORTANT TO SAFETY.

NON-ENVIRONMENTAL IMPACT RELATED ColfTROI.I.ED COPY FoY -THREE MILE ISLAND NUCLEAR STATION USE IN UNIT I ONL UNIT NO. 1 OPERATING PROCEDURE 1102-1 PLANT HEATUP TO 525'F 7g Table of Effective Pages v 'Page-Revision Page Revision Page Revision Page Revision ~ 1.0 52 31.0 52 2.0 52 32.0 55 3.0 52 ' 33.0 , 52 -4.0-52 34.0 55- - 5.0 - -52 35.0 55 6.0 52 - 36.0 55

7.0 52 37.0 55

• THIS PROCEDURE MODIFIED FOR *

'8.0 52 38.0 52 ,$ THE PURPOSES OF PERFORMING f 9.0 52 39.0 .52

• TP 600/4.

-10.0 53 40.0 52 11.0-52~ 41.0-52 12.0 52 42.0 52 13.0 52 43.0 52 '14.0 52 44.0 52 15.0 52 45.0 52 16.0 54 46.0 52 '17.0 52 47.0. 52 18.0 -52 48.0 52' 19.0 52 49.0-52 20.0 52 .50.0 52-21.0 52 51.0 52 -22.0 52 23.0

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m-FOR USE lN (.NlT l Oi'ik / ( 0;lon52 .c, THREE MILE ISLAND NUCLEAR STATION - UNIT 'NO.1.0PERATING PROCEDURE 1102-1 PLANT HEATUP TO 525'F Table of Contents Section-Page

1.0 REFERENCES

2.0 '2.0 LIMITATIONS AND PRECAUTIONS 2.0

2.1 Equipment

2.0 2.2 Administrative 5.0 3.0 OPERATING PROCEDURE 7.0 N. 7 OFFICIAL FIRin COPY ~ DUPUCATE PAGE O TMI UNIT 1 TP 600/4 1.0 Encloss e 3, 2/40 Effective Page 0 ~ Page 53

• I**

FOR USE }i Dn i GNiff ( 1102-1 ,,. a Revision 52

1.0 REFERENCES

-1.1 Filling a'nd Venting Reactor coolant (R.C.) System Operating Proce-dure 1103-2 1.2 Rressurizer Operation Operating Procedure 1103-5 1.3 R.,C. Pump Operation Operating' Procedure 1103-6 1.4 Decay Heat Removal System 1104-4 1.5 Plant Technical Specifications 1.6 Plant Limits and Precautions 7perating Procedure 1101-1 1.7-Once Through Steam Generator (OTSG) Fill, Drain and Layui Operating Procedure 1106-16 1.8 Makeup and Purification System Operating Procedure 1104-2 1.9 Hydrogen Addition and Degassification Operating Procedure 1102-12

• 1.10 Core Flooding System Operating Procedure 1104-1 1.11 Reactor Protective System Operating Procedure 1105-2 TMI UNIT 1 1.12 Turbine Generator Operating Procedure 1106-1 T

Encl re 3, 3/40 1.13 Main Steam O 1106-14 Effective Page 0 8.H fud $ Blue) perating Procedure frecess fru.Jm H R.nS P"E* S4 2.0 LIMITATIONS AND PRECAUTIONS 2.1 Equipment 2.1.1 Reactor Coolant temperature, pressure and heatup rates shall be maintained within the limits specified in Figure I (SLb2rit. Figure 1 has been modified for this test. NOTE: Following each refueling outage, or following any . outage in which the RC System was opened, the heatup/ : cool-down rate shall not exceed 50*F in any one hour (T.S. Fig. 3.1-2). 2.1.2 The pressurizer must 'not be filled with water to solid (400") water conditions at any time except as required for system hydrostatic tests, emergency procedure and SOP. 7.. ~ ~ ^ 2.0 ~ OFFICIAL.N.3 COPY r amu - A

FOR USE ININiT i.ONL'1 ( s. 1102-1 ~ Revision 52 . 0.1.0 Jhe=presette+eee-me*ime :110 :ble heatup r:t -:ha44:4e= limitd tc-100*fVhriidGM7r2T--~tT4;iGTrTrurea .d:11 ntWe-by-greater 7han=400*F-vi. thio-any=one= S.,

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Z.1..'_ The-pressurieer-to4 cop (hotMFJ7"dTffffEntiab. temper.an-4ture-shall b: mahtained-et-4ess*thar. 010*." eTe 2.1.5 The once through steam generators maximum allowable secondary pressure when the once through steam generator temperature is below 100*F shall be limited to less than 200 psig (T.S. 3.1.2.2). .Li i....TheJiagimbut.aL10wable4ifferent4abbetween-4eedwatdr 1 f = 4emperature rand-steam-generaton=10werMoyncomer-tempena= stgr.c.,:h:ll 5: "-f ted t: 10:: th:r "2 *" L .l 2.1.7 When reactor coolant temperature is less than 500*F-no ~ more than 3 reactor coolant pumps shall be run at one time. 'l nd-h8..... Toi i m e w wanuallysreset Aha Mgh.andelow9ressure. ,10jaction= bis. tables,pcier to-the-automat 4mset-ofA ~ 4ppWable hypan&i31@les_wille.ause,.an-4*advev6enh.

• 4*f t4ati dh"6PThFTng i nee red +sa feg ua rdgysteem 2.1.9 Do' not exceed a temperature of 190*F and 100 psig pres-sure in the reactor coolant system until reactor coolant pump seal ' injection flow is established',to all reactor coolant pumps.

271-r1C u.Twowsteamrgenerators7hal1%e operable Wirenever Dri .Apolant%verage-temperature-i+-above-250*f (4.S. 2.1.1.2)e TMI UNIT 1 7ET.D C. OM hFVTD gT TP 600/4 I-vt--v 3.0 ', 4/40 - [{ 1 Effective Page 0 DUPUCATE PAGE Page 55 ...a,-,..~--- . ~~---.~.- -= ~ ~ ~----- ~ '~-~ - - - ~ ' ~ - ~ * " ~ ~ ^

'.. ~. FOR US21N (N T i GNil I ~ s u02-1 Revision 52

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1 .The temperature differential between the pressurizer d- ..the p fldfd shall always be maintained-es~s'than ~ 430 *F (T.S. - 3.1.. Forpal plant heat-up/ cool down ~ i-arid power opera nbistempeva re differential should ~ - - Jo a ntained at.less than 250*F. jt 1.12 If CRA Safety Groups 1-4 are withdrawn prior to heatup s g due to moderator temperature coefficient being posit e s'and/or deboration during~ heatup, observe the foll ing: A. Available shutdown margin with highest wo h control ~ \\ l-robstuck out must be >l percent a k/ at most M reactive. condition. B. The shutdown bypass should be i itiated if control rods are to be withdrawn,' and5the high flux trip k / setpoint should be reset to'4.25 percent per Operat-NN f ing Procedure 1105-2,O % Appendix I. C. Prior to reaching / 1720- psif.. (the shutdown bypass ' / \\ bistable setpointi, control rods.should be inserted 4/ until the shutdown bypass has be\\en deactivated and thelowpres# sure bistable has reinitia d at 1900 psig. h high flux trip setpoint should reset / ~.75 percent when the bypass is cleared.pe at Operating Procedure 1105-2, Appendix I. .2 Q The Nuclear Instrumentation will be continuouslyg 24 %itoredng-anyf ivity additg! < ". - ..3

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~ ,W, ha -. u,, -........y ....,.. y. v v ve r:.e a vu ...u-o. r......,.., g. e ,_ [ TMIUNIYl -- e. m uu. TP 600/4 4.0, 5/40 ,.~. O.. m' e-.r.a r-ww-TD COM Effective Page 0 .V " ~ ~ Page 56 ,O i CUPUCATE PAGE I'

< PORLUSE lii (N T I OXLY T O ~ u02-1 Revision 52

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.2M M ri n3-pl a nt=heatsp40ltowi ng-refueli ng =1/M.datas hould 4bedakenwersuwtemperature at.leastwvery.JiDL 2.2 ' Administrative '2.2.1 When reactor coolant temperature is less than 525*F, the- l reactor shall be maintained subcritical by an amount equal to or greater than the calculated reactivity (0.1 percent K.) insertion due to depressurization (T.S. 3.1.3.3). 2.2.2 The boron concentration in the reactor coolant system shall not be reduced' unless at least one reactor coolant pump or one decay heat removal pump is circulating reactor coolant (T.S. 3.1.1.18). In addition, while shutdown, when the RC system boron concentration is being. reduced by more than 50 ppm a 1/M plot versus the amount of water added to the RCS must be maintained. Also the soun:e range counts per second must be monitored or recorded continuously when shutdown and decreasing RC system boron concentration. 2.2.3 When operating at reactor coolant pressures less than 450 psig, the low range reactor coolant pressure instrument i must be used. 2.2.4 When the reactor'is in the heat up or hot shutdown mode, ~ d both Decay H~ at Removal trains should be operable. e ' ~

• Should it be required for one train to be removed from the operable status, the Manager - Plant Operations must omCIEFTRTD CSSYttried, and the priority set to return both trains DUPUCATE PAGE to operable status as soon as possible (dependent on TMI UNIT 1 Decay Heat level).

TP 600/4 FOR U$2 !N5.'0 nit i ONLY n;::i;;h '? b Page 57

FOR USEiN (NfT l ONLY I u02-1 Revision 52 EE. 3 - Wiien TenGui stiCiMeis~than45-perur,t F.", do-ne4, ' FequUledupf%istoute Of--th e-f0MeWiM9-GOmputer-9FoupH3 ' gipr.dio. - - Descript4en ~ 20 orst Cn:.3ennal-GonditSr. - u- ?,1 Phsti-Gond4-64en, 40 hre-Average-Thennal=Condi. tion,,, 30 - C0Ye: Map-Aem! C~v'itier. 40- - - - - - - "1 ThermaMetput ~S4 3etected-Assemb}ywTh e nna Worfd itic& 2.2.6 If any Safety Limit (defined in Technical Specification ' 2.1 and 2.2) is exceeded, the shif t supervisor shall notify the Operations and Maintenance Director or Duty - Superintendent. The reactor.shall be shut down. The licensee shall notify the Commission, review the matter and record the 'results of the review, including the cause i of the condition and the basis for corrective action taken to preclude reoccurence. Operation shall not be resumed until. authorized by the Commission. 2.2.7 If, during operation, the automatic safety system does not function as required, the Operations and Maintenance Director or Duty Superintendent shall be notified. The shift supervisor shall take appropriate action as out-lined in the Tech Specs. Note that this appropriate action may include shutting down the reac' tor: Examples of " failure to function as required" are: 1. Setpoints exceeding limiting safety system settings 2. Failure of a protection system component in an un-TMI UNIT 1 tripped state. TP 600/4 Q Q CJf1 g!KI E C O 2Y' ~-, 7/40 6.0 Effective Page 0 Page SS f ~ ~ CUPUCATE P'T a

i;OR US2 W (nit I ONL / ( s 1102-1 Revision 52 2.2.8 When a Limiting Condition for Operation (defined in Section 3 of the Technical Specifications) is not met, the shift supervisor shall notify the Operations and Maintenance Director or Duty Superintendent..The reactor shall be shut down o_r_ remedial action taken as pennitted by, the Technical Specifications until the condition can be met. In the event an LCO is not met and the remedial action pennitted by the Tech. Specs. does not correct the situation, the licensee shall notify the Commission, review the matter and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude reoccurrence. 3.0 Operating Procedure 3.1. Prerequisites Indicate satisfactory completion of steps below by initialing each step;and sign at end of section. p A report has been received from the Plant Engineering, Operations, and Maintenance departments that all work To upree~T* Rc3 Pew,a,,a4;*n fu bar, seq lefsd. necessary for-heatup-has-been-completed. r ___________________....._.___________..__...____....._________ s NOTE: - The report from the Plant Engineering DepJamen

• %hould include verification thatpoutine Tec'hii' cal-Specification Sur.veillances not included 'in :

.I Enclosure l'orML,haveleen perfonned as scheduled by the.Te_chnicfSpecTficati.og,ill be b { Surveillance Program. ny unresolved discrepancies sh ht to the ' attention of the Manager - Plant Operati act. ? 2 Csusi's Gu S Cam 7~3. ha feen af,m,j 7; s/I,w exee,s 0, in 71.c y 16;ues e f Ha. 5Ou flis* cwt"de newco-ol]w .sfecdo'el 5*" RCS Clcrn,q j3 gyg,ydlg,

• - e an 7'0 mI WIT 1 OFFICIAL FMD COPY TP 600/4

. Enclosure 3, 8/40 DUPUCATE PAGE E"**

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FOR USE ;N (nit i CND ( 1102-1 Revision 52 Source range (CPS) and intermediate range ( AMPS) indica-tion available on strip chart recorder located above console cc. If recorder is out of service may be waived

1. - by Shif t Supervisor.

5. Ites so-o. c.ne.an % % shsil bs m & *aj bat ~an tro _ ssw yea,.

3.2 Procedure Indicate satisfactory completion of steps below by initialing each step nd sign name at end of applicable section. hCI. Place all Integrated Control System (ICS) control sta-tions in manual and adjust the manual outputs to zero in accordance with Operating Procedure 1105-4. Verify setpoint stations are set as specified in Operating Procedure 1105-4. Yerify the NDTT switch on "PCR" is in the AUTO position. (This reduces the setpoint for RC-RV-2 (PORV) to 485 psig.) (T.S. 3.1.12). NOTE: Before going to " Defeat" on steam line, break F.W. shuto'ff system notify S/S or S/F. Verify or complete the following switch line up at console cc. A STM line break F.W. shutoff system. Def' cat a. B STM line break F.W. shutoff system - Defeat A STM line break backup system - Defeat 1 B STM line break backup system - Defeat b. Emergency FPT auto start defeat selector switches.. Defeat TMI UNIT I OECE FT.n WW TP 600/4 p, 9/40 ,, g,pg ;g pgg8.0 1y Effective Page 0 Page 60 .. e b_

FOR USE W (P.llT I ON!J ( u021 Revision 52 Verify or' complete the items listed on Encl.1 (preheatup check list) and Encl. 2 (startup surveillance test ch,eckoff). NOTE: The sustained voltage should not exceed 506V on the 480V buses and 4400Y on the 4160V buses. Changin) from tap 3 to tap 4 will result in a 2.5 percent in-crease in voltage thus prior to the tap chanle the 480V bus voltage should be < 490V and 4160V bus voltage should be < 4290V. ~ 4.1. If the Aux. transfomers are not in the 224 KV tap (tap 4), contact Middletown Line Depatment to have the taps changed. The transformer tap chanje should be accomp-lished per 1107-2. h 5. Verify that the Fdd ter chemistry is within required specification as indicated on the water chemistry status sheet. h;. ~~d M 7l.nynf w.j h in accordance 1 p, 71 bl Establish steam generator levels-et-96-pen:en't;tW-100 with OP 1106-1(< leul -sMF'JOO onehes4n~9GH"r a:nje> - psent-on-the.operat4n34ve14strumeritP in accordance with-Operati ng -Procedu re-1106-16. i Oh aintain the main feedwater nozz es subme ed hev.same ti , open the bypass li.neraroTid the feedwatePifon tv -V85A7B) fully open, and control OTSG e h)we be-sheet drains l ' as.eequTre (FW-V86A/B). e Fi -or o. pen Turbine : m r bypass valves an necessary to contr TSG7, ev.e, %h. Fill the reactor coolant system maintaining boron concen-WG:Jst I800 -1900 t!m, tration at least at i )EE,ent aK/K suberitical for 70*F T ~ conditionh, in accordance with Operating Procedure 1103 2, if necessary. TMI WIT 1 TP 600/4 L. 10/40 omcIAL ymm COPY 9.0 g]f Pm 0 .p") DUPUCATE PAGE ~

'.)O~.:.gg()kger-.;.xty,j ( ..s-ca.., .,J j ". Il s i V i 18-. n _g 1102-1 Revision 53 ,3 CAUTION: Do not exceed a temperature of 190*F or 100 psig pressure in the reactor coolant system until reactor : coolant pump seal injection flow is established. ,.m._____.__________________....... _________________________..___. ~NOThTheCS maQe pressuriz,ed toJ5 psig.with'N'f0E 2 leak check. _ Af ter-.leakAeck reduce pre.ssure to 30 psig by venting to RDCT via RCY28._~ ~~ .___.____......____..____...._.....__ _._______....__...:_ W.5

1. D esu //r p

Establish a^ bubble in the. pressurizer {n xcedence ith 4 s etin; "re:: t p: 1102 5. CAUTION: Prior to starting make up pump, insure RC_RV.2 (PORV) : block valve RC-V2 is open and NDTT switch is in auto : insure alarm PRF_6 8 is clear. T. S. 3.1. 2 ~ CAUTION: Insure MV.V217 and MU-V16A, B, C and D are closed and : their respective breakers are open and PZR level is < 220" prior to performing step No. 9. Maintain PZR Tevel,< 220" until RCS > 275 F (See T.S. 3.1.12.3). / 9. Start a make up pump and establish seal injection flow to all reactor coolant pumps in accordance with Operating Procedure 1104-2. Place pressurizer level control in automatic with setpoint at 100" (25 percent). Establish letdown flow as necessary to maintain pressurizer level between 90" and 115". (MU-V5 minimum flow is 10 gpm for (observe valve protection.) *Ed14 ^<U 3/cul *l***y fer //04-2f E-1 Limits & Pre N% plt _ ese.p-wm skll ha m:ssa,l va;q N caution Ste HoTC Q g 6.7 of 10. If desired by Manager, Plant Operations, perfonn MU-V-140, TP 600/4) flushing per Operating Procedure 1104-2 Enclosure II and MU-V-109B flushing per Operating Procedure 1104-2 . Enclosure III. TMI UNIT 1 TP 600/4 OFFICIAL mLD COPY n ; ; g;; h s' q 10.0, -DUPUCATE PAGE b Page 69 ~ p

j*. %.3,lj b,. r { N 1 -i '.'siii--. N' t ':/ ( s 1102-1 Vi-c '. N i t aevision 52 1. Vent the reactor coolant system in accordance with ,,,,,, Operating Procedure 1103-2, if system pressure has been less than 30 psig. CAUTION:.Do not exceed the decay heat maximum pressure as shown in Fig. 1.

12. Pump the R.C. pump oil drain tanks to 55 gal drums and remove the drums from the-reactor building.

1. The following steps enable application of vacuum to I 's during startup, maintain radioactive' gas rel. eases to the environment as low as practicable, and a e same time \\\\ allow the discharge of small concentrat ons of radioactive gas from the condenser vacuum l pumps to be s ,.s. .L . controlled an. credited as planned ra ioactive gas .u releases. ^ a. Prior to proceeding /to Step 13 accomplish the \\nsure MS_V 25A/B are tightly following: closed. Veri y at th flange is blanked between MS V 25A a\\ e nd and MS-V 24A and B. / b. Mark RMA-5 recorder ch rt as follows: " Vacuum is. ing established." F 1 ow Emergency I Procedure 1202-12 if RMAS al s or alanns. c. Prior to drawing vacuum on OTSG' : sure nitrogen is isolated to OTSG and-feedwater heaters per 1104 26A. h TMI UNIT 1 Ec!O.3,1mo OFFICIAL Fmn COPY 11.0 ...q Effective Page O CUPUCATE PAGE ~ Page 63

- = _.. FOR USl,N CNlT l Qivi_1 ( u021 Revision 52 \\ 14. Take manual control of the turbine bypass valves at ' console cc and crack open the valves to, draw a vacuum n both steam generators. 7'

. ' NOTE :

A _ vacuum must. be maintained on the steam generators .0 ntil reactor coola~nt temperature is greater han .............'20*F..L\\......_..........................._......._..........: 2 k / 15. Ifthg'Nmoderator temperature coefficient /is not known to be negat ye and/or deboration is to be// ' concurrent with / .f heatup, perfom the following operations prior to start-tarting RC pumps)l-e 1 in) heatup. p 1'_ ' a. Comp ete NuclearfInstrumentation Precritical 3,, x (.- Checks. b. Set high flux trip setpoint to 4.25 Percent per V Operating / Procedure 1105-2, Appendix !. \\\\ Manually geset the shutdown bypass high pres-c. \\ sure trip bistable \\ on each channel (4 total) of ./ \\h the reactor protective' system. Notify S/S or 4 S/F. d. itiate the shutdown bypass on each channel (4 \\ total) of the reactor protect ye system. N0hh$ Thks hkfk rembve the fo ow ng tr p protectkon 1. Power / Imbalance / Flow \\ 2. Power / Pump g g 3. Low Pressure \\ 4. Pressure / Temperature TMI UNI Notify S/S or S/F. TP 600/4 OFFICIAL Fw n COPY 913/'o 22.0 Effective Page O "g CC.=UCATE PAGE U- ~ Page 6L {

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i. t 'wv611 1102-1 Revision 52 ~ ~ 12oo

16. Verify that the RCS boron concentration is maintained at 1800-2000 r pa (at least at the concentration for 1 percent AK/K subCritical at 70*F conditions.)

17.'Q%. Place the following on computer trend recorders..u// ntil at 0 p% Mark'// ercen power, 2155 psig and 532"F. the recorders with date, t and scale, and every e change and time. "s Pt. 512 - Loop A Tcold Pt. 515 - Loop B Tco d Pt. 505 - RC sure ~,

18. Durin up plot temperature / pressure in F gure No. 1 ery 30 minutes. Mark time of point in plotted cu.

every 2 hours. k' 19. Increase reactor coolant pressure to greater than the net positive suction head (NPSH) requirements for the reactor- .M coolant pumps (See Fig.18) and verify at least 280 psig. AP across No. I seal of the reactor coolant pump to be started. Insure pressure and temperature stay within the limits of Figure (1).mmmensessanness b N 20. Place the spray valve ' control switch in the manual position and verify the spray valve is in the closed position as indicated on console cc. / . w...._.._ CAUTION: E4 Maintain pressure within the limits of Fi,g.31A-with n w ontro w f-they ress eizer-weatens.. Should reactor coolant system pressure approach the NPSH limit Fig ~{h)specified for reactor coolant pumps on-1A stop the reactor coolant pumps. I TMI UNIT 1 TP 600/4 OFFICIAL MD COPY D;2l*";lh,'s' 13.0 C^ r=8e 65 ~ ougumy em m

FOR USE IN (NIT i ON!?/ C u021 s Revision 52 ( 1. Start I reactor coolant pump in accordance with Operating Procedure 1103-6.

22. Run RCP simultaneously with Decay Heat Removal pump for l

at least 10 minutes. (

23. Stop RCP after at least 10 minutes run.

l -C-A& MOW =0nigne:RCP.:may=be=run.whMe-Deeay1eht*WmmT1r in-eper: tie r :--- g,,g %k24a. Run each of the other three reactor coolant pumps one at l a time for at least 5 minutes each. When all four (4) RC pumps have been run as specified, leave 1 RC pump runnirn 'a-1g ...1 m [ 24b. While maintaining the RCS.in accordance with Figure,1$ l-for simultaneous operation of the RCP and DHR system, the CRDM's may be vented while RCS temp is between 100*F and 200*F. S-When-ell i reactor:coolantepumps-have.been-run ar:Miet4"d' [ e Eqd. lea-ve 1. reas.te- -^^' 'at-pump -punn z, :ecure. Decays.,, i H,e,abRemce:1 Sy:t= :nd-4ncres:: "ca:ter C:chr.t "r:: a .i' t"._ Ve"i fy 'll - ::fety-tm r; c;. : :d &;; "" V6@6 j E:SE3S', :nd 0" YES '10~EMB$i:::R&M97. Ond/ r cl<^q -

• BEY 9. and SB tr::ker:.=

i CABT-10h--WhMe,be)ow;;115.l, gas,syys.RC-Pump. conf 19wat4cc f : ^: 1.n _................-accordanceawi th F.1 yure-4A,# _. _ $4 rn a.i n~G.in Tb a R G s.T /:02 5 *i~ owolfecc.ture in aseonIsone 4sitA f, so-a t..esarran y GAen Ses.lIn;<cp.n f;!tw s<srne lms sM//;Q,,em A Y cMnur s.,/ nLp terg,,,,,(,;.-df to & TMI UNIT 1 TP 600/4 14.0 OFFICIAL FIED, COPY, 15/40 Erreceive Page o Page 66 0.L'?UCATE PAGE

s= ' PAGES 15.0 - 27.0 REMOVED. THIS SECTION IS FOR HEATING PLANT TO 525'F AND NOT APPLICABLE TO TF 600/4. ~ 9 4 v .Q Q Q K DCQhY TMI UNIT 1 TP 600/4 O, 16/40 DUPLICATE PAGE. Effeqtive Page O Page 67' i.

ON USE IN CNIT I ONLY C

u02-1 Revision 52 ENCLOSURE I OPEP.ATING PROCEDURE 1102-1 Pre-Heatup Check List Overall Support Systems 1. 230 KV substation. buses 4 and 8 energized. _h 0 2. Aux. transfonner 1A and 1B disconnects closed. S1A-08 (7hr S1B-04 3. Verify a current nomal electrical system lineup per ~ Operating Procedure 1107-1. %h 4. Verify a current emergency electrical system lineup per Operating Procedure 1107-2, and emergency power is available. 5. Nuclear service river water system is in operation per Operating Procedure 1104-30. 6. Secondary services river water system is in operation %k-per Operating Procedure 1104-31. '/. Nuclear services closed cooling water system is in operation per Operating Procedure 1104-11. h 8. Secondary services closed cooling water system is in ,h operation per Operating Procedure 1104-12. 9. Instrument and control air system is in operation per Operating Procedure 1104-25. [/// 40a=-P4ce-one-oFmore ElitUrating=Vfater-pumps.d3t;operati% . par operatiny Procedure-4404-9.- d

11. The LWD Systems in operation as needed per Operating Prohedure 1104-29.

TMI UNIT 1 TP 600/4 O m g m F. T. n C. O n 2e.0 tocio. ore 3, 17f40 p ,m. - .. y --..,;,., ;..,.. Effective Page O

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-OR USE IN (NIT I ONLY ( u02-1 Revision 52 e

12. Gaseous waste disposal system is in operation per N

Operating Procedure 1104-27. - e uir n'

13. All the below listed auxiliary ' systems are operable and in service as needed. -

A. fSpent fuel cooling. Operating Procedure 1104-6 B. Aux. and Fuel Handling Building Ventilation - Operating Procedure 1104-15A-C h ~ C'. Control Room' Tower Vent - Operating Procedure 1104-19 h-D. Cycle makeup pretreatment Operating Procedure 1104-22 E. Demineralized water Operating Procedure 1104-23 F. Misc. support building vent. Operating Procedure 1104-24A-M r di-J clid wasti dispisal ;0peratTnfProcedurs-1104-20 H. Screen house equipment Operating Procedure 1104-33 M-I..~0-tre water chTWa7d'cTemPfee'd"-6pTfia'tTng4bs'edGr~e"'" ~ r t104=3fr""' /t///$ .d Jiver water-cMorr-1-10446~** A//M K. Mech. draft cooling tower Operating Procedure 1104-37 L'. ' Sump pump and drainage Operating Procedure 1104-40 Mf f M. Station service air Operating Procedure 1104-42 N. Nuclear plant sampling Operating Procedure 1104-43 b ~ ^ C.. Tubi 41e.-plant samp1.1.ng-Oper.at.i.ng-.Rr.ocedure 1.10' " P. Fire service water Operating Procedure 1104-45 //2y Q. Heat tracing Operating Procedure 1104-46 R. Screen house vent and river water - Operating Procedure 1104-48 TMI UNIT 1 TP 600/4, 18/40 OFFICIAL Fg@,CppX...,29.0 Effective Page o ,.; I,il..( './ [. ; 2 ,,,f,,,,'. Page 69 ~ = CUPUCATE PAG 2 j

OR USE lit CN T l ONLY

( ttoz-t Revision 52

• • S Domestic water Operating Procedure 1104-49

'/ T.- Sludge facility and industrial waste Operating \\ rocedure 1104-50, Secondary Systems \\

14. Start the t'urbine auxiliaries and place the turbine on the turning gear per Operating \\rocedure 1106-1..

Start the feed p\\ 15. ump turbine's auxiliar.ies and place both main feed pumps on their turning g\\' /. ears per Operating Procedure 1106-3. T /

16. Verify a current valve, lineup for the feed system per Operating Procedure 1106-3.

' 17. Verify a current valve lineup for the condensate system per Operating \\ / Procedure 1106-2. Start both auxiliary boilers ~and wam{up the auxiliary stem header per \\ 18. Operating Procedure 1106-4. \\, p L

19. Verify a current valve lineup ~ for extraction steam, feed water heater

\\ vents and drains per Operati 3 Procedure 1106-12. / \\\\

20. Start one condensate pump and perform the; feed water cleanup for both I

heater trains per Operating Procedure 1106-2g \\ Train A ' Train B ' 21. Place powdex, Units ir service per Operating Proced re 5 1106-13. 22. Place gland steam system in operation per Operating / Procedure 1106-10.

23. Es ablish vacuum in the main and feed pump condensers per p'erati ng

/ s\\. P r6cedure 1106-15. '\\ T81 UNIT 1 TP'600/4 $;M;;" h, T OFEICLH. Fmin COPY 30 0 t ig3,7.s-Page 70 DUPUCATE PAGE p

FOR USE IN (N T l ONLY f 1102-1 Revision 52 t y

24..,

e condensate chemical feed system in operation per Operating Procedure 1104-3. Comp \\,te 'a valve lineup on the emergency feed system per Operating / 25. le Procedure 6-6. / Comp' ete a valve lineup on the main steam system per Operat ng Procedure 26. l (Ma n\\' Steam Lines drained and pipe hanJers not 1106-14. inned).

27. Place the isolated p ase bus duct cooling system in k

operation per Operating cedure 1106-11. '28. Insure the following valves.are set up for automatic operation by check-ing that the valve operation in the neu ral position, the pin is removed,'(or the handwheel is locked the full open position) the air, equalizing valve is close.the air hupply is valved in and the control s box man / auto lever is in auto. A. MS-V-3A \\ B. MS-V-38 j C.. MS-V-3C D. .MS-V-3D ,/ E. MS-V-3E / \\. MS-V-3F[/ F. \\ G. MS-V-4A' \\ H. MS-V-B ~ I. EF V-30A J. kF-V-30B K. ' FW-V-16A OFFICIAL Fmn COPY i.h O FW-V-16B. DUPUCATE PAGE \\ TMI UNIT 1 TP 600/4 .31.0, 20/40 ,s,,,,. ,,, l,L.' Effective Page 0 c m c.....

Ji., !~

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t ( QR USE ;N UNLT I.ONLY jg2;1 ~ M.\\ f.W-V-17A-s N. V 178 .. y. _. O. MS-V,6' [_ Q P...MS-V-13A s \\ Q.. MS-V-138 29. Insure Instrument a e valved in to the air speed c' hangers for: A. FW-P-IA (IA-V-990 B. FW-P-1B (IA-V-987) / / ......InsureEF-P-1governorks C. set. 30. Insure that the white light abel "MS-V4A/B ICS Control" and "MS-V3A-F ICS Control" are 1111 min ed on ICS/ N N ower monitor cabinet. / 31. Insure NORMAL-EMERGENCY selector switches or MS-V4A and EF-V30A located p in the ESAS room are in the NORMAL position.. f ~. _ 32. Insure ' NORMAL-EMERGENCY selector switches for MS-V4B and EF-V30B located j near the Remote Shutdown Panel are in the NORMAL position. 33./nsure the System Control / Manual Loader Selector Switche\\ I so console CL / and CC for EF-V30A/B are in the normal position. N N OFFICIAL FTwin COPY O" at untz 1 DUPUCATE PAGE - TP 600/4, 21/40 Effective Page 0 32.0 Page 72 y i t 5-b

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FOR USE IN (N T I ONLY ( 1102-1 Revision 52 Reactor Building Syst' ems 7

30. Place fluid block system in operation per Operating Procedure s.

04-20 / //

31. Pla e i

~ Proce\\penetrat on pressurization system in operation per O ,. / dure 1104-21. / A e

32. Place pen tration cooling systm in operation per Operating Procedure 1104-16.

33. Place reactor b 11 ding ventilation systems in operation per Operating

\\ Procedure 1104-14 through F.

34. Place control rod drive service structure ventilation in service as follows:

/ / (1) Close or verify closed breakers 12,13, and 14 on Panel D-8. ~ (2) Close or verify closed brea.ker 25 on panel CV-3 (breaker for ind. lights) (3) Close or verify close,d 12 breakers on the "D" ring on west' side of s the refueling cana / (4) - Verify 12 indica in) lights for head' vent fans are on (mounted on "D" ri ng). 35. Verify a current.~ valve lineup exists on R.B. spray % ystem and. verify th s the system isc/ in 6mer. standby mode per Operating P~ ocedure 1104-5. t s... '.,,

36. Verify a current valve lineup exists on reactor buildin3' emergency

/ \\ .coolin i t d verify the system is in standb -per Ope / g r ver wa er system an rating Procedure 1104-38. OFFICIAL FMn COPY 1,,1 O tr 600/4 DUPUCATE PAGE, 22/40 ,33.0 Effective Page 0 .s,. /.. J. y,, Page 73 ~' ,. f w g-

( ( )R USE W UN T I ONLY g;t t Primary Support System

37. ' Decay heat river water system is'in operation per Operating Procedure 1104-32.

._b

38. 'Deday'hiat' closed' cooling watir sy' stem is in operation o.

per Operating Procedure 1104-13. h-39.. ' Decay heat removal system is in operation per ~ (7)4f 0perating Procedure 1104-4.

40. Place intermediate cooling system in operation per Operating Procedure 1104-8.

_h[

41. Verify that a current valve lineup exists on the makeup and purification system per Operating' Procedure 1104-2.

~ @f

42. Verify a current valve lineup on the nitrogen supply system per Operating Procedure 1104-26.

O

43. Verity that a current valve lineup exists on the chemical addition r

pk system per Operating Procedure 1104-478.

44. Verify few range pressure instrument RC3-PT5 is valved into the primary

/bh system.

45. Verify a minimum volume of 16 feet of free space in the reactor coolant hieed tanks.

M. Instrumentation Systems 46=WerifyMhat-theapressuri zere. heater.d odp;ietalautet*41Notmoverridden ,h-. it.ck.;n-the-lCS/NNI:poweremonitormabinet-i. ;.. i.t.e i.emei pgskion-end41trmaen:PRF1-3-5 is clear 4m M/// ~ ' OFFICIAL FMB COPY TMI UNIT 1 p ' DUPUCATE PAGE l > TP 600/4 ', 23/40 Effective Page 0 34.0 Page 74 ~,., ' ~~ - ( 9'

.( (

, FOR USE ;N UNIT l ONLY u02-1 Revision 55 47., The following instrumentation systems are in the conditions specified f

n I A. . At le st' one source range instrumen NI-1 I-2 (ci le applicable ~'instrume\\.... nt; has a current test 1303-7.2and.re/ . ads greater that N OT' f-D v 0.6 / W/g %, cps. -7 ' cps f l../Vi ~ ./ 5 . At least one intermediate range in trument, NI-3/NI-4 (circle applicable ins \\ trument), as a current test 1303-7.1 C. At least two power range instruments, NI-5/NI-6/NI-7/ NI-8 (circle applicable instruments) have current 1303-4.1 tests, and their trip setpoint is 4,25 percent per ' ' sectio 5,8,2 / D. 114 shutdown bypass switches are in the bypass position. t REACTOR PROTECTION SYSTEM s E. At.le t wo of the shutdown bypass channels have ~ section 6.8 o ' st1353-4.1 current. F. Ierify below listed P signal Jacks are connect'ed to operating channels. l 1 R.C. Pressure - ch lux Recorder - channel 2 R.C. Flow - channel 5. R.C. Iow "A" - channel \\' 3 Reactor Flux - channel 6. R.C. Flow "B"- hannel ~ EsAs 48)t>'1 ast 2 analog channels for the engineered safety THI UNIT 1 .in COPY TP 600/4 OFFIC tocio.or. 3, a/w ter.eciv. P.. o DUPUCATE PAGI Page 75 35.0 ..i. + ,/

FOR US2 INbNIT I ONLY ( .u02-1 e c 3 Revision 55 1 ~ features listed' below have current tests as noted. (T.S. .5.- 1) N-Makeup and purification system (H.P. Infection Mode) A Reacto lant Pressure Instrument Channels-1303-4.11 Reactor Building $4 psig Instrument Channels -s1303-4.13 . Manual' pushbutton' ',1303-5.2, and 1303-4.11. B. Decy Heat System (L.P. ection Mode t Reactor Coolant Pressure I trumente hannels - 1303-4.11 ~ o C. Reactor Building Isolation and Reac r Building Cooling System (l303-4.13. Reactor Building 4 psi nstrument Channelsq'- 1303-5.1. Manual pushbutton - 1303-5.1.

• N,

//. N D. Reactor But,1 ding Spry System ~' Reactor.' 11 ding 30 psig Instrument Channels 1303-4.14. A Spr Pump Manual Switches 1303-5.2, and 1303-4.11. ung Y '49. The following minimum non nuclear instrumentation is in service: A. I reactor coolant flow channel per loop. L. A's B. I wide range and 1 narrow range Tc channel per loop. M C. 1 pressurizer level channel. Mb D. 1 pressurizer temperature channel. b b. E." 1 wide range and 1 narrow range pressure channel.. Ch4 b F. 1 main steam pressure channel per steam generator. MN1, 25/40. OFM M F-Q T M Es'eY as 0 ~ DUPUCATE PAGE -l >1 [ ~.

'FOR USE IN(UNIT I ONLV ( 1102, ,'a Revision 55

• • G."~~ Tu'iain i.un,ine-throttle pressure channel per. steama generator.

flh H.. I' start @,1 operating, and 1 full range steam d !)ene'rator level instrument per steam generator.

50. Review the "Firewall Breaching Notification" Log in the Control Room and notify the Manager - Plant Operations of any that will require a fim watch as plant heat up commences.

(Ref. 1420,FB-1)

51. Physically verify positioni and lock status of allfvalves on the Locked Yalve List. Any discrepancies between the Locked Valve List and

~ the actual valve / lock position shall be noted to the Shift Foreman and either corrected or logged in the Locked Valve Log. Signature

52. ' Verify 1105-3 " Safeguards Actuation System" System lineup is correct.

53. Shift Foreman / Supervisor verify whether a 100*F or 50*F maximum tempera-ture change in any one hour type heat-up is to be perfomed. Note that a 50* HU/CD limit required for RCS inservice leak and hydrostatic tests.

Df SksGAf-- 1100~F Change in.any 150TChange in any one hour type heat-up one hour type heat-up Sk/SSInitial SF/SS Initial ENCLOSURE 1 Checklist Complete: Perfomed By /211l YW Date ~7f3 Signa' turd 1 // . Reviewed By SRO' \\ or R0 License N#A \\ Date 7-2.# ~7-3-83 Signature OFFICIAL FwgCOM Ectlfre3,26/40 ' Q,,' 3{.0 j; Effective Page 0 DUPUCATE PAGE Page 77 3

1 1 .:OR USE IN (nit I ONLY ( u02-1 Revision 52 Enclosure II Operating Pruceduru 1102-1 Startup Surveillance Pmcedure Checkoff 1. Prio r to each.Startup verify that each of the following surveillance requirements have been pe rfo nned. Procedure data must be < 24 nonths old unless otherwise stated).

Su rveillance

T.S. Pa ragraphs :

Initials

Proc. Numbe r

Applicable Title of Procedu re

'of Checker

$ 1SGZ-51'2 din #4 til. ~ ~ RC-Temp?C-hil/P risTJTem70fm-d~ ' - - 'E

4.1.1.11

-- -. yarato r*Calibratierrw i [

1302-5.2 and 5.3 :

4.1.1.8

High and Low R.C. Press.

4.1.1.9

Channel Calibration O~

• -tS024. ^

~ -..--4-1.1.10.._.... Flux-RfCr41ow-Compsratar : f ;:

Calibration

1302-5.6'.,.

4.1.1.12

Pump Flux Comparato r and

R.C. Puup Powe r Ibnito

Calib ration

~_ ./

1302-5.7

4.1.1.1%

High Reactor Building 1

PressuJe' Channel. Calibration :

/

1302-5.8

4.1.1.15

. High and Low Pressure Inj. q

4.1.1.17

Analog > Channel s Calibration

\\ 1302-5.10'

4.

9

Heacto r Build E

Cooling and Isol. krijency ) Analog:

Ch - 4 PSIG - Calibratiot

{ 'A:

1302-5.11

4.1.1.21

Reaeto r Bui1 ding Spray Sys.

/

Ch. - 30 PSIG Ch.

) .-Ca l-1 b ra tio n--- - ~ e, ometAL EELD COW myg i O 38*0 tee 1eeere 3. 27,40 DupuCATE PAGE _ Effective Page 0 ) .3 -,.. - 3,. ; ,i..... m ,r. . ' s i '. ./..; C..,1 /i'.. t.,, ' !.',,- Page 78 ~ r y

1 FO.R USE IN (NIT l ONLY C 2o2;t ~ ,,g, .'. - j -: Su rveillance

T.S. Pa ragraphs : - -

Initials - -:

P roc. Numbe r -

Applicable Title of P rocedum

of Checke r

1302-5.12

4.1.1.22

Pressurize r Teraperaturu and :

h t[Lew1 Channels Calibration 4.1.1.26

1302-5.13 4.1.1.23

Control Rod Absolute and h

Relative

) )s 4.1.1.24

Position Calibration

~: '. : 1-382 ';.1";.... _. _._,. 4rl:id5- ---. lare= Flood-Tanks-Pressu m= ~ ~

md-4:e wl-Channeh -

Ad4bret-iom=

1302-5.17

4.1.1.27

1 lake-Up Tank Le wl

Channel Calibration

.J

1302-5.18

4.1.1.29

High and Low Pressure Inj.

[n,,/) Mi

Sys. Flow Channels

Calib ration h:

1302-5.19

4.1.1.30

B.W.S.T. Lew1 Ind. Cali b.

~

2 -5,20. _... --4.1..lc31_ -

:hAaH<Ts=Le vel-and-Temp.

1

Channel Calibration

1302-5.21

. s4.1.1.32

Recl. B.A.T. Le w1 an ap.:

Channel Calibratpi

1302-5.22'

4.1.1.33 tainment Terap. Channel 1b tio n i.

s. .g

1301-13.1 - - - - : -.l.1.35

: Euervancy Equipae t.

Readiness

! 130J-5 ! Environmental 1unito rs

ETS 5.5.1 N

. y,s 4 --

• 6LibIatiQA --

f

1302-S.25

.4.1.1.37

Reacto r 81dg. Sump Le vel

Channel Calibration s

OFFICIAL F C E6E Sm.. 5 M i! '.'l. Ii - [1 L,.. 28/40 ~ i a< 3...

i...

. DUPLICATE PAGE_ U ~ ' Effective Page O Page 79

FOR USE IN CNIT I ONL'/ C 1102-1 Revision 52 e r j

Su rveillance

T.S. Pa ragraphs :

Initial s

P mc'.' Nurabe r ~ ~: Applicible "" ' i Ti tle o f P mcedu re i of Checke~r ~ :

1302-5.26

4.1.1.38

0.T.S.G. Wate r Le vel

Channel Calibration

= ~

13vz-T.'r ~~

...4-1-1-4G e ~.Sodiura-Thiosulfate-Tk;-tiHiwTTO x-- r ; :

-shannelr-Calib rati6M

1562-E25

4. 1.'1 %

..ediunf-ttytimiille:Ti. ~ .- ~:. r... :

ulewi-ChanneM1+be

.......u., h ,p,,,,..,,,.- .,.a...,.o ._..__,m._,_m._2 .m _. .~s..~ .uim. o n. . v u. m. op_

' Calibration

': 1302-5.31A

3.6.3.1

4160V U and E Bus Degraded

'Giid under Voltage Relay

Systera Calibration s

g

/

1302-5.31B

3.5:3.1

4160V D and E Bus toss of j

Voltage Relay Systera

Calib ratio n y

1302-5.31C

3.5.3.1 UV D Bus Loss of Voltage / :

g ed Grid Auxilia ry ~ f ' ~~ ' ,... ___......... _.. T h Nah ^: 1302-5.31D

3.5.3.1

4160V E Bus los of Voltage / :

-~ i' Degraded Grid Aux a 'ry ~

Tirner Calibration

' 130%11.19E -

i'4.1.1.39' ""~ ~ i Tu rbine ove ripded Trip Te st" ~ ~ ~ ~ ~

(Data < 12 r:n s. ol d).

.s f ~~ lyI-11.2

4.1.2

P ressurize r Safety Valves

..-...-..-,.3 ~~~, . Sc tpo-1 nt---{-50-Pe7 deWt:Te'sttRTP - - t 1M1 Lo11 1 TP 600/4 OFFICIAL FMn COPY Enaosme 3, 29/40 ,*o .s,4*N, Effective Page O 3. ..d'.,.~~ i' ,I*'~ Page 80 DUPUCATE PAGE M . 1 *.,., w I

.FOR USE IN CNiT l ONLY ( 1102-1 ' Revision 52 -a I Surwillance

T.S. Paragraphs :

Initials

/

Pmc. Nunbe r

Applicable Title of Pmcedure

of Checke r / :

g

1303-11.3

4.1.2.4

Main Steam Safety Valves

\\.

Setpoint (25 pe rcent Tested) :

\\ ./

1303-5.5 Control Ibom Eme rgency

/

4.12.1

Filtering System (Data must : /

be < 12 nos. old and system :

operation less than 720 hrs d-I

since last sury.

N::

g.

f:

1303-11.25

414.1.2.1.A.1

• Local Leak Rate Test-Person- :

4.%.1.2.1.A.2.: nel and Eme rgency Air Lock

Oute r Doo r Seals (Once'ewry :

6 months o r within32 hrs..:

of opening when Cint. Int, is:

re qui red.

/ .t' ./.

1303-11.18E3

4.4.1.2.1.8.1'

04-V1, 2, 33and 4 and HP-V1, :

+

4. 4.1. 2.1. B. 2 6 Local Leak Rate Test

./

sg i

1303-11.23

4.4.1.2.1.C.1

Fluid Block System Local

LeaKRate Test through

4.4.1. 2.1. C. 7

/ ,\\ sN 4.4.1. 2.1. A.4 '2',: Reacto r Bldg. Purge Isolation:

1303-11.18D Yales Localgteak Rate Test

(Data Date must be < l year :

i

old)

/

1303-11.18

4.4.1.2.1'.A.5

Blind Flange Local 'L'eak E10,11 :

Rate Test l

f.

NN

1303-11.18E5

. 4.4.1.2.1.A.3

Fue1 Transfe r Tube Seals

• Local Leak Rata Test j-

1303-11.24 /-

4.4.1.2.1.A.3

Ecpt. Hatch Seal local Leak :

Rate Te st (Eve ry othe r

Refueling) e N

1303-5.1

4.4.1.3

R.B. Isolation Vales Test - :

l

[

( Addressi ng the val e s not g:

testtble during operation) q l

OFFICIAL FIELD.COU2 :p ~41.0 '.r-

j; '

76%I Enclosure, 3, 30/40 i DUPUCATE PAGE Effective Page 0 f*~ ' Pace 81

FOR USE IN CNiT I ONLY ( uoz 1 Revision 52

Su rveillance

T.S. Paragraphs :

Initial s

Pme. Numbe r 4 Applicable Title of Pmcedum

of Chacke r

bM1 -

.- 4. 4.17 4' ~ - =.. -L. Ol dg-Annua-1-insp& tie r/

4.5.1.1

1303-11.10 N.

4.5.3.1.A

E'.S. Eme rs. Lo adi ng a nd Pw r. :

N.

4. 6.1. B.

Transfe r Test N:

1303-11.8

4.

2.1

Hi Pressure Injection N

s 'N 77

' Low Pressure Injection

1303-11.54

4.5.2.2

'-s N. : R.B. Pu rg.e:filte r Ai r flow

1303-5.10

4.12. 2.2. a

est.JData mst be < 18 uos

~

o d@nd system operated 20 hrs since last sury.)

/: N .: 1303-11.39

4.9.1.4 f

Eme rgency Feedwate r Pump

Automatic Sta rt

/

1301-10.1 R 3.3.4

Internal Yent Valves

Inspect and Exercise

.f

'1303-9.9

4.17.4

Func. Te sti ng o f' y

Mydraulic Snubbers 7

N: 0910.1-- -- 3 ^.3._.. " ' 7iTru rge -5y~ stem C: .: 1303-4.15

4.12.1.3

Radiation Ibnito ring p3

.: System

-1903-5.7

.12-2.2.e - r NPirge ai r-in:atm nr. -:-- -

. 0pe-ration 7est'6f Vans".

AH-E--?A 1rnd=78.

Data-must-be 68 mo.4ol31

10G3-5.9- -

.-4.12-E.1 -. tBwPu me - Ai r i n: a uaent*

."il te. ( AH=F -i-)-

,Di-f4etent-144-P re ssu re-Ten,

Da t-e-must-be-418-moni d. :

TMI UNIT 1 OFFICIAle_pm CO.E #*'!

. ~.

,m, Li de 3, auco .. p. ~... DUPUCATE PAGE d Effective Page 0 Page 82 b~

FOR USE IN (nit l Ci1LY ( 110,_1 Re vi sion 52 ),', ~

Su rveillance

T.S. Paragraphs :

Initial s

P roc. Numoe r

.: Applicable Title of Pmcedure

of Checker

Mn3-5 A T ' 12,3+2 ~ ~ ~---- ^ ux-a nd-Fue-1-Ha nd1:1 ng -e-

4.12. 3. 2. d

Exhaust Air Treatment

4.12.3.1

Fan and Filte r Te st ~

Data must be <18 mo. o'ld n

N*

1303-6.1

...... 4.1.1.15

ILRT

/ .. -Data must be <3.3 yrs. old

1303'-6.2

' : 4.4.3.1 Hydmgen)t be <3.3 yrs. old rt.ie System ata gus .r

1303.12.3

4.5.2.la

HPI/LPI ystem Vent

4.5.2.2a

-N, / ...4:7.6

1300-3T,,

DH-Y-22A/8; CF-Y-4,bA/8

Leak Check s

1300-4B.

_ -.. : 4. 1 9

~

OTSG Eddy Curnant Testing

/

g: f.-i30147 ~~ ~~ "~ '.' ~4 tl-2.-10 A . Pump ibuse-Floo r-Intake ---- =-o. ~ : .:-Si4 t-Accuuul ation-

1302-5.33

CK/Calib of 14DCT

~~:

Teup Loops

303-FF-

.-Table-4.1-2 -de fueli rigMystem .e

.JteaW"7In'tFrloTke-

-tS03 -11. C"-"-

-2.-Tabler4-1.--5 pent-Fuei-tbo11 ng - - - -~i~~~

--l-tem =9 -

' : System-Fu nc t nTe st----- -

1303-12.5

4.18. 4.1. b CO2 System Function J

1303-12.16

4.18. 5.1. b

Halon System functional

bj-TMI UNIT 1 OFFICL4LJnri.n, COPY.43 0 In"c!Oe3,3m0

.~

. N 21 i *

DUPUCATE PAGE V t .,. i

• Effective Page 0 Page 83 s /

FOR USE IN CNiT I ONLY ( 1102-1 Revision 52 e a

Surveillance

I.S. Parajrapns :

Initial s

.: Proc. Number

Applicable Title of Procedure

of Checker 1 -

'7fP' ~ . 4-18thl- - --- : F.i re Barri er seai s-N. $1303-11.28 Resta WDS Leakv0

.-Comm f

~ ~ ' ' ~ ~ - ~ ~ ~ ~ ~ ~

'1303-1

Restart Report : Waste Gas Sys. Leak Check i

._--....-rnm?i.tment _, a r- = --.:~ 2 ~. 3,n, 1 -_ n-,- 1 ..,7..

^ - ' " ^ "

_s_ $Ii103-T C3Y ~~ .I ~ Re stdepUrNkic omo i ne Ni pe t.e a K ----$"-- - Cbeck N-

Commitment

1303-11.50

Restart Report : RB Spray Sys. Leak Check' ' ~ :

Commitment ~: EFW Flow Testfr/

1303-11.42

4.9.1.

om 1 CondensateJtorage Tank /

N y

1300-3R

4.2.1 1.514estsonMS,Mll,RCand S Systems gN

.1300-3P

-.---.: 4.2.1. ISI Tests on CF, CA. FB, DH, : -

WDL Systems

1300-3S ---

4.2.1

--- - - - : CA-P-1A/B Functional Test ~:. f p N:

N02M4

-. 471 T 45 c RrTrip on ioMnif MFW/, --- - -- - - ?

diaiTrTTrrN-

1302-6.14

4.1-1, 47a

Calib. of D/P Mon. on PORY L- :

and Code Safeties TMI UNIT 1 TP 600/4 Q%- CT ?.7' nRT.n COPY 44 0

• *
• 3 33/4 r

Effective Page 0 A- - - ~- 7 - ' y" ~ ~ ~.* ~ ~ Page 84 DUPUCATE PAGE b s

FOR USE IN (NIT I ONL'Y ( 1102-1 a. Revision 52

su rveillance

1.s. Pa ragraphs :

Initial s

P roc. 'Nurabe r

' Applicable Title of Pmcedure

'o f Chec ke r

1302-6.13

4.1-1, 47b

Calib. of Accoustic lbn.

.... _: g g

~on PORY

=- //[

1302-6.16

. 4' 1-1,. 4 8

Calib. of PORV ~ Set Pa int '

g 2-6+6 - ' : 24n% 49 .- Calib--Sat MaYn ibto r-:--- ~ s. q =.4.1-1, 50

1302-6.3

Calib. EFW Flow Channe N.*EFW I,itiation (Refueling

.. y

1302-6.17

4.1-1, 51 n

CaTibe-(\\ d: ! 13'3-11.21 0

4.5.2.-

Co re Flooding u.

Operability Test

~

1303.11.

4. 5. 3.1. is

Rx B1 dg. Erae rg. Cl g. and

/

Isolation Sys. Valves and Coole-rs-Ope rabili ty--Te st.c- - :-~~~

~. -

1303-11.16

4.5.4.2

Decay Heat Removal System

Leak Test

ISG" - 8.2"~ ~~'~ T'4i671iC ' ~

~~~7iesePGe'nirato r' Annual - - - ~ - -. . _... : Insp. (Data must-be < 1

yea r ol d)

^? % c . 1303-11.11

4.6.2.D tation Bat Load

~ f, w N

• 1301-9.2
• 4.7.2.2 Control Rod Power and Instrumentation Cable Verification

[ TMI UNIT 1 Q % C r d. a * = d^ " n C O M u TP 600/4, 34/40 DUPUCATE PAGE _ - 0.. s 45.0 Effective Page 0 ,s J Page 85 NW <

-FOR ~USE lN (NIT i ONCf C u02-1 Revision 52 fQu,rveillance .: T.S. Parajraphs : a initials f:

1%c. Number

Applicable Title of Procedure

• 'of Checkdr

!1303-3 .: 4.12.1.2.a Control Room Filtering

System Test (Data must be gt

< 12 mos old and operatedr :

._.,m. --- ~ ~ T 720 hrs since 'TastJu'rTr. ': Main Steam)sIl tion Valves

~1303-11.22

4.8.2

Closure, Time Test

Table 4.1-2

.:geactor Bldg. Purge Exhaust :

1303-11.14

Item 8

. Sp (Dat.a must be < 18 mos-

~

4.12.2.2.a -

old and iystem operated <

4.4.3.2

720 hrs sin'c last sury.)

Enclosure II Perfom y ~' ~ ~ Signature Date Reviewed 2by SRO + Signature Date

a. -..... --.......-....-.

.y L r i OFFICIAL Fm.n COPY. ' L DUPUCATE PAGE i TMI UNIT 1 TP 600/4, 35/40 1 46.0 Effective Page 0 gj. Page 86 7 1 ...t l e

/ - FOR USE IN{ NIT I ONLY 1102-1 y,. Revision 52 ENCLOSURE III OPERATING PROCEDURE 1102-1 ' ~ " ~ Heat-Up Exception and Deficiency List \\ Operatin) Procedure No. 1102-1 Name Pre-Heatup Checklist l' [ Date. Data Taken x / Date Com leted and/or Justified / No. E/D Par.. Description Initial /Date Resolution'/ Signoff Date y / / ,? /: /: s x b

\\g

/ / N /

Performed By

~ ate Sig n,ature

Reviewed By SRO

~ ~ *

or R0 Licnese

/ Date j< Signature / / 07FICIAL FIELD COPY b BUPLICAft PAGE 1 l TMI UNIT 1 TP 600/4 47.0, 36/.40 Effective Page 0 Page 87

• • '...}

i - - - - . -.- e ; 'd

• i

? ( ( FIGUP.E 2. 0 _... _....i......... ..l.. 3. ...l ..o_. ...,..._..l.- g .....). 8 3.. l. l_. t.. ..i .....j..,.... .i..- g. ..,e .... 1 6 ** : ..t.

• -*-**-[

..p-

• g***
• g-}.**

...... 1t v..,.J,I A!.iD 1..n...., RC.oR.c e.,S. r t. l... ...i..... _......:...l.................... ........ w.. t e. a.. un. ....t.... ............ D.h..G S.. JL.. I:Cw.. CP:.r.A 4 Ia.. O,r. .t.. ..t...._.. i- .,..,.. I. RC An. D u... FM., P.,

i.. !i.:-

6 ......-l n ._ i t_.. a...:.... _.....i...r...... 6. _._........_.l...._............ ~ ..i_......_........... .1...... ....i........ _... .. 1. .... i.. L... 5.. i. ...l..........g, lr..,. ..r..... ....i ..r....i......._.i_._.... - w _., p .i 6.. .g i. ._i. ._. _. i.

s...r...:

p._...... 1 n.: ~ i..,, m.ja.o.aa.l__....t..... . I... .....i o...n.. ig g *. r._:.:. : ..l 1 .r 1.,T.... ...i...........t

i....

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s.... ..i... i .__t.l..__...., .i i .i i .i .,,.,,.,t...... n P.oCR. :.._..... l., D. _ -..... -.s._..t.. .. _..._ _.. l,.... II... .t a.. c.. i...... .. w t,0. ....i. .._,._i....._..( _..... .l...... _....._.1 ......i . r., .... RC.-L m,P.CC.,I..A ICt..C.LA. ....i t i..... .....i... .t. .i.. ..i.... . ~ . i... . 1.... .......i. ..g.._...,._. .i......_.......... ...i.. _._...........s.._ ..i.. ..,n ..._._....... -... _............. _ i....... ...._. :....,ia . i.... .... g..

i...

..... i _._....I..... ....i. 6 6 6. l .l. 3 t ,;:.f./.Ia e .I.p.g,,(E l g. .s...,u; wat r.

3. _.u..,O..

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- I

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r.....

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PROCEDURE FOR INJECTING H 0 TO RCS 22

1). Prepare H 0 t the 4% Boric Acid Mix Tank according to the requirements 22 of Specification SP-1101-28-006, RCS H 0 Cleanup.

22

2) Establish valve line up in accordance with Enclosure 6 STR-1

3) Start pump CA-P7, 4% Boric Acid Injection pump.

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TP 250/3 1410-Y-50 Revision 1 MTX No. 600.5.1.9 TESTING DATA OF PIPING SYSTDiS UNIT 1 s ge,) VALVE LINE UP CHICK LIST LINE UP CECKED LINE UP CECKID VALVE NO. OPEN CLOSE VALVE NO. OPEN. CLOSE gy gy CA-V247 X g7 h CA-V248 X Ok re fuhr A h A-V252 X CF-Vll X Q, fD CF-V10 X pa fm WW CF-V34 X y Fi,ke. W CF-V29 CF-V19B X R,k fm x Fa r~ f0 CF-V19A CF-V28A X Shre CF-V26A X y CF-V27A X h x f RC-V1.039 M 7~N RC-V1038 y CA-V-zst K n,L,- Fu p THI UNIT 1 TP 600/4 g ;~. + - . w 3 7 -.f r- - 3

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? 9"?? 5 RECLAIMED 55 $$ E~ 94

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H4 aha# g 2 sveety 0 ->- MAKE UP R. WM y} T Vc y.ygg CA-J L I VaV7 Q I .y% M f g[oD Y *ePty 8 EE' vj 5 . con,. g l VN V-fjiL7a N'k ]n> ca. o vasy CA V1 u cs 4 CF r, r., cA cp k A k Vt96 Va5/ b vi7 VCF-Va? VC F-ggyg AT J L J kVA8A Q' es -- X \\' cA-pq C A-CF g. V.15'3-V31 yfy4 secar REACTOR c o,- e s tr. FUEL e tot, ~ ~ ~ - - Tc'c~ ~ c stoRAGC REACTOR TAtJK Cootelt PdWP I.I PK-Yb3 cr vtaA / + v E M>E gogg i Floop TAAIK A i ~ J

~y1 & A Q Q l0 (LW 0 p o 7/11/83 to 7/12/83 DAILY REPORT - UNIT 'l (1) PRIMARY PLANT CONDITIONS Pressure 307 PSI Temperature 130 + 5'F Cooling Mode DH-B-Water Level Primary sidq; 100 inches - 150 inches przr OTSG-A Nitrogen supplied - Full wet lay up OTSG-B Nitrogen supplied - Full wet lay up Primary to Secondary leakage "B" OTSG Cs 137 at We ib ' (2) WORK FOR NEXT PERIOD I. PRIMARY PLANT A. Primary System Operation 1. Hydrogen peroxide flush - TP 600/4 - Ops /SU In progress - Run rods - once a day - Chemistry samples - In progress - Component shifting - In progress - Add peroxide - In progress - A Q4 (naks.e P e p 2. BH-V-16A - Shevlin - In progress k'P - Open up 0 a emble 3. Expedite anion resin - Hawkins (here) - C of C - Samples Rx Bldg D-ring cleanup (Zewe inspect) 4. a. "A" - In progress 5. Tube sanple flow meter - Engr (no flow) - Observe over weekend B. Problems / leaks 1.. RC-P-1A speed variation problem WO 7-11-83 e 41

? 2. RC-P-1B TE #1 outlet temp. 3. .RC-P-1A-1D speed switch problems K. Letdown Flow Instrument repair - overhaul CA-P-7 packing leak C. MU-P-1A 1. PS-475A - QA Engr. (writing receit QC insp, plan) out 7-11-83 (check at Unit 2) - PS Engr evaluation 2. Seismic supports (7-3) 7-12-83 D. Waste Gas System - Shovlin S 1. WDG-P-1 A will not stop in auto E. Rx Big Painting 346 level - Shovlin 1. Painting on Hold - Resolution - R. Miller - Take samples (Results) (4' weeks for results - DBA te'st) 2. Move equip from Area 4 for preps and painting 3. Patch work 281' E1 - entrance to "D" ring Complete after D-ring work 4. D-ring work - In progress

a. ' Spec 8-83 b.

Prep area - In progress c. Paint (2 weeks to do) LLRT - Shovlin 1. LR-V-49 Repair - LLRT - In progress G. AH-E-14 Fan - Shovlin 1 M 1. Makeup air damper problem (A -D-24) H. MU-Y-203A/B Opr "A" Shim "B" shim S S e

h,# -" ) I. Rx B1dg cleanup outside D-ring - In progress + - Grading clips to fasten J. DH-V-148 seat ring materie.1 send to lab for analysis - Engr K. AH-E-1 A High Vibration 7-12-83 signature (7-3) RM-G-22/23 High range source calib. - Procedure - Vendor training - Receive soun:e 7-12-83 - Perform calib. 7-14&l5-83 M.- AH-E-18A/B High Vibration - Shovlin 'N. ' Sodium %droxide- - STP - Zewe - Inspect valve for leakage - Drain tank - Check transmitter II. SECONDARY PLANT A. EX Steam Defect - (MD-T-2C) 1. Install insulation - ACAS a. Ray scaffold - need technical data on material used 8. SR-S-3's repairs 1. SR-5-38 shear pin (will not travel) 7-11-83 2. Cycle to 'often - screens C. EFW new DPT - Zubey 1. Anchors - QC Inspe W 2. Drain lines - check D. Water treatment seaple cabinet replacement WO. 7-18-83 !!!. OTHER ITEMS A. Rad Waste Area - Ross 1. 7/11/83 (3-11) a. Rx' Bldg. Laundry b. MU-P 1A/B/C c. Weste Gas Compressor Rm d. Waste gas Delay tank roon e. Empty dry vacuums

'2. 7/12/83 (7-3) a. Laundry h.- Waste packaging c. Hittman (transfer & fill) d. Rx Bldg. cleanup [ 3. 7/12/83 (3-11) ? a. Rx Big laundry i b. Neut tk room c. CWST room 4.. 07/13/83 (7-3) E a. Clean Rx Bldg. i h. Laundry E c. Hittman (solidify) i d. Waste packaging ~ B. LM-25A - Testing - S/U - In progress ? [ 1. RM-A-8/9 high calib - not in service

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2. RM-A-5 High L - Not in service { - Low = surveillance to run IC (procedure) SP366/8 (Required before vacuum 7-23-83) g I 3. RM-G-26/27 - Not in service 4. RM-G-24/25 - Not in service F C. Task S/U [ 1. R!t-L-10/11 - in progress D. Decon Unit 1. Chip hole for ventilation pipe - Zubey 2 2. Grout sleeve in wall 7-13-83 E. Snubber.s (12 completed to Eng. for eval) F. Beckman Analyzer - Hawkins - T/0 to S/U (Elect.) 3 1 - T/0 to S/U (Mech.) to SU G.- ' Halon bottle computer room - Fill K E .T

y,- s-H. FS-P Shovlin g4 - IRG readings (3-11) 7-11-83 (3) TECH SPEC CLOCK ITEM ~ N0NE (4) RELEASES WECST - A/B (5) RADIOACTIVE WASTE A. Limits on shipment - None B. Shipment past period - None -C. Planned shipment - None R. C. Troutman Ext. 8154 Document ID. 0037K b o e e e 4 e '.4 '} i 9

i. ,,,e ,,y i ~ OTSG REPAIR COMPLETION /RCS CLEANUP SEQUENCE Plans.& Program. - Dil-1 May 2, 1983 TMMW@' !* W ',,T F 6 M Re natal 1 St t Eility g g,gg Tc 1.ower rent ia ,ene-(Basel l v 1103-2 g 1 I g3-2, 1101-2 .u - ww Kun Hakeup, terform Evaluate F 11 & V nt

Estabilg, r:a:'u 2rify i ll RCS A-No goRCSij@f gg%%{

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+ X 9 o,;, ' * + agers 1x RyInstall 'manent .A POSTkEPAIRPROGRh Ila s (1.00P) l ! \\ gg 1103-11 I 'eq. ' O '. "h aluate Drain e I Dr I nil tr/ p F y Curreur a h f Cm b h \\ l'l bes To T s Be real I"" # "E' Base Ine Hanways 1102-1 1103-6 Il04-79E TP 600/4 TP 600/4 RCS Clean To Tleree ( RCS 11 0 Remove So Evaluate Restore S unil Use 22 4 g"" RCS li o RCS Chemis. Ileatups/ h I"' II"*E"P8 Cooldowns g Cleanup h h & Hil Oli Cleanup & 4 it C Vent N2 7 w e e [ m

SAPC t 140

• lntCr6ffl30 Mcmcrendum Date July 13, 1983 Nuclear Suoject Thyroid Dose Limit for OTSG Isolation During SG Tube Rupture To R. J. Toole Location Director - Operations & Maintenance TMI-1 This letter is to request that you revise the tube rupture emergency procedure and any related procedures as necessary to include an additional criterion for isolation of a damaged steam generator.

The requirement to isolate the OTSG when offsite dose exceeds or is projected to exceed 50 mr/hr whole-body should be modified to 50 mr/hr whole-body or 250 mr/hr thyroid. The additional criterion is intended to address situations when the condenser-is unavailable and thyroid dose is limiting. The 250 mr/hr dose rate, like the 50 mr/hr limit was selected to be consistent with site emergency action levels. The procedure guidelines (TDR 406) are concurrently being revised to reflect this change. The inclusion of this limit was specifically required by the NRC as a result of their review of the TDR and the emergency procedure. k J. N. G. Trikouros, Manager - Safety Analysis & Plant Control NGT/ar f cc: G. R. Bond - Director, Nuclear Analysis & Fuels T. G. Broughton - Director, Systems Engineering M. J. Graham - Engineer - PWR Licensing L. C. Lanese - Engineer, SAPC L. C. Pwu - Engineer, SAPC M. J. Ross - Manager, Plant Operations TMI-1 H. B. Shipman - Engineer Senior II, TMI-1 J. S. Wetmore - Manager, Generic & Regulatory Affairs /B \\

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