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.STARTUP TEST REVISION-DATE 09/30/83-CONTROLLING PROCEDURE-TEST' PROCEDURE TITLE' NO . - 600/2 FOR .
OTSG REPAIR TESTING REV. NO. STR-3' REASON FOR CHANGE : .
Previous'90 F/Hr cooldown'did not achieve. required OTSG tube-to-shell A T'to satisfy SER.
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-INSTRUCTION FOR ENTERING CHANGE ,
. Remove: Cover page, STR-2; Tab. of Eff Pgs.1,11; Pages 2, 7a,18, 21,119.
.. ; Insert:. Cover page, STR-3, Tab. of Eff Pgs. 1,11; Pages 2, 7a, 18, 19b, 19c, 19d, 19e, 19f, 19g, 19h, 20o, 20p, 21, 119, 119a.
. Modify Enclosure 6 to reflect changes to Section 9.8. (Pen and ink change) -
CHANGES ENTERED I certify that all changes have been accurately entered into the test procedure:
ThefollosingrepiacedpagesoftheOfficialField/OfficeCopyareattached:
OFFICIAL FIEED COPY DATE OFFICIAL OFFICE COPY DATE 4
Page of t
8506140063 850125 POR FOIA DETJEN84-897 PDR v.
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TMI UNIT l-STARTUP AND TEST NUCLEAR SAFETY / ENVIRONMENTAL IMPACT EVALUATION '
DETERMINATION AND REVIEW REQUIREMENTS -
- CLASS' 1 TITLE CONTROLLING PROCEDURE NUM.BER TP 600/2 CATECORY A . FOR MTX 600.5.1.7 OTSG REPAIR TESTING REVISION STR-3
- 1. Safety Evaluation Does this procedure / change (a) increase the probability of occurrence,or the consequences of yes O an accident or malfunction of equipment important to safety? no 2 (b) create the possibility for an accident or malfunction of a dif- yes O.
ferent type than any evaluated previously in the safety analysis no E report?
(c) reduce the margin of safety as defined in the basis for any yes C technical specification? no SZ
- 2. Environmental Impact Evaluation Does this procedure / change (a) possibly involve a significant environmental impact? yes C no S (b) have a significant adverse effect on the environment? yes 3 no X (c) involve a significant environmental matter or question not pre- yes C viously reviewed and evaluated by the NRC? no 5 NOTE: If any of the answers to the above are YES, a detailed evaluation MUST be '
attached.
. Preparer / .SectionManagerM M,M Date 6 bO N) N' i <.
Date 9-30 5.5
. Technical Reviewer a /2 . Independent Date 9/::y/>/M 7 8^ **Y "" *"*#
s - / v -
Date S V6kcht-
/0,/$, $3 MANAGER SU/T (or designee):
. This procedure must be reviewed and commented on by: (check all applicable)
OEM DIRECTOR %TechnicalFunctions M NSSS (B&W)
O qC Mod-ops AQAMod-Ops O Other Si;:nsturO M Date 9-8d h Original to Histery File
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THREE MILE ISLAND UNIT 1 CLASS 1 CONTROLLING PROCEDURE NUMBER TP 600/2 FOR CATEGORY A OTSG REPAIR TESTING KrX 600.5.1.7 REVISION STR-3 PREPARED: Cognizant Engineer .
f /M Date 9 -3o M v-RESPONSiB'LE TECHNICAL REVIEWER:
Signature j 'Date 827 M DIPLEMENTATION APPROVAL:
Signature ,
Date/d-/-
0&M DIRECTOR CONCURRENCE: 3 Signature ~
' 4 Date O
i APPROVAL OF TEST RESULTS:
SU & T Representative '
Date ENCLOSURES:
- 1. Test Exception and Deficiency List lA. Questions for Test Exception Acceptability
- 2. Quality Control Witness Signoff Sheet
- 3. OP 1102-1, Plant Heatup to 532 F (Modified by TP 600/2)
- 4. OP 1102-11, Plant'Cooldown (Modified by TP 600/2)
- 6. OTSG Repair Testing Sequence *
- 7. Heatup and Cooldown Computer Points
- 8. OTSG Leak Rate Data Sheets ~
- 9. General Emergency Operating Guidelines for 11FT Program 6
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. TABLE OF EFFECTIVE PAGES-PAGE EFFECTIVE PAGE: -PAGE EFFECTIVE PAGE .PAGE EFFECTIVE PAGE :
'l 0 -
20a STR-2 37 0
- 2 lSTR-3 .. 20b STR-2
- 38 0 3 0 20c- STR-2 39- 0 3a 0 20d STR-2 40 . 0 4 1 l0 _
20e -STR-2 41 0 5 .0 20f -STR-2 42 0 6 0 '20g STR-1 43 0
~7- '0 20h STR-2 44 'O
- 7a STR-3 201- STR-2 45 0 8 0 ~20j STR-2 46 0 0 20k STR-2 47 .O
^
J I 10- 0- 201 STR-2
'48 0
- ll' 'O 20m STR-2 49 0-4 12 0- 20n STR-2 50- 0 .
13 0 20o STR-3 51 0 14, 0 20p. STR-3 52 0 15 0 21 STR-3 53 0
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15a 0 22 0 54 0
'16- 0: 23 0 '55 0 16a 'STR-1 ' 24 0 56 ~0 17 STR-1 25 0 57 0
.18 . STR-3 26 0 58 0 .
19 STR-2 27 0 59 0 19a STR-2 28 0 60 0 19b STR-3 29 0 61 0
. 19c' STR-3 30 0 62 0 19d STR-3 31 0 63 0
-19e 'STR-3 32 0 64 .
0 19f STR-3 33 0 65 0 19g STR-3 34 0 66 0
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19h. STR- 3 35 0 67 0
'20 STR-1 36. 0 68 0 TMI UNIT 1 i.
TP 600/2 STR-3 p . .
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TABLE OF EFFECTIVE PAGES PACE EFFECTIVE PAGE PACE EFFECTIVE PAGE PACE ' EFFECTIVE PAGE 69 0 102 0 70 0 103 0 71 0 104 0 72 0 105 0 73 0 106 0 74 0 107 0 75 0 108 0
^
76 O 109 0 ,
77 0 110 0 78 0 111 0 79 0 112 0
'80 0 113 0 81 'O 114 0 82 0 115 0 83 0 116 0 84 0 117, 0 85 0 118 0 ,
86 0 119 STR-3 87 STR-1 119a STR-3 88 0 120 0 89 0 121 ,
0
^
90 .0 122 0 91 0 123 0 92 0 124 0 93 0 , 125 0 94 0 126 ,
0 95 0 127 0 96 1 0 128 0 97 - 0 129 0 98 0 130 0 99 0 131 0 100 0 132 0 101 0 TMI UNIT 1 TP 600/2
- 11. STR-3
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. :.; a 1.0~.; PURPOSE (cont'd)
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'1.3.4 Conduct an'RCS cooldown to.350*F'at-a rate of-60*F/hr using
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main feedwater.-
1.3.5 Conduct a second RCS' Heatup to 532*F, 2155 psig and allow approximately 11 days for soak time.
d- ,
1.3.6'- ' Conduct a second RCS cooldown to 350*F at 90*F/hr using--
. main feedwater in order to. approach a 140*F dT between the
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1.3.7 Conduct a third RCS heatup. to 532.*F, 2155 psig.and allow approximately 11 days for soak time.
1.3.8- Conduct plant cooldown at 90*F/Hr to 350'F using Emergency
' Feedwater Syste's in order -to achieve a minimum of 70*F AT a4d approach 120*F AT between the OTSG shell and RCS Tave; and to heatup the plant to 532*F 2155 psig.
1.3.9 . Conduct a retest of TP 664/1 - PORV Flow Indication
-STR-3'
. ;.- Functional Test.
1.3.10 Conduct an RCS c'ooldown to approximately 130'F, 300 psig at 90*F/Hr using EP 1202-5, OTSG Tube Leak / Rupture.
.' ~ 1.4 During tihe test sequence, OTSG leakage will be monitored through J'
the'use of the Krypton-85 tracer injected into the Makeup pump suction piping. Additional RCS/0TSG data will be recorded during
,heatups and cooldowns to improve our understanding of tube loads
, and'to confirm our assumptions used in the tube load analyses.
- - t TMI UNIT 1 i
TP 600/2 Effective Page STR-3 Page 2 f
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6.0 LIMITS AND PRECAUTIONS (Cont'd.)
6'. 8 OP 1102-11 Plant Cooldown (Enclosure 4) as modified for this procedure is to be used for all cooldowns, scheduled or unscheduled, for the duration of this test.
6.9 EP 1202-5 (Enclosure 5) as modified for this procedure is to be used only for performance of Section 9.7 of this procedure. Use approved plant procedure EP 1202-5 as directed by Manager of Operations standing order for other than performance of Section 9.7.
6.10 During plant heatup the OTSG shell temperature must be within 60*F of the average tube temperature.
6.11 Do not allow OTSG level to go lower than 18" on startup range during performance'of Section 9.8.
6.12 For plant cooldown at 90 F/hr to 350*F using Emergency Feed-water System the plant administrative limit for maintaining STR-3 the OTSG average tube temperature within 70*F of the average shell temperature during cooldown is relaxed to 120*F.
TMI UNIT 1 TP 600/2 Effective Page STR-3 Page 7a
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1'9.0 TEST METHOD (Cont'd.)
9.6.2 ?In accordance with Enclosure 3 (OP 1102-1, Plant Heatup, as l
-modified.for TP 600/2) perform a plant'heatup to 532*F,-
- l 2155:psig. Monitor OTSG Tube Leakage in accordance with~ !
Enclosure 8-requirements.
' 9.6.3 : Maintain RCS con'ditions are 532*F,-2155 psig for eleven-(11) days.- ,
9.6.A Deleted. ' STR-3 9.6.5 .All necessary OTSG tube leakage' monitoring data has been re-corded and attached to this procedure.
Section.9.6 Accomplished: SAT UNSAT Signature Date-EDII: ~ Perform Section 9.8 prior to performing Section 9.7.
STR-3
- 9.7- Third Plant Cooldown 9.7.1 Initiate the PPMP computer-data collection (Enclosure 7) every ten (10) minutes prior to initiation of'the cooldown and program to collect _ data _ every ten (10) minutes. The time should also be recorded when either RC Pumps or Decay _ Heat Pumps are turned-
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on or off. The data should be taken throughout the cooldown until Tcold is below 150*F and the maximum OTSG shell temperature is less than 200'F. Any additional activities that occur during cooldown that would make a significant change on the OTSG
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Tube-Shell temperature rofile should also be recorded and at the
' completion of the cooldown print out the data collected.
.- Ef fective Page STR-3 Page 18 n' ,
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, 9.0 ~ " TEST METHOD -(Cont'd.).
_ 19.8- Plant Cooldown at 90*F/hr to 350*F, using emergency feedwater,'while-maintaining the OTSG Tube-To-Shell,A T near, but not exceeding 120*F 19.8.1; Initiate the PPMP computer data collection (Enclosure 7)
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ten-(10) minutes prior' to initiation of the cooldown and program to collect data every ten (10) minutes.- The time should also be recorded when either RC Pumps or' Decay Heat Pumps are turned-on or off. The data should be taken throughout the cooldown until Teold is 350*F. Any additional activities that occur during cooldown that would make a significanIt change on the .
OTSG Tube-Shell temperature profile should also be recorded and at the completien of the cooldown print out the' data
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collected. Mark up the computer printouts with the following:-
-Step number,-TP number, initials, date,-page number and. attach as part of Enclosure 7.
9.8.2 Section 9.8.4 will cooldown to 350*F at a rate of 90 +0-10*F/Hr, while approaching the 120*F J1T (Step- 6.l'2) in accordance with Enclosure 4 (OP 1102-11, Plant.Cooldown,
. as modified for'TP 600/2). Monitor OTSG Tube Leakage in '
accordance with Enclosure 8 requirements.
9.8.3 The following prerequisites have been met prior to comrencing cooldown. .
T TMI UNIT 1 TP 600/2 Effective Page STR-3 Page 19b p . -.
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9.0 TEST METHOD /(Cont'd.)-
. -9.8'.3.1 RM-A5 Low is operable and in service for cooldown.
Signature Date 9.8,3.2 Grab sample for offsite analysis'has been taken from RM-A5 line prior to commencing cooldown.
Signature ~ Date 9.8.3.3 collars made and-installed to block EF-V30A and B to prevent complete valve closure (to preclude additional EFW nozzle thermal cycles) and docu-mented per AP 1013.
Signature
, Date STR-3 9.8.3.4 Plant at hot shutdown conditions with four RC pumps running.
Signature Date 9.8.3.5 Cycle valves EF-V30A and EF-V30B open and closed to insure proper operation.
Signature Date 9.8.3.6 Krypton-85 (6 Curies) added to RCS and RCS kr 85 iti equilibrium, based on sample results.
i-Signature Date t
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TMI UNIT 1 TP 600/2 Effective Page STR-3 Page 19c i
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.9 0 ' TEST METHOD'(Cont'd.)
9.8.3.h- Dissolved oxygen concentration of.at least one condensate' storage tank is less than 850 ppb, or
. level agreeable by Operations and Chemistry Departments. -
CST 'A' d.o. ppb CST 'B' d.o. ppb.
Signature Date 9.8.3.8 EFW System valves lined up to pump water from CST with lowest dissolved oxygen to both OTSG's per OP 1106-6 " Auxiliary System Operating Procedures, Emergency Feed".
STR-3 Signature Date 9.8.4 To accomplish the desired cooldown rate of 90'F/ hour and approach the 120*F AT limit proceed as follows:
9.8.4.1 Stop Main Feedwater flow to both OTSG's by closing valves FW-V85A/B, FW-V16A/B and FW-V92A/B and
. reducing feedpump speed to minimum. Startboiling down OTSG's while maintaining constant OTSG pressure and constant RCS Tave and pressure.
9.8.4.2 Insure EF System auto defeat switches in the Control Room are in the ' Defeat' position.
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TMI UNIT 1 TP 600/2 1 Effective Page STR-3 .
Page 19d f,
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- 3. -
- 9.0 TEST METHOD (Cont'd.)
'9.8'.4.3
'When'OTSG. levels reach approximately 30 inches-startup' range.~.with Bailey ICS Controls;in manual-
.for'EF-V30A/B, manually start one' Emergency Feedwater Pump. EF-P-2A (or EF-P-2B). . Insure
- Emergency Feedwater Pump'is operating properly. .
, then trip the Main Feed pump.
NOTE: If' running EW pump' stops, immediately start 'second
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motor driven EFW pump or turbine driven EFW pump.
CAUTION: DO NOT ALLOW OTSG LEVEL TO GO LOWER THAN 18" ON THE STARTUP RANGE.' ,
9.8.4.4 Trip a.,e RCP then gradually adjust Bailey ICS sta-STR-3
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tions (if necessary) and place EF-V30A/B in
' AUTO' if possible, then adjust Turbine-Bypass-valve setpoints to smoothly' decrease the-OTSG pressure in both OTSG's'from 900 psig to 600 psig 1
. to cause Teold to decrease.at approximately 90*F/ hour. Record data as required by Section
.10.8.4.4 il
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9.8.4.5 Monitor average shell temperatures. Teold, and tube-to-shell.4 T every ten (10) minutes.
9.8.4.6 Continue lowering steam pressure to maintain 90*F/hr. cooldown of Teold. If tube-to-shell l
AT approaches.120*F, decrease the cooldown rate to maintain the tube-to-shell 3 T at ( 120* F.
, Effective Page STR-3 Page 19e
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9.0c TEST METHOD (Cont'd.).
9.8.4.7 . Continue cooldown until the RCS T cold is approximately E350*F. Cooldown to T eold 8PProx-imately 330*F-is permissible if it appears desired 70* AT would result.
9.8.4.8 At the' completion"of the cooldown, throttle the Turbine Bypass Valves to stop cooldown; then control EF-V30A/B Bailey ICS stations (auto control preferred) to feed OTSG's'as necessary-to maintain level. Restart Main Feed Pump and establish feed gradually to both OTSG's through STR-3 valves FW-V85A/B then secure EFW pump.
9.8.4.9 Open valves FW-V92A/B and commence gradual refill e of steam generators using FW-V85A/B and/or.
.FW-V16A/B and fill to level specified per Figure 2 on Enclosure 2, page 53/54.
cold 8C 8PProximately 350 F and stable 9.8.4.10 With.
count rate on RMA5 low, perform grab sample from RM-A5 line for offsite analysis.
9.8.4.11 Remove collars from valves EF-V30A and-B that were installed in Step 9.8.3.3, and removal documented per AP 1013.
, Effective PaFe STR-3
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9.0' TEST METHOD (Cont'd)
.9.8.5_ Plant Heatup to 532 F. 2155 psig
.[9.8.5.1 : Initiate the PPMP computer data collection-A (Enclosure 7) every 10 minutes prior to
' initiation of the heatup and program to col - '
lect. data every 10 minutes. The time should also be recorded when either RC pumps or' Decay
-Heat-Pumps are turned on or off. The data should be taken throughout the heatup until hot standby conditions are reached and at the completion of
.the heatup printout the data collected. Mark up-the computer printouts with the following: Step number, TP number, initials, date, page number, STR ,
and attach as part of' Enclosure 7.
V 9.8.5.2 In accordance with Enclosure 3 (OP 1102-1, Plant Heatup, as modified for TP 600/2), perform heatup to 532 F, 2155 psig. Monitor OTSG Tube Leakage in acc~ordance with Enclosure 8 requirements.
(- .
9.8.5.3 ' Collect grab sample on RM-A5 line, for offsite
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analysis, after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> at 532 F.
f l . 9.8.5.4 Maintain RCS conditions at 532 F. 2155 psig.until F
directed to proceed by D. Slear or his designate.
4.
9.8.5.5 At the completion of Step 9.8.5.4, perform TP 664/1 - PORV Flow Indication Retest, to
, verify PORV operability.
. Effective Page STR-3 Page 19g f -
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9.0 ~ TEST ' METHOD _. (cont 'd.) ' ~
'9.8.5.6 'All necessary OTSG tube leakage monitoring data STR-3
, has-been~ recorded and attached to this procedure.-
'Section 9.8 Accomplished: -SAT' UNSAT -
Signature Date r
TMI UNIT 1 TP 600/2 Effective Page STR-3 Page 19h
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10.0' ' DATA REQUIRED' Initials -
- Step- _ _
Acceptance >
. No. Description of Data Required- Data Criteria Org. Date 10,8.4 4 CONTROL [ ROOM
- OTSG Pressure A & B A psig Record .
, . Computer points 0556 and 0557 Data B psig EF-P-2A (EF-P-28) discharging .- Record
- pressure PI-71 (PI-72) psig Data EFW flow EF-FI-788 gym Record Indication Data EF-FI-782 gpm e
- Valvepositionh EF-V30A Record
(% open) <
D***-
EF-V30B % ,
'A' Condensate Storage Tank Level Record
'B' Condeissate Storage T-I- Tank A3 Level ft*
Data
- v. LI-44 ft.
L,0 CAL' Pump suction pressure , ,
PI-69 (PI-70) psig Record Pump discharge pressure Data
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PY-67 (PY-681 Psig Inlet pressure PI-476 (A) psig Record to EF-V30A/B Data PI-477 (B) psig PXI-1154 (A)
, v ri niet psig Record pressure Data PXI-1155 (B) psig Pump suction flow EF-FIS-77 (79) gpm Record Pump bearing flow EF-FI-162A (B) gpm Data l . T!!I LTIT 1 '
. TP 600/2 Ef fective Pace STR-3 Pace 20o y v y --v,-,,.,.#n-e.-m- ,,p.-w._,,w-,-._y-.,,mww.,r.- _, .w.-,,,, . - - . . , , , - . - . . . , , ,.,m.. -
...,,yw, ,,,y .,,n.,, ,.,.r,,%y , .-,-r, , - .7-,w,--,-,-...,--y-
.1
'* E s- '
z; ; 10.O . DATA' REQUIRED
, Initials Step _ _ . Acceptance
.No. Description _of Data Required Data' Criteria Org. Date
~10.824'.'4 .
.(Cont,d) LOCAL (Cont'd.)
-A Condensate Storage Tank Temp F--
Record
.B. Condensate Storage Tank Temp ^F Data Record Emergency feedwater -
Record Pump running - EF-P-2A or EF-P-2B Pump 4
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T"I U::IT 1 l . TP 600/2
- l. Ef f cetive Ps;:e STR-3 >
l Page 20p
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-11.0 ACCEPTANCE CRITERIA 11.1 Acceptan'c criteria for specific tests listed in Enclosure 6 are_ contained in'Section 11.0 of the individual test procedures or in the appropriate enclosures of this procedure.
, 11.2 _ OTSC, tube-to-shell AT of at least 70 F achieved during plant cooldown at 90 F/hr. to 350 F using Emergency Feedwater System STR-3 (Section 9.8).- , ,
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. i I TMI UNIT 1 TP 600/2 Effective Page STR-3
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ENCLOSURE 8 LCPUNC Specification 1101-28-008 Rev. O, is being issued to define the OTSG Leakrate Monitoring Program during hot testigg. The parameters being measured and'the sampling frequencies are as follows:
Parameter-Samp.le Location Frequency Data Sheet #
Krypton-85 RMA-5L (offgas monitor) Continuous - Counts / minute l' to be logged every 15 min-utes during cooldown and every 30 minutes during steady state.
Leakrate calculations must be performed at these times.
2 RCS Daily One hour 1 30 minutes after 2 see each addition of the radio- Note STR-1 active tracer (Krypton-85) 3 One hour 2 30 minutes after 2i each large addition of water (2000 gallons or more) to the RCS during the OTSG hot testing S**
MU Tank (Gas space)
Note STR-8 Following each RCS sampling 2 3 after a Kr-85 injection #
Daily 3A/3B Tritium OTSG Daily 3A/3B Hoewell Daily 2 Gamma OTSG and Hotwell Daily 2 Isotopic- RMA-5L (Grab sample) 1 Hour'(Cooldowns) h ( See Analysis RMA-SL (Grab sample)* 4 Hours (Steady State) 2/ Note STR-3 RMA-5L (Grab sample) Every 2 gph or more increase 2 l3 over a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or less as calculated from the RMA-5L (offgas monitor) count rate.
DATA SHEET 4 - Primary to Secondary Leak Rate Calculations.
Fill out Data Sheet and Compute P/S Leak Rates whenever Kr-85 grab samples at RM-A-5. Low are taken.
1 Log'the average count rate for the 15 minutes (30 minutes during steady state) since the last reading, on Data Sheet 1 and compute the primary to secondary leak rate using the most.recent RCS Kr-85 activity, condenser vacuum pump exhaust . flow rate, and formula g g, .:. (s.4 = soWce*4.Er.Foom6(Rm AS =tc .h l STR-1 2 Nc6 UII W" YY
3 TMI UNIT 1 For performance of Sections 9.8 and 9.7 see revised analysis TP 600/2
. frequencies on Enclosure 8. Page 119a. Enclosure 8, 1/
Effective Page 37p.-
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The following changes to the sampling and analysis frequencies are required for the remainder.of.the OTSG Hot Testing Program; for analyses listed below !
all other samples to be' performed per Enclosure 8, Page 119. *
- 1) Sample .and analyze .the Reactor Coolant System for krypton-S5 approximately three (3) hours after krypton-85 addition and every- four'(4) hours after that for twelve (12) hopps. Reduce
. this frequency to once per day thereafter. The Kr-o- will be ,
considered to be in equilibrium when two consecutive Kr-85 analyses are within + 15% _
- 2) Sample and analyze the RCS make-up tank fo krypto n-85 approxim.*ely six (S) hours after krypton g5 addition. ,
- 3) RM-A5 (Low) samples for outside vender analysis, a) steady state - 3Neek Mon., Wed., and Fri.
b) cooldowns - three (3) samples required.
- 1. c. ample within four (4) to e ght (8) hours of the start of the cooldown after Kr jU has reachedOne (1) equilibrium in RCS. '
- 2. One (1) sample with RCS at 3500F..
- 3. One (1) sampla twelve (12) hcurs after the RCS is hected to 5320F.
- 4. Rit-A5 ('.ow) samples for cite analysis:
As a result of the low activity of these. samples, thus far,
.. th is requirement for sampling is unnecessary and ma'y be suspended.until R!l-A5 (Low) exceeds 1000 cpm or other signs indicate a high enough leakrate to produce >6 x 10-b pC1/cc of krypton-SS activity in the condenser exhaust.
The increased RCS sampling after krypton-85 addition is to provide sufficient data prior -to the cooldown f or increased statistical certainty of l the reactor coolant krypton-85 activity. Therefore, the krypton-85 must be added at leas ~t 15 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the cooldown.
A0000448 TMI UNIT 1 TP 600/2 Enclosure 8, 2/ -
Effective Page STR-3 Page 119a
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DETAILS ~
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- 1. ~ Persons Contacted .
Gen 1 Public Utilities (GPU) Nuclear Corporatiori 4 #
R. Bar ey, Lead Mechanical Engineer \ b
//2e4AN R. Corb , Site Weld Engineering Supervisor
\ '.-
- J. Colit Plant Engineering Director, TMI-1 R. Fenti, C. Manager ~
S. Giacobbe, Materials and Welding Manager (Reading,
- H. Hukill, V. . and Director of TMI-1
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C. K. Lee, Sup visor, Pressure Components (Parsippt !! .J . )
- D. Landan, QA/Q - OTSG Repair d,']d/
/
- S. Pru'tt, THI-IS Supervisor a. J-[/ 4 g 'p
- S. Levin, Acting D ector, Maintenance and Construe: 5
- R. Szczech, TMI-1 Li insing / '
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- C. Smyth, Supervisor I-1 Licensing t
\N M. Torborg, ISI Program ngineer ,
U. S. Nuclear Regulatory Co
- R. Conte, Senior Resident Insp tor ssion f
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- F. Young, Resident Inspector '
- Indicates.present at the March 24, 83 Exit Interview. /
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- 2. Licensee Action on Previous Inspection ndings ; i ,
h,0 (open) Licensee Identified Item (289/81-LO-13), steam' generator repaira tube plugging in progress during this inspection. Inspection of steam generator repair activities-for this report are covered in paragraph 3.
sf bibo P Inspection of final stean generator repairs, H 022 cleanup, cold
~
pressure tiis~ ting and hotiunctional testing activities is intended during j // and after completion of these steps h g g I
(J 'This item remains open pending satisfactory completion of required
- recovery tasks.
- 3. Steam Generator r and Recovery Activities 3 d Background dW b8@ At the start of this ins ection the tubes of st.
A and B had been kinetical expanded in the up 32nerators(OTSG)
'ubesheets and 84> 2 L the post expansion tube flush g operation was iete. Tube
' f- stabilizer insertion as require for certain ti. :o be plugged was ube ple'g D p,,u , , in. progress with final preparatio s being made
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l correction or re ir and the work toward.s completion L a been in pro-gress. The Safety valuation Report dated December.10. 2982, portions of which are proprietar include the OTSG tube failure i ysis; prevention of recurrence; and, s ary of tube' repair process as essary to :
l Ecomplete adequate correc ve measures. This item is c d.
j{lD~(Open) Licensee . Identified ItemL(298/81-LO-13). Work - area ir of steam generator repair including tube expansion; post repai. __nup; tube end mil ((ng,plugg,ing,.coldtesting;RCSH032 cleaning if mired; and, hot' functional testing are the remaining. topics for c- + ion and inspection during the steam generator recovery procer !
This item remains open pending satisfactory completio: required recovery tasks.
-(Closed) Inspector Fo1 w Item (289/80-04-03). Fire ha: ; analysis of cable butt splices. Th inspector reviewed the fire L; trd analysis for
. task RM-1, Heat Shrink T ing/ Butt Splicing Inside Reactor Building. The analysis concluded that th addition of butt splices hts no significant
' effect on the fire loading f various areas in which t'he splices are located. Discussions with r sponsible licensee personnel indicated that the fact that the red sealant used.in conjunction with the heat shrink-able tubing is combustible was onsidered in the analysis, however the
- amount of combustible material ded to a fire area by butt splicing.in relation to the . area total ~ fire ading was found to be insignificant, This item is closed.
(Closed). Inspector Follow Item (289 0-04-05h Documentation of quality control inspection criteria for engi ering change memoranda. The inspector reviewed the licensee's Pro am for documenting Quality Control (QC) inspections and discussed the pro ram with QC personnel. Engineer- !
ing Change Memoranda (ECM), which requi QC inspection, are denoted as such on the ECM cover sheet. The QC org ization then determines what inspections are required and documents th se inspections on QC Plant Inspection Reports. The inspector reviewe QC activities for several modification packages and noted no discrepa cies. This item is closed.
(Closed) Unresolved Item (289/80-05-03).- Proce ure for LOCA qualified cable splices does not incorporate manufacture 's recommendations. The inspector reviewed selected portions of task R ,1 and noted that the installation procedure for butt splicing requirdd that ctble surfaces be cleaned.with isopropyl alcohol prior to the appitcation of heat shrink sleeving as recommended by-the manufacturer. This. rear: cement is also contained in the licensee's Corrective Maintenance Yrec::ure 1420-Y-24, b Installation of Ray-Chem Splices, Revision 0. FurthVi formation concerning this ' item is discussed in NRC Inspection i ; 289/82-02, paragraph 2,. item 289/80-04-02. The inspector concit
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that the licens-ee's procedures adequately address.the manufacturer's .cmmendations and had no further questicas. This item is closed.
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Region I Form 2 (Revised February 1977)
[md "!
POST-INSPECTION COVER SHEET DATE SUBMITTED: 19 FROM: b bh6/
(Reporting I'nspector)
RE: 2 69/PJ -2.f on 9//P- 9/ /83 (Inspection No.) (Dates of Inspection)
To: 5 lhM ll?)$ hb-l (Reporting Inspector's Supervisor) (Facility Identification)
/)V The facility project inspector has been informed of the inspection results.
// Inspection Report is completed and ATTACHED.
/X/ hrRepo ~
ave been completed, reviewd by author's supervisor, and are a ccocnea - u su yy g 7f g 1,
2.
3.
///k// Duuumentation letter completed and attached (a- standard form with new or modified paragraphs desired).
N/ List of updated outstanding items completed. For Materials, license folder attached (list will be with it).
/h Statistical Data Sheet completed a'nd ATTACHED.
/X/ Inspection Plan as corrected, ATTACHED for Branch Files.
- g/A A/ Inst for Gray Book / Yellow Book submitted to Project Inspector.
Additional Comments:
brl Q (Reporting Inspector)
File:
Reporting Inspector's Branch NOTE: Cross out and initial sections not applicable.
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PRE-lh5PFCTION COVER SHEET (Region 1 Work Form)
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Report No. fo-2.69! 8 3 17 From: _(Reporting Inspector) *
.N S toct.Tof G AC To: T b u f"f-(Reporting Insp:ctor's Supervisor) ) g* y'C /t . Q"
. -7"
- Subj: INSPECTION OF 7h//I f/ /
- (Facili ty)
ON 7h9- ?/21/S3 (Dates)
/ -/ List of outstanding items up to date, reviewed and proper items selected.
/X/ Inspection plan completed (attached or sumarized below).
Inspection Items:
S l- l. 0 -/3 ~ .S~.d. <'. int s l/?uAsiz /?z,cits-mfNSFktYatis 9 2 e 6- e / -if C S & + .c: e hs~ncsnew cwm widM*wt wec4m.
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/l. dia nt:b- h cass a Of HCea.c s/t.lQ dded ( sto -treassiss fp/g 3 t'oy3-o?-o 3 o 7-oIL- os3
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NAMES OF ACCOMPANYING PERSONNEL: RESIDENT INSPECTOR NOTIFIED: #5 /i/evud eb If>3 Project Section Chief
" *e
,/ ACKNOWLEDGED:
/YO N 4 - - -
Project Inspector ACKNOWLEDGED: A-Accompanying Inspector's Supervisor (if applicable)
SUBMITTED: [' '8'A7 - APPROVED: ,,u /
Reporting Inspector geporting Inspector's Supervisor File:
Branch Files (Inspector's Branch and Project Branch) l Hotel: NAexiseu, eat / b$.s 7- Phone: ( ) -
FTS: 9-7/7-93 9~ 78 Y/
SiteContact(Name)I.Noac, Phone: ( ) -
FTS: 59 0- //ff' Region I Form 1 (Nov1979)
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.. , - i-U. 5. NUCLEAR REGULATORY COMMISSION REGION I fgj,sy;/
g, p/g.w a Report No. .f'O' ? 99/4 3 - 2 f'
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' Docket No. 5"0-2 89 License No. p 8A. - 70 Priority --
Category C
. Licensee: A/ 0U YJCCfAA Co/EsenA7torf c
it). hex 4'80 l)> Aet L 7' e wH , b'wN 5 ft. V/fN/A l)#~'~ I Fac11ity Name: &att. Mn.t 2~sANc / Vacc.gsA S y riost L/tv/7 pl Inspection At: Niege_t;ow ffwivsye virassy Inspection Conducted: _f/// Yen 3/<f. /9- 2./,, / 9 6 3 Inspectors: ~
, date
- f. /f' d4 A y, l(An AtAt7CA sit *N4tw///2. date date Approved by:
0 J. P DJ/M - CHis /' Mim/Aes A+c/,4ecs'rics S~ey/oy r date Inspection Summary: .7e' p e7s/ w *U JQ W Zm sf^i', /f- Z/, /993 (.7'vgprc i rio st-AtfoR7'/Yndtst To - 299/83-w).
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