ML20214E075
| ML20214E075 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 03/03/1986 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 5211-86-2010, NUDOCS 8603070073 | |
| Download: ML20214E075 (96) | |
Text
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Route 441 South Middletown, Pennsylvania 17057-0191 l 717 944 7621 l TELEX 84 2386 j Writer's Direct Dial Number:
March 3,1986 5211-86-2010 i Office of Nuclear Reactor Regulations Attn: John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Stolz:
l Thrce Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. OPR-50 Docket No. 50-289 Inservice Testing of Pumps & Valves (IST) i The purpose of this letter is to supplement our July 10, 1984 submittal of l GPUN's program for Inservice Testing (IST) of punps and valves whose function is required for safety. This submittal provides additional information and commitments in response to NRC requests from our meeting in Bethesda on September 4-5, 1985 and conference calls on October 24 and 29,1985.
Attached are Tables A, B, and C. Tables A and B describe the revised punp and valve test program. Table A applies to all Class 1, 2, and 3 pumps which are provided with an emergency power source. Subtable A-1 describes the pump testing program. Subtable A-2 provides GPUN's request for relief from ASME Code Section XI punp test requirements along with justification for the relief. Table B applies to all Class 1, 2, and 3 valves. Subtable B-1 describes the valve testing program. Subtable B-2 provides GPUN's request for relief from ASME Code Section XI valve test requirements along with justification for the relief. Subtable B-3 lists limiting values of stroke times for motor-operated valves included le the IST program. Copies of the latest revision to the IST drawings referen'.ed in Tables A and B, along with Piping and Instrumentation Drawings (P& ids) were provided prior to our meeting of September 4-5, 1985.
Table C along with the photographs (9 per set) provide the results of more recent disassembly and inspection of valves to supplement our disassembly report which was submitted on June 13, 1984 Subtable C.1 provides the disassembly results and valve information in tabular form. Subtable C.2 is an )
index to the photographs. All of these valves were disassembled for IST l l purposes and were found in excellent condition (no unusual corrosion, loose '
l parts or wear were observed). All photographs show the "as found" condition. l The valves were reassembled with no replacement parts required except for gaskets. 0603070073 060303 PDR
(
ADOCK 05000207 l
, P PDR 'fl GPU Nuclear Corporation is a subsidiary of tno uuneral Public Utilities Corporation 1
5211-86-2010 March 3,1986 Your letter of July 15, 1985 requested additional information to support the relief requests included in our program submittal of July 10, 1984 Our letter of August 22, 1985 addressed NRC's list of questions each of which were discussed in our September 1985 meeting. Additional discussion continued in conference calls on October 24 and 29,1985. With the exception of those issues (PIV issues) which were identified as generic backfits for operating plants in a meeting of the NRC Committee to Review Generic Requirements (CRGP,)
on July 24, 1985 the remaining issues from GPUN : March 19, 1985 letter of appeal were included in the agenda for the September 4-5, 1985 meeting and the discussions which followed on October 24 and 29,1985. It is our understanding that the technical resolution of these issues which resulted from the discussions as reflected in the revised IST program Tables A and B, along with the informtion provided in Table C will close all of the Amendment 71 SER open items with the exception of the PIV issues.
Those issues raised in your latter of July 15,1985 which 5: ave not resulted in changes to the IST program in Tables A and B or which we are presently unable to address fully are as follows:*
1.) AH-V11 A/B and NS-V108A/B (E.1 and V.4) - These valves regulate cooling water to the air conditioning system that cool the Control Tower. GPUN is in the process of developing a Probabilistic Risk Analysis (PRA)
Program for THI-1. As part of this program we are evaluating the impact i that the loss of the Control Building Chilled Water System would have on l Control Building temperatures. The results of this study will show if j the failure of these valves is tolerable or if the operability of these l valves is required. This study is scheduled for corpletion by June 30, 1986 If the study demonstrates that operability of these valves must be preserved, then a program and schedule for testing these valves will be developed to support the IST program.
I 2.) AH-V3A/B (E.1) - These valves regulate cooling for Containmnt concrete at the Main Steam and Feedwater penetrations. These valves are not needed to achieve cold shutdown or to mitigate an accident. Therefore, they need not be included in the IST program. If AH-V3A/B were to m1 function or if temperatures were to approach the limit, the valves would be repaired / opened or continued plant operation would be evaluated to determine if the plant should be shutdown. AH-V3A/B are an operational concern not related to plant safety.
3.) AH-V16 (E.1) - This valve regulates cooling to the first floor of the Control Tower when the Control Tower is on recirculation. There are no components on the first floor of the Control Tower that are needed to achieve cold shutdown or mitigate an accident. Therefore, AH-V16 need not be included in the IST program.
- Question numbers from NRC's letter of July 15, 1985 appear in parentheses, i
5211-86-2010 March 3, 1986 4.) RC-RV2 (AA.3) - The PORY provides low temperature overpressurization protection of the RCS. Currently GPUN tests the electrical circuitry and setpoints of the PORV. The solenoid and pilot valve plunger is cycled, but during this test the block valve remains shut and the main disc does not open. During our meeting on Septerber 4-5, 1985 GPUN was given a copy of a draf t ANSI /ASME standard OH-13 entitled " Requirements for Periodic Perforence Testing and Monitoring of the PORV." GPUN does not conclude that this standard should be adopted while it is still in draf t form. Also, Owner Committee 1154 is currently studying the appropriate testing requirenents for the PORV. Upon completion of this study, GPUN will resolve this issue based on recommendations from the committee.
5.) Spent Fuel Cooling Valves that Supply Makeup to the Spent Fuel Pools (B8.1) - There are several redundant methods of providing rakeup to the spent fuel pools. The method employed normally about twice yearly in making up losses to the spent fuel pools uses manual Reclaimed Water valves and a short length of hose. An installed system monitors the seam welds for leakage at least daily. This monitoring allows for early detection of weld seam leakage and sufficient time to make use of one of the manual mthods of spent fuel pool makeup. Therefore, spent fuel pool mkeup does not need to be added to the IST program.
During the 120-mnth testing program which is applicable f rom September,1984, until September,1994, GPUN is required by 10 CFR 50.55a(g)(4)(ii) to follow the ASME Boiler and Pressure Vessel Code Section XI Division I,1980 edition and addenda through Winter,1980. In addressing the applicable ASME Code Edition and Addenda, GPUN is required by 10 CFR 50.55a(g)(5)(iv) to demonstrate the bases for the determination where inservice testing code requirements are determined to be inpractical. This is to be demnstrated to the satisfaction of the NRC not later than 12 months af ter the expiration of the initial 120 month period of operation from start of facility commercial opera tion. Your letter of December 11, 1985 allowed that the staff would consider the 12-month " clock" to begin at restart. Since restart occurred on October 3,1985, we understand that we must obtain the necessary relief from Code requiremnts prior to October 3,1986. However, if additional modifications to plant equipment become necessary in order to support IST resul ti ng f rom: PRA recommndations, resolution of those issues which are currently under review, or denial of relief requested as part of this submittal; additional time would be needed to allow sufficient time for installation of any such modifications.
The Inservice Testing Program which is described in Tables A and B is permitted by the current Technical Specifications and no Technical Specification changes are required. Therefore, GPUN sees no conflict between THI-1 Technical Specifications and the updated Inservice Testing program and concludes that Section 50.55a(g)(5)(ii) of the regulation has been met.
i This re-submittal will require changes in the IST Program implementing procedures. All of these changes will become effective no later than six
, months from the date of this letter.
, 5211-86-2010 March 3, 1986 We are currently re-e/aicating the Screen House Ventilation System to detarmine if the cooling water supply equiptent performs a required safety related function. If it is concluded that this equipment does not perform a required safety related function, it will be deleted from the IST program.
Requests for any additional relief, resulting from future plant design modifications which become necessary during the interval for which this program is applicable, will be requested as necessary through future correspondence. However, GPUN does not view changes to the IST program which any becoce necessary as requiring a submittal other than through the reporting requirements of 10 CFR 50.59 unless additional relief from ASME Code Section XI requirements or changes to the Technical Specifications becone necessary.
Sincerely, f .
H. D. Hukill, Director, TMI-1 HDHMIRK/vimv Enclosures tc: J. Thorn, HRC, Licensing Project Manager R. Conte, NRC Region I Senior Resident Inspector H. Rockhold, EGAG Idaho l
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TABLE A THREE MILE ISLAND UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
I. SCOPE AND OBJECTIVES This table describes the Inservice Inspection Program for all Class 1, 2, and 3 pumps which are provided with an emergency power source. The objective of this program is to provide assurance of the operational readiness of these pumps during their service life.
II. APPLICABLE ASME CODE EDITION AND ADDENDA In accordance with 10 CFR 50.55a(g)(4)(li), the applicacle Code Edition and Addenda are the 1980 Edition with Addenda through Winter, 1980.
III. PERIOD OF APPLICABILITY In accordance with 10 CFR 50.55a(g)(5)(iv), this program is applicable from September, 1984 to September, 1994.
IV. Ir4SPECTION PROGRAM The inspection program, which is detailed in Table A-1, will be carried out in accordance with ASME Code Section XI, 1980 Edition with Addenda through Hinter, 1980. Specific exceptions to the ASME Code Section l
XI requirements for each component are identified in Table A-2 along with the basis for each exception l requested.
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TABLE A-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
PAGE I of 3 PUNP FLOW ISI TEST QUANTITIES MEASURED
- TEST ;
PUMP NAME NUMBER (S) DIAGRAM DRAWING N Pi 5 T V LUBR. Tb ** INTERVAL LEVEL CONTROL AH-P3A C-302-847 ID-ISI-FD-Oli X X X QUARTERLY BUILDING AH-P3B CHILLED WATER SUILDING BS-PIA C-302-712 ID-ISI-FD-012 X X X X X X QUARTERLY l SPRAY BS-PIB BORIC ACID CA-PIA C-302-670 1D-ISI-FD-021 X X X X PLANT REFUELING .
CA-Pla INTERVAL DECAY HEAT DC-PIA C-302-645 ID-ISI-FD-003 X X X X X X QUARTERLY CLOSED COOL- DC-PIB ING HATER DECAY HEAT DH-PIA C-302-640 10-ISI-FD-005 X X X X X X QUARTERLY REMOVAL DH-PIB DECAY HEAT DR-PIA C-302-202 ID-ISI-FD-002 X X X QUARTERLY ,
I RIVER HATER DR-PIB SEE ASME SECTION XI FOR DEFINITION OF TEST QUANTITIES !
- BEARING IEMPERATURES WILL BE MEASURED YEARLY PER ASME SECTION XI, IWP-3300 1575X/pe
TABLE A-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS) '
PAGE 2 of 3 PUMP FLOW ISI TEST QUANTITIES MEASURED
- TFST '
) PUMP NAME NUMBER (S) DIAGRAM DRAHING N Pt 3P Q V LUBR. Tb** INTERVAL i
LEVEL i
EMERGENCY EF-P1 C-302-082 10-ISI-FD-009 X X X X X X X QUARTERLY i FEEDWATER (TURBINE ORIVEN)
EMERGENCY EF-P2A C-302-082 1 D-ISI-FD-009 X X X X X X QUARTERLY FEEDhAIER EF-P2B (MOTOR DRIVEN)
MAKE-UP AP.D MU-PIA C-302-661 1D-ISI-FD-017 X X X X X QUARTERLY PURIFICATION MU-PIB MU-PIC NUCLEAR SERV. NR-PIA C-302-202 ID-ISI-FD-002 X X 00ARTERLY RIVER WATER NR-PIB NR-Plc X X X PLANT REFUELING INTERVAL C-302-610 1D-ISI-FD-010 X X X X X X QUARTERLY, TWO PUMP !
NUCLEAR SERV. i:S-PIA NS-PIB COMBINATION TESTING CLOSED COOLING HATER NS-PIC X X X X X PLANT REFUELING l INTERVAL, SINGLE i I
PUMP TESTING i
SEE ASME SECTION XI FOR DEFINITION OF TEST QUANTITIES. I
- BEARING TEMPERATURES WILL BE MEASURED YEARLY PER ASME SECTION XI, IHP-3300 .
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TABLE A-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
PAGE 3 of 3
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PUMP FLOW ISI TEST QUANilTils AEASURED
- TEST PUMP KAME NUMBER (S) DIAGRAM DRAWING N Pg aP Q V LUBR. T**
b INTERVAL LEVEL REACTOR BLDG. RR-PIA C-302-202 1D-ISI-FD-002 X X OUARTERLY !
EMERGENCY RR-PIB COOLING X X X PLANT REFUELING INTERVAL SPENT FUEL SF-PIA C-302-630 1D-ISI-FD-018 X X X X X 00ARTERLY COOLING SF-P2A SCREEN HOUSE SH-P2A C-302-203 1D-ISI-FD-002 X X 00ARTERLY VENTILATION SW-P2B EQUIPMENT X X X X OUARTERLY BORIC ACID WDL-P13A C-302-692 ID-ISI-FD-021 .
RECYCLE WDL-P138 X X X X PLANT REFUELING INTERVAL SEE ASME SECTION XI FOR DEFINITION OF TEST QUANTITIES
- BEARING TEMPERATURES WILL BE MEASURED YEARLY PER ASME SECTION XI IHP-3300 NOTE: GPUN has determined that the Screen Wash and Slutte Pumps (SW-PIA /B) are not needed to achieve cold shutdown or mitigate the consequences of an accident since aP across the screen is alarmed and if necessary manual means can be employed to wash the screens. Therefore, these pumps have been deleted from this submittal. SW-PIA /B are supplied with emergency power but this is a convenience since the only power available in the Screen House is emergency power. Therefore, per ASME Section XI, IHP 1200(b), they are encluded from IST.
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TABLE A-2 l THREE MILE ISLAND - UNIT NO. 1 l PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS) ;
EXCEPTIONS TO ASME XI REQUIREMENTS PAGE 1 of 9 ASME III ASME XI CODE CLASS ASME XI EXCEPTION TESTING PERFORMED IN LIEU PUMP MAME PUMP NO. CODE CLASS EQUIVALENT REQUESTED
- JUSTIFICATION OF CODE REQUIREMENT CONTROL SUILDIf4G AH-P3A 3 Non-Nuclear Q See Note 3 Flow metering will be i CHILLED WATER AH-P3B installed prior to startuo for Cycle 7.
Tb See Note 13 None Lubr. Level See Note 13 None BUILDING SPRAY BS-PIA 2 N-2 None N/A N/A ,.
SS-PIS BARIC ACID CA-P1A 3 Non-Nuclear Quarterly Testing See Note 12 Refueling interval testing. !
CA-PIB Q See Note 12 0 will be calculated.
Pt See Note 12 Pt will be calculated AP See Note 12 None Tb See Note S None i Five Minute runtime See Note 12 Run until system is stable.
DECAY HEAT DC-PIA 3 Non-Nuclear None N/A N/A CLOSED COOLING DC-PIB ,
i RATER DECAY HEAT DH-PIA 2 N-2 None N/A N/A REMOVAL DH-PIB DECAY HEAT DR-PIA 3 Non-t!uclear V See Note 1 Motor vibration will be RIVER WATER DR-PIB measured.
Tb See Note 2 None ,
Lubr. Level See Note 2 None
- SEE ASME SECTION XI FOR DEFINITION OF TEST QUANTITIES
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TABLE A-2 '
THREE MILE ISLAND - UNIT NO. 1 -
PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIREMENTS PAGE 2 of 9
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ASME III ASME XI CODE CLASS ASME XI EXCEPTION TESTING PERFORMED IN LIEU PUMP NAME PUMP NO. CODE CLASS EQUIVALENT REQUESTED
- JUSTIFICATION OF CODE REQUIREMENT EMERGENCY FEED- EF-P1 2 Non-Nuclear Scale Range for See Note 9 Flowrate will be a measured l HATER (TURSINE- flow meter test quantity using the in-DRIVEN) stalled flow meter.
EMERGENCY FEED- EF-P2A 2 Non-Nuclear Scale Range for See Note 9 Flowrate will be a measured
, KATER (MOTOR- EF-P2B flow meter test quantity using the in-DRIVEN) stalled flow meter.
MALE-UP AND MU-PIA 2 N-2 Q See Note 8 N/A r
l FURIFICATION MU-PIB MU-Plc l
! MUCLEAR SERVICE NR-PIA 3 Non-Nuclear Q See Note 6 Will be measur ad during l RIVER WATER NR-PIB plant refueling outages. l l NR-Plc V See Note 1 Motor vibration will be [
measured.
Tb See Note 2 None ,
Lubr. Level See Note 2 None P&JCLEAR SERVICES NS-PIA 3 Non-Nuclear Single Pump See Note 10 Single pump testing will be :
CLOSED COOLING NS-PIB Testing performed during each NS-Plc refueling outage. '
REACTOR BUILDING RR-PIA 3 Non-Nuclear Q See Note il Q will be measured during RR-PIB plant refueling outages.
EMERGENCY COOLING V See Note 1 Motor vibration will be measured.
Tb See Note 2 None l Lubr. Level See Note 2 None ,
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- SEE ASME SECTION XI FOR DEFINITION OF TEST QUANTITIES j 1576X/pe
TABLE A-2 THREE MILE ISLAND - UNIT NO.1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIREMENTS PAGE 3 of 9 ;
ASME III ;
ASME XI CODE CLASS ASME XI EXCEPTION TESTING PERFORMED IN LIEU PUMP KAME PUMP NO. CODE CLASS EQUIVALENT REQUESTED
- JUSTIFICATION OF CODE REQUIREMENT ,
SPENT FUEL SF-PIA 3 N-3 Pt See Note 4 Pt will be calculated. !
SF-PIB AP See Note 4 aP will te calculated.
Tb See Note S None l
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SCREEN h0USE SH-P2A 3 Non-Nuclear Q See Note 3 Flow metering will be install- [
SW-P2B ed prior to startup for VENTILATION .
EQUIPMENT Cycle 7. !
V See Note 1 Motor vibration will be measured.
Tb See Note 2 None Lubr. Level See Note 2 None BORIC ACID WDL-P13A 3 Non-Nuclear Q See Note 12 0 will be calculated on a re-WDL-P13B fueling interval. i RECYCLE P5 See Note 12 Pg will be calculated.
AP See Note 12 AP will be calculated during the quarterly test.
Tb See Note S None 5 Minute runtime. See Note 12 Run until system is stable. ;
Thrcttling to a See Note 12 AP and flow rate data will reference value, be compared to the manufact-I urer's capacity curve.
- SEE ASME SECTION XI FOR DEFINITION OF TEST QUAN!ITIES !
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TABLE a-2 THREE MILE ISLAND - UNIT NO.1 PERIGOIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIREMENTS Page 4 of 9 JUSTIFICATION NOTES .
kote 1 This is a vertical deep well type pump with the pump submerged under water at all times. It is not practical to measure pump vibration in this type of installation. Past operating experience has shown that motor vibration is indicative of pump mechanical problems in this type of installation. Therefore, motor vibration will be measured in lieu of pump vibration.
Note 2 Inis is a vertical deep well type pump with the pump submerged under water at all times. Pump bearings are lutricated by the fluid being pumped. There are no installed means of measuring bearing temperature and the pump design and installation makes it impractical to measure in any other manner.
Note 3 There are no flow meters installed in the flow path of this pump. Therefore test quantity "Q" cannot be measured. Prior to start-up for Cycle 7 GPUN will install flow metering for these pumps.
Note 4 For SF-PIA /B there is no pump inlet pressure gage tap. Test quantities Pi and AP cannot be measured.
SF-PIA (B) take suction from the Spent Fuel Pools. The pool water level is alarmed high at 40 feet (347' elevation) and alarmed low at 38.5 feet (345.5' elevation). This is only a 1.5 foot (0.65 psi) difference.
Therefore. SF-PIA /B suction pressure is nearly constant (can vary only by a maximum of 0.65 psig and this maulmum difference in level is less than a 1 psig typical minor scale division). Since Pi cannot be measured, it is calculated based on the water level in the pools.
Since suction pressure is relatively constant and can be calculated with reasonable accuracy, a suction pressure gage is not needed to determine the operational readiness of SF-PIA /B.
This method of testing meets the intent of the ASME Code Secticn XI test requirements and ensures the operational readiness of these components without directly measuring AP or P . aP and Pt will be 3
calculated based on the water level in the pools.
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TABLE A-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIREMENTS Page 5 of 9 JUSTIFICATION NOTES (Cont'd)
Note 5 Pump tearing temperature cannot be measured on this pump since the bearings are located deep inside the pump ca<;ng and are surrounded by an oil reservoir. An exception is requested per 10 CFR 50.55a(g)(5)(lii) in tnat measurement of parameter Tb is not practical within the limits of the design of this pump, kate 6 Flow metering for this system is located in the common discharge lines from all three pumps. Plant operating heat loads require the operation of at least two Nuclear Service River Water pumps during normal plant -
operation, thereby making it impossible to measure flow for a single pump. Pump flow will be measured for each pump during plant refueling outages when operation of only one pump is required.
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_ Note 7 (Note 7 has been deleted)
Note 8 ,
1 Installed plant instru7entation does not allow measuring the. flow rate,for each ficw path for these pumps. I Therefore, testing is performed using a combination of fixed rettstance and reference value flow rate; Seal " '
~, 'njection is held at 32 gpm. Normal makeup is isolated with 3.5 gpm through HU-V205 and the minimum recirculation line (MU-V36 and 37) is cpen providing fixed-resistance. Q is the independent variable and AP is the dependent variable. This testing method is allowable per ASME Section XI IWP-3100.
Note 9 Ine Emergency Feedwater Pemps (EF-P1 and EF-P2A/B) are tested on recirculaticn td the Condensate Storage Tanks. Installed orifices limit flow rate to a fixed value of -190 gpm for EF-Fi and -90 gpm for EF-P2A and B. O is the independent variable and AP is the dependent variable. For EF-Pl. flow rate is read on ' ,
flow Indicating Switch 78 (FIS-78). FIS-78. scale range is 0 to 1000 gpm. For EF-P2A and B, flow rate is read on FIS-77 and FIS-79. FIS-77 and 79 scale range is O to 500 gpm. FIS-78, 77, and 79 do not meet ASME Section XI, IWP-4120 which states "The full-scale range of each instrument shall be three times the reference value or less." celief is requested from IWP-4120, which states that flow instruments are to be calibrated to 221 of full scale range. The basis for requesting relief is that FIS-78, 77 and 79 will be calibrated 1576XIpe
TABLE A-2 THREE MILE ISLAND - UN!T NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIREMENTS Page 6 of 9 JUSTIFICATION NOTES (Cont'd) such that one of the calibration points will be 200 gpm for FIS-78 and 100 gpm for FIS-77 and 79. This will insure that 221 accuracy is achieved at the reference value of -190 gpm for EF-P1 and -90 gom for EF-P2A and B. All other code calibration requirements per IWP-4000 will be met. FIS-78, 77 and 79 are located on the suction piping to EF-P1 and EF-P2A/B. It is impractical to reduce the scale range of FIS-78, 77 and 79 since emergency feedwater flow rates when feeding the OTSG(s) are much greater than the IST reference flow rate values. If the FIS scale range were sized for IST testing purposes, the FISs would be over-ranged and damaged when EF-P1 or EF-P2A/B were used to feed the OTSG(s). In conclusion, calibrating such that one of the calibration points is at 200 gpm for FIS-78 and 100 gpm for FIS-77 and 79 insures that the acceptable accuracy of 221 is achieved for the IST Test.
Note 10 Flow metering for this system is located in the common discharge lines from all three pumps. Plant operating heat loads require the operation of at least two Nuclear Services Closed Cooling Water Pumps during plant operation thereby making it impossible to measure flow for a single pump. Therefore, two-pump testing will be conducted on a quarterly frequency. Three two-pump tests will be performed as follows: 1.) pumps A and B 2.) pumps 6 and C, and 3.) pumps A and C. Two-pump testing will be conducted in accordance with the requirements of ASME Section XI, Subsection INP except that a reference value for Q or AP will not be established per IWP-3100 and 3110.. Also Table INP-3100-2 will not be used for acceptance criteria. Two pump testing will be conducted such that Q will be measured. This data point of AP and Q will then be compared to the pump manufacturer's capacity curve. Acceptance criteria will be 2101 of the manufacturer's curve.
If the 2101 criteria is not achieved, an analysis will be made to demonstrate that pump cperability is not impaired and the pump will still fulfill its safety function. If the analysis cannot support the operability of the pump, the pump will be repaired or replaced.
The two pump test is performed during normal plant operation and it is impractical to establish reference values because the Nuclear Services Closed Cooling Water System (NS) is a very large system (52 component coolers) that is operated over a range of flow rates. By procedure (OP 1104-11) the NS flowrate is varied to maintain the water temperature >70*F but <95*F. The 'ower limit is to prevent condensation on the NS piping and the upper limit is to prevent component cooler overheating. River water temperature, and outside ambient temperature require the number of NS Heat Exchangers and component coolers to be throttled or varied. In addition, plant operations such as processing radwaste may require additional NS heat exchangers. These operational conditions make it impractical to establish a reference value since the reference value must 1576X/pe
TABLE A-2 THREE MILE ISLAND - UNIT NO. 1 l PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIREMENTS Page 7 of 9 JUSTIFICATION NOTES (Cont'd) be established such that operational parameters are not upset. In addition, several sets of references valves may not cover all of the operating modes for the NS system. Testing with several sets of reference values would be cumbersome. Therefore, the above testing will'be conducted as an alternative; and technically, this testing is equivalent to the code requirements. Single pump testing will be performed during each refueling outage using single pump reference Values.
Note 11 The Reactor Building Cooling Water Pumps (RR-PlA/B) supply river water to the Reactor Building Emergency Cooling Coils. Thase pumps will be tested during normal plant operation using a fixed resistance flow path that bypasses the cooling coils. This test will not measure flow rate. The testing during normal plant
- l. operation will not pump river water through the cooling coils because after the test, the cooling coils must l
be drained and then flushed with Nuclear Service Closed Cooling Water. The drain and flush water is drained to the Reactor Building Sump and this produces large quantitles of water that must be processed through the Liquid Haste Disposal System. However, flow rate will be measured during refueling outages, when river water j
is pumped through the cooling coils in accordance with Technical Specification requirements.
bote 12 A. CA-PlA/B For CA-PIA /B, GPUN requests relief from quarterly testing and the measurenent of Q, Pj, AP, and the five minute run time. The following testing will be conducted:
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l 1.) Testing CA-PIA /B will be conducted each refueling interval. CA-PIA /B does not have a recirculation l flow path. Without recirculation capability, the only method of testing these pumps is to inject into the Reactor Coolant Makeup System. The resulting reactivity changes would affect plant I operations adversely and would result in significant volumes of radicactive waste. During normal operation, testing one pump would generate 1,300 gallons of radwaste at the beginning of core life, 3,000 gallons at middle of core life and 32,000 gallons at end of core life. This much radwaste is generated becase injecting concentrated boric acid requires dilution of the RCS. For these reasons it is impractical to test the subject pumps during operation. The appropriate test interval is each refueling due to the large quantities of liquid radwate generated.
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TABLE A-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS) '
EXCEPTIONS TO ASME XI REQUIREMENTS Page 8 of 9 JUSTIFICATION NOTES (Cont'd) 2.) Flow rate (Q) will be calculated using Makeup Tank level change over time, since installed flow measuring instruments do not exist.
3.) Inlet pressure is not available. There are no existing pressure gage taps. Pt will be calculated using suction tank level.
4.) for CA-PIA /B pump differential pressure (aP) will not be calculated since CA-PIA /B are positive displacement pumps. Relief is requested from the ASME Section XI, INP-3110 requirement to calculate AP for CA-PIA /B. The calculation of AP for CA-PIA /B would not be meaningful since the flow rate is fixed solely by the displacement of the cylinder and the speed of the pump, both of which are held constant, while AP is only a function of system resistance (backpressure).
Therefore, such a calculation would be an unnecessary exercise for the operator.
S.) ASME Section XI IHP-3500 states that pumps under test should be run for at least five minutes under conditions as stable as the system permits prior to taking data. To minimize radioactive waste, the subject pumps will be run until the system has stabilized and then data will be recorded. GPUN believes this meets the intent of INP-3500.
I In conclusion, the CA-PIA /B test each refueling verifles the required flowrate_for CA-PIA /B while pumping to the Makeup Tank. This demonstrates that CA-PIA /B can perform its safety function by providing the required boric acid capacity at normal Makeup Tank backpressures. For this test, the Makeup Tank will be pressurized to its normal operating range. Pump vibration will be measured while pumping to the Makeup Tank.
B. WDL-P13A/B ASME Section XI, IHP-1100 states that emergency powered pumps should be included in the IST Program.
HDL-P13A/B are not emergency powered, but are included in the IST Program as requested by NRC. The addition of HDL-P13A/B in the program provides further assurance of the capability to supply concentrated boric acid to the Reactor Coolant Makeup System.
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- -. .-- .- .. . . _ . . = - .
TABLE A-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (PUMPS)
EXCEPTIONS TO ASME XI REQUIRFMENTS Page 9 of 9 JUSTIFICATION NOTES (Cont'd) for WDL-P13A/B, GPUN requests relief from the measurement of Q, Pj, AP, and the five minute run time. Testing will be conducted each refueling interval for the same radwaste concerns expressed above for CA-P-1A/B.
1.) Flow rate (Q) will be calculated using Makeup Tank level change over time, since installed flow measuring instruments do not exist.
2.) Inlet pressure is not available (There are no existing pressure-gage taps). Inlet pressure will be
' calculated using suction tank level.
3.) HDL-P13A/B's discharge valve is a diaphragm operated valve that is either open or closed. There is no handwheel on the valve. Instead of throttling to a AP reference value, WDL-P13A/B will be tested unthrottled while pumping to the pressurized Makeup Tank. Since WDL-Pl3A/B is tested while pumping to the pressurized Makeup Tank, pump AP is variable (it increases'over pumping time).
This makes it impractical to establish a AP reference value. HDL-P13A/B's safety function is to supply concentrated boric acid to the Makeup Tank. This testing will verify the accident design flow rate. 't 4.) ASME Section XI IWP-3500 states that pumps under test should be run for at least five minutes under conditions as stable as the system permits prior to taking data. To minimize radioactive waste, the refueling test will be run until the system has stabilized and then data will be. recorded.
GPUN believes this meets the intent of IWP-3500.
In addition, WDL-P13A/B will be tested on recirculation only when it is selected for the Technical Specification source of concentrated boric acid:
a.) Testing will be quarterly.
b.) Pt will be calculated using suction tank level.
c.) AP will be calculated.
Note 13 l
l The pump and motor form an integral unit. The pump bearings are located in the motor. There is no l- lubrication level on the pump that can be checked. Also yearly bearing temperatures will not be measured since the bearings are deep inside the motor end caps.
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TABLE B li THREE MILE ISLAND UNIT NO. I e PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
Page 1 of 3 I. Scope and Objectives This table describes the Inservice Inspection Program for all Class 1, 2, and 3 valves. The objective of ,
this program is to provide assurance of the operability of these valves during their service life.
l II. Applicable ASME Code Edition and Addenda
! In accordance with 10 CFR 50.55a(g)(4)(11), the appilcable Code Edition and Addenda are the 1980 Edition with i Addenda through Hinter, 1980.
III. Period of Applicability j
In accordance with 10 CFR 50.55a(g)(5)(iv), this program is applicable from September, 1984 to September, 1994.
j IV. In_spection Program i'
The inspection program, which is detailed in Table B-1 will be carried out in accordance with ASME Section XI, 1980 Edition with Addenda through Winter, 1980. Specific exceptions to the ASME Code Section XI requirements for each component are identified in Table B-2 along with the basis for each exception requested.
j In addition to tests indicated in Table B-1, all valves listed in Table B-1 with remote position indicators i shall be observed at least once every two years to verify that valve operation is accurately indicated per
! ASME Section XI, IHV-3300.
V. Limiting Stroke Time for Power Operated Valves I Table B-3 provides a list of limiting values of full-stroke time for all the power operated valves in the IST
' Program. Please be advised that this limiting stroke time is subject to change. When limiting stroke times l
are changed, appropriate analysis per ASME Section XI, IHV-3413 and 10 CFR 50.59 will be performed to demonstrate applicable Code and safety standard compliance.
1 j
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TABLE B THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
Page 2 of 3 SYMBOLS Symbols which appear in the respective columns of Table B-1 are as follows:
CLASS The ISI system classification of the portion of the system in which the valve is located.
CAIEGORY As defined in ASME Code,Section XI, 1980 Edition through 1980 Winter Addenda, Paragraph I4V-2200.
TYPE OF TEST T- Full stroke valve exercise and time measurement for power operated valves.
F- Full stroke functional check of valve operation.
P- Partial valve stroke exercise. (Partial stroke times will not be measured).
L- Valve seat leak test.
1 SP - Set point test.
FS - Fall Safe test.
a- Leak test. These check valves are Wash-1400 Event V configuration valves. The valves separate high and low pressure systems and they perform a pressure barrier function insuring that the low pressure system is not subjected to pressures which exceed their design limits.
D- Disassembly and visual examination.
FT - Functional test of valve operation TEST FREQUENCY Q- Quarterly test frequency.
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TABLE B THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
Page 3 of 3 SYMBOLS (Cont.)
C- Cold shutdown test frequency (when shutdown exceeds 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and more than 92 o,ys have elapsed since test was performed during last previous shutdown period). This testing will continue until complete or the plant is ready to return to power. Completion of anj valve testing will not be a prerequisite to return to power. Any testing not completed at one cold shutdown will be performed at subsequent cold shutdowns.
(This is per a NRC staff position presented during a meeting on October 18, 1978).
C* - Cold shutdown test frequency. C* is only applicable to DH-V16 A/B where either A or B valve is tested on a cold shutdown frequency by the normal operation of providing Decay Heat Removal flow rate of >3000 gpm. In addition, both A and B valves will be tested each refueling interval.
R- Refueling outage test frequency.
RC- Following a Refueling or a Cold Shutdown When Cold Shutdown exceeds 30 days.
SY - Tests of valves are distributed over a 5 year period per ASME Sec'*on XI, Table IWV-3510-1.
9M - Prior to achieving hot shutdown following a cold shutdown of greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> duration unless testing has been performed within the previous 9 months, and prior to achieving hot shutdown after returning the valve to service following maintenance repair or replacement work.
10Y- Each 10 years (at or near the end of the 10 year ISI interval).
l NOTE: Roman numerals in parenthesis found in Table B-1 refer to the Roman numerals in Table B-2 which correspond l
to specific requests for relief from ASME Section XI test requirements.
l i
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l l TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 1 of 37 l
SYSTEM / TYPE TEST l CATEGORY OF TEST l (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS F R_E_QUENCY l
AIR HANDLING AH-VIA/D B' FLY 48" PNEU. 2 A L/T(IX)/FS R/Q/Q SYSTEM (ID-ISI-FD-023) AH-VlB/C B' FLY 48" MOTOR 2 A L/T R/Q l
NOTE: All valves listed in Table B-1 with remote indicators shall be observed at least once every two years to verify that valve operation is accurately indicated per ASME Section XI IHV-3300.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 2 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY __
CORE FLOOD CF-V2A/B GLOBE 1" MOTOR 2 A L/T R/Q SYSTEM (ID-ISI-FD-004) CF-V4A/B CHECK 14" ----- 1 A/C A/P(VI)/D(2) 9M(V)/C(3)fjoy CF-VSA/B CHECK 14" ----- 1 A/C a/P(XII)/D(2) 9M(V)/C(3)/ joy CF-V12A/B CHECK 1" ----- 2 A/C L/F R/C(I)
CF-Vl9A/B GATE 1" DIAPHRAGM 2 A L/T/FS R/Q/Q CF-V20A/B GATE 1" DIAPHRAGM 2 A L/T/FS R/Q/Q Footnote:
(1) In accordance with ASME Section XI IHV-3522, CF-V12A/B will be tested at each cold shutdown since testing CF-V12A/B involves changing the position of other valves (CF-V28A/B) that are listed in Operating Procedure Number 1101-3, " Containment Integrity and Access Limits". In accordance with Operating Procedure 1101-3, the position of CF-V28A/B may not be changed during normal reactor operation.
(2) CF-V"./B and CF-VSA/B are the same size, manufacturer and catalog number. CF-V4A, or CF-V4B, or CF-t5A, or CF-V5B (1 of the four) will be disassembled each 10 years for an inspection. If degradation which would make the valve's full stoke capability questionable is found, then the remaining three valves will be disassembled and inspected during that outage.
(3) Check valve CF-V4A/B and SA/B isolate the RCS from the low pressure Decay Heat Removal System and during normal plant operations, CF-V4A/B and SA/B will not be tested on a quarterly frequency because there is no method of opening these valves. The check valves are on the discharge side of
'DH-PIA /B. DH-PlA/B only produce ~200 psig. Therefore, it is not possible to overcome normal RCS pressure (2155 psig) with DH-PIA /B.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 3 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY CHEMICAL CA-VI "Y" GLOBE 1" MOTOR 1 A L/T R/Q SAMPLING SYSTEM CA-V2 "Y" GLOBE 1" PNEU. 1 A L/T(IX)/FS R/Q/Q (ID-ISI-FD-020)
& CA-V3 "Y" GLOBE 1" MOTOR 1 A L/T R/Q (ID-ISI-FD-021)
CA-V4A/B "Y" GLOBE 1" MOTOR 2 A L/T R/Q CA-VSA/B "Y" GLOBE 1" PNEU. 2 A L/T(IX)/FS R/Q/Q CA-VI3 GLOBE 1/2" MOTOR 1 A L/T R/Q CA-V177 CHECK l ----- 3 C F R(IV)
CA-V189 GATE 2" PNEU. 2 A L/T/FS R/Q/Q
]
CA-V192 CHECK 2" -----
2 A/C L/-(I)(XI) R/-
Footnote:
(I) CA-Vl92 supplies demin. water purge to the RC pump No. 3 Seal. CA-Vl92 is not needed to maintain No. 3 seal integrity. However, during normal plant operation, purge supply cannot be isolated without some risk to the reliability of the No. 3 seal; therefore, CA-V192 will not be tested for closed function on a quarterly interval. CA-V192's only safety function is to close to provide containment isolation. The containment isolation function of CA-Vl92 will be verified each refueling by leak testing in accordance with T.S. 4.4.1.2.1.b per Surveillance Procedure 1303-11.18.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 4 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY CHILLED WATER CH-V22A/B CHECK 4" ------- 3 C F Q SYSTEM (10-ISI-FD-01I) 1577X/pe
TABLE B-1 THREE MILE ISLAND UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 5 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY CONDENSATE CO-V16A/B CHECK 10" -----
3 C P/F Q/RC(II)
SYSTEM (1D-ISI-FD-009) 1577X/pe
TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 6 of 37
~
SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY _
CONTAINMENT CM-V1 BALL 1" PNEU. 2 A L/T(IX)/FS R/Q/Q MONITORING (ID-ISI-FD-023) CM-V2 BALL 1" PhEU. 2 A L/T(IX)/FS R/Q/Q CM-V3 BALL 1" PNEU. 2 A L/T(IX)/FS R/Q/Q CM-V4 BALL 1" PNEU. 2 A L/T(IX)/FS R/Q/Q f
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 7 of 37
- SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY
]
DECAY HEAT DH-VI GATE 12" HOTOR 1 B T C(2)
REMOVAL SYSTEM DH-V2 GATE 12" MOTOR 1 B T C(2)
(lD-ISI-FD-005)
DH-V3 GATE 12" MOTOR 2 B T Q ;
i DH-V4A/B GATE 10" MOTOR 2 B T Q I DH-VSA/B GATE 14" MOTOR 2 B T Q j
DH-V6A/B GATE 14" MOTOR 2 B T R(I)
I DH-V7A/B GATE 4" MOTOR 2 B T Q DH-V14A/B CHECK 14" ----- 2 C P/P(XII) Q/R(III) l DH-V16A/B CHECK 10" ----- 2 C P/F Q/C*(XIII) i DH-V22A/B CHECK 10" -----
1 A/C A/F 9M(V)/C(3) l DH-V38A/B GATE 5" MANUAL 2 B F Q DH-V64 GLOBE 2" MANUAL 2 A L/-(I) R/-
DH-V69 STP-CK 1-1/2" MANUAL 2 A/C L/-(I) R/-
Note: Manual valves DH-V12A/B were included in the first revision of this submittal. They have been deleted because they are now passive locked valves. During criticality DH-V12A is locked closed and DH-V128 is locked open for boron precipitation concerns. No meaningful information would be obtained by exercising these manual valves that are already in their required safety related position (during criticality).
i i
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAN - (VALVES)
PAGE 8 of 37 SYSTEM / TYPE TEST l (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY footnotes:
(I) This CIV is passive (a closed valve whose function is to remain closed). Therefore, this valve is exempted from the quarterly functional stroke requirement of IHV-3412 per NRC staff guidelines since no meaningful information would be gained.
(2) DH-V1 and DH-V2 are the two high pressure valves in the Decay Heat drop line (suction line to LPI pumps).
During normal plant operation, these valves cannot be cycled because this would reduce redundancy by providing only one high pressure valve between the RCS and the low pressure Decay Heat Removal System. In addition, DH-V1 and 2 are interlocked with RCS pressure such that they cannot be opened unless RCS pressure is <400 psig. This Engineered Safeguard Feature interlock is verified during ESAS testing in accordance with T.S. Table 3.5-1, item C.2.c. Therefore, per ASME Section XI IWV 3412, these valves will be tested on a cold shutdown frequency.
(3) During normal plant operations check valve DH-V22A/B will not be tested on a quarterly frequency because there is no method of opening DH-V22A/B. DH-V22A/B are on the discharge side of DH-PlA/B. DH-PIA /B only produce ~200 psig; therefore, it is not possible to overcome normal RCS pressure (2155 psig) with DH-P1A/B.
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TABLE B-1 THREE MILE ISLAND UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 9 of 37 SYSTEH/ TVPE' TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY __
DECAY HEAT DR-VIA/B B' FLY 20" MOTOR 3 B T Q RIVER HATER SYSTEM DR-V7A/B CHECK 2" ----- 3 C F Q (ID-ISI-FD-002)
& DR-V21A/B CHECK 1" ----- 3 C F Q (ID-ISI-FD-014)
DR-V22A/B CHECK 1" ----- 3 C F Q DR-V26A/B CHECK 2" ----- 3 C F Q f F DR-V37A/B CHECK 3/8" ----- 3 C Q l
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l TABLE B-1 THREE HILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 10 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY EMERG. FEED EF-V3(I) CHECK 6" -----
3 C P/D 0/10Y HATER SYSTEM (10-ISI-FD-009) EF-V4 GATE 6" MOTOR 3 B i R(I)
(ID-ISI-FD-010) EF-V5 GATE 6" MOTOR 3 B T R(I)
EF-V11A/B CHECK 4" ----- 3 C F RC(2)(II)
EF-V12A/B CHECK 6" ----- 2 C F RC(II)
EF-Vl3 CHECK 6" ----- 3 C P/F Q/RC(II)
EF-Vl9A/B CHECK 1-1/2"----- 3 C F Q l
EF-V21 CHECK 2" =
3 C F Q EF-V30A/B CONTROL 3" PNEU. 3 B T/FS Q/Q 1
Footnote:
(I) GPUN will remove the internals from this valve at the Eddy Current Outage which is scheduled for March 1986.
When the internals are removed, the valve will be deleted from the IST Program.
(2) EF-VilA/B are the discharge check valves on EF-P2A/B. EF-P2A/B is tested on recirculation with the OTSGs isolated from EF-P2A/B by EF-V10A/B. The recirculation line is upstream of EF-VilA/B; therefore, tnere is no l flow through EF-VilA/B. It is not possible to initiate flow through EF-VilA/B on a quarterly frequency due j
to the limited number of thermal cycles allowed (40) for the Auxillary feedwater Nozzles.
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DRAFT TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC TNSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 11 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY EMERGENCY EG-V31A/B(3) CONTROL 5" -----
3 C F/D Q/10Y DIESEL GENERATOR EG-V32A/A, CHECK 4" ----- 3 C F/D(1) Q/10Y COOLANT A/B B/A, SYSTEM B/Bl2) l (ID-ISI-FD-013)
EG-V34A/B CHECK 5" -----
3 C F/D(I) Q/10Y EG-V47A/B(3) CONTROL 4" -----
3 C F/D Q/10Y EG-V48A/B CHECK 4" -----
3 C F/DCI) Q/10Y l Footnote:
(1) These valves will be disassembled each 10 years per I.E. Bulletin 83-03.
(2) EG-V32A/A, A/B, B/A and B/B are located downstream of the Diesel Generator Jacket Coolant Radiator. These valves must open to allow coolant to be pumped out of the two 507. capacity each radiators. Their function is vertfled open during the monthly performance of SP 1303-4.16 which verifles acceptable engine coolant temperatures. If one of the two check valves did not open, acceptable engine coolant temperatures would not be obtained. SP 1303-4.16 verifies acceptable engine coolant temperatures and that the diesels are capable of providing their design rating of 3 1 0.1 MW for one hour.
(3) EG-V31A/B and EG-V47A/B are self-contained thermostatic valves that use an expanding wax type of temperature sensing element. There are no external actuators or operators. These valves are similar to the thermostat in an automobile. EG-V31A/B are 4" valves and have four internal elemcnts that start to open at 100*F and are full open at ll5*F. EG-V47A/B are 5" valves and have six internal elements that start to open at 155'F and are full open at 170*F. EG-V31A/B and EG-V47A/B are categorized C per ASME Section XI, IHV-2200 since the valves "are self-actuating in response to some system characteristic, such as pressure ...". For EF-V31A/B and V47A/B, the system characteristic is temperature. EG-V31A/B open to allow cooling water from the diesel generator intercooler to be diverted to the engine radiator and EG-V47A/B open to allow cooling water from the diesel generator's jacket to be diverted to the engine radiator. The operability of these valves is verified in the monthly performance of SP 1303-4.16 since acceptable intercooler air receiver temperature and acceptable jacket water temperature is verified. SP 1303-4.16 verifies design load of 3.0 1 0.1 MW for a minimum of oi.e hour. In addition, EG-V31A/B and 47A/B will be disassembled / inspected on a 10 year interval. During the 10 year disassembly / inspection the temperature elements will be replaced or the elements will be verified to open and close at the correct temperatures.
l TABLE B-1 THREE MXLE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 12 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE __0PERATOR CLASS CATEGORY OF TEST FREQUENCY FLUID BLOCK (10-ISI-FD-015)
Note: Technical Specification Amendment No. 93, issued May 18, 1984, deletes the fluid Block Valves from Appendix J leak rate testing requirements. GPUN has disabled the Fluid Block System to the gate type CIVs by positive means. Therefore, the Fluid Block Check Valves have been deleted from the IST Program.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 13 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY FEEDWATER FH-V12A/B CHECK 20" ----- 2 C SEE TABLE SEE TABLE SYSTEM B-2, (X) B-2, (X)
(ID-ISI-FD-009) i i
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 14 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY HYDROGEN HM-VIA/B GLOBE 1/2" SOLEN 0ID 2 A L/T(IX)/FS R/Q/Q MONITORING SYSTEM HM-V2A/B GLOBE 1/2" SOLEN 0ID 2 A L/T(IX)/FS R/Q/Q l
(ID-ISI-FD-023)
HH-V3A/B GLOBE 1/2" SOLENOID 2 A L/T(IX)/FS R/Q/Q HM-V4A/B GLOBE 1/2" SOLENOID 2 A L/T(IX)/FS R/Q/Q l
~
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l TABLE B-1 THREE MILE ISLAND UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 15 of 37 SYSTEM / TYPE TEST l
( VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY Of TEST FREQUENCY
_ISI DRAWING NO.)
I HYDROGEN HP-V1 GATE 6" MANUAL 2 A L/-(l) R/-
PURGE (ID-ISI-FD-023) HP-V6 GATE 6" MANUAL 2 A L/-(I) R/-
Footnote:.
l l (I) Amendment No. 108 to THI-l's Technical Specifications has approved the use of the Hydrogen
! Recombiner System; therefore, these valves no longer by design will be used to purge hydrogen from l the Reactor Building. The quarterly functional test has been discontinued for these passive valves. The only safety function of HP-VI and HP-V6 is to remain closed and act as a Containment Isolation Valve (CIV).
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- . - - _. - - - _ ~ . - - - _ _ _ _ _ _ _ _ _ - _ _ _ _ ---_- - -_. . -__ ___ . . . - - __ -
l -
TABLE B-1 l THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 16 of 37 SYSTEM / TYPE TEST l
(ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY HYDROGEN HR-V2A/B GLOBE 2" MANUAL 2 A L/F R/Q RECOMBINER SYSTEM HR-V4A/B GLOBE 2" MANUAL 2 A L/F R/Q (ID-ISI-FD-015)
HR-V22A/B GATE 2" SOLEN 0ID 2 A L/T(IX)/FS R/Q/Q HR-V23A/B GATE 2" SOLEN 0ID 2 A L/T(IX)/FS R/Q/Q ,
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSEPVICE INSPECTION PROGRAM - (VALVES)
PAGE 17 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY INSTRUMENT IA-V6 GLOBE 2" MANUAL 2 A L/-(I) R/-
AIR SYSTEM (lD-ISI-FD-023) IA-V20 GLOBE 2" MANUAL 2 A L/-(I) R/-
STATION SERV. SA-V2 GLOBE 2" MANUAL 2 A L/-(I) R/-
AIR SYSTEM (lD-ISI-FD-023) SA-V3 GLOBE 2" MANUAL 2 A L/-(I) R/-
l Footnote:
(I) This CIV is passive (a closed valve whose function is to remain closed). Therefore, this valve is esempted from the quarterly functional stroke requirement of IHV-3412 per NRC staff guidelines since no meaningful information would be gained.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 18 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY INTERMEDIATE IC-VIA/B(2) GATE 4" MOTOR 3 B T C(I)
COOLING SYSTEM IC-V2 GATE 6" MOTOR 3 A L/P/T R/Q/C(3)
(ID-ISI-FD-022)
IC-V3 GATE 6" PNEU. 2 A L/P/T/FS R/Q/C(3)/C IC-V4 GATE 6" PNEU. 2 A L/P/T/FS R/Q/C(3)/C IC-V6 GATE 3" PNEU. 2 A L/P/T/FS R/Q/C(3)/C IC-VIS CHECK 3" ----- 2 A/C L/F R/R(III)
IC-V18 CHECK 6" ----- 2 A/C L/F R/R(TII) l Footnotes;.
(I) IC-VIA/B supplies cooling water to the Primary System Letdown Coolers. In accordance with B&W guidance and the failure history of the Letdown Coolers it is not advisable to thermal cycle the Letdown Coolers by isolating cooling water to an operating Letdown Cooler. Thermal cycles increase thermal stress which increases the potential for tube leakage. Therefore, per ASME Section IWV-3412, IC-VIA/B will be tested at cold shutdown frequency.
(2) These non-safety related valves do not provide an essential safety function and are not safety related.
However, IC-VIA or B may be used during certain abnormal conditions to place a second letdown cooler in service to maximize letdown flowrate.
(3) These valves are in the supply or retcrn lines to the Primary Letdown Coolers, Control Rod Drive Cooling Coils, Reactor Coolant Pump Heat Exchangers and/or R."C. Drain Tank Heat Exchanger. It is not possible to stop flow in these lines to test these valves without upsetting the reactor plant. Therefore, in accordance with ASME Section XI, IWV-3412, these valves will be tested on a cold shutdown frequency.
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TABLE B-1 j THREE MILE ISLAND UNIT NO. 1 l PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 19 of 37
, SYSTEM / TYPE TEST (ISI DRAWING h0.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY LEAK RATE LR-Vi(I) GATE 6" MANUAL 2 A L/- R/-
TEST SYSTEM (lD-ISI-FD-015) LR-V4 GLOBE 3/4" HANUAL 2 A L/-(2) R/-
LR-V5 GLOBE 2" MANUAL 2 A L/-(2) R/-
l LR-V6 GLOBE 2" MANUAL 2 A L/_(2) R/-
i
} LR-V10 GLOBE 1" MANUAL 2 A L/_(2) R/-
4 LR-V49(I) GATE 6" MANUAL 2 A L/- R/-
l I
Footnotes:
(I) Technical Specification Amendment No. 108 has approved the use of the Hydrogen Recombiner System; therefore, these valves no longer by design will be used to supply air for hydrogen purging after an accident.
Therefore, the quarterly functional test has been discontinued for these passive valves. The only safety function of LR-VI and LR-V49 is to remain closed and act as CIVs.
1 (2) This CIV is passive (a closed valve whose function is to remain closed). Therefore, this valve is exempted j
from the quarterly functional stroke requirement of IWV-3412 per NRC staff guidelines since no meaningful Information would be gained.
l
)
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_ _ _ _ . _ _ _ _ . ~ . _ _ _ _ _ - - _ _ _ _ _ _ . _ _
TABLE B-1 !
t THREE MILE ISLAND UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 20 of 37 i
SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY MAIN STEAM MS-VIA-D STOP-CK 24" MOTOR 2 B/C P(4)/T Q/C
-SYSTEM (lD-ISI-FD-001) MS-V2A/B GATE 12" MOTOR 2 B T C(I)
- i MS-V4A/B CONTROL 6" PNEU. 3 B T/FS Q/Q MS-V6 CONTROL 4" DIAPHRAGM 3 B P(XIV)/FS . QtQ MS-V8A/B GATE 12" MOTOR 3 8 T C(3) i MS-V9A/B CHECK 6" ----- 3 C P(VI)/D. Q/10Y i
MS-V10A/B GATE 6" MOTOR 3 B T C(2)
MS-V13A/B GLOBE 2" DIAPHRAGM 3 8 T/FS Q/Q MS-V17A-D RELIEF 6"x10"----- 2 C SP SY MS-VI8A-D RELIEF 6"x10"- --
2 C SP SY l l
MS-Vl9A-D RELIEF 6"x10"----- 2 C SP SY i
MS-V20A-D RELIEF 6"x10" -
MS-V21A/B RELIEF 3"x6" ----- s i Footnotes:
(I) MS-V2A/B isolate the six turbine bypass valves. MS-V2A isolates three turbine bypass valves and likewise MS-V2B isolates the remaining three turbine bypass valves. Technical Specification 3.4.1.c requires'four of the six turbine bypass valves to be operable. If MS-V2A/B stuck closed during a quarterly test, this would !
limit the ability of the plant to cooldown. Normal cooldown decay heat removal is by the steam generator '
through MS-V2A/B to the turbine bypass valves and then to the condenser. Therefore, per ASME Section XI l IHV-3412, these valves will be tested on a cold shutdown frequency. t k
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 21 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASC. CATEGORY OF TEST FREQUENCY (2) MS-V13A/B is a 2" valve in parallel with MS-V10A/B, which is a 6" valve. Upon loss of both Main Feedwater Pumps or upon loss of all four RC pumps, MS-V13A/B opens to supply steam from the OTSGs to the Turbine Driven Emergency feedwater Pump (EF-P1). Then at approximately 300 psig steam pressure, MS-V10A/B is jogged open to maintain steam pressure to EF-Pl. To preclude the possibility of challenging the safety relief valves for EF-PI's turbine (MS-V22A/B), MS-V10A/B will only be tested at cold shutdowns, in accordance with ASME Section XI INV-3412.
(3) Technical Specification 3.4.1.c requires four of the six turbine bypass valves operable when RCS temperature is >250*F. MS-V8A or B isolates three of the turbine bypass valves. Cycling MS-V8A or B during normal plant operation would violate T.S. 3.4.1.c; therefore, MS-V8A/B will be stroke timed on a cold shutdown frequency. ;
(4) Full-stroke testing during power operation is not practical because of the potential for possible turbine pressure instabilities downstream of the valves and possible unnecessary challenges to safety valves upstream of the MS-Vis. Also, Abnormal Procedure 1203-42 requires the reactor to be tripped if MS-VIA/B/C or D cumpletely close during power operation in order to prevent damage to the OTSG that was not isolated.
3 l
I l
l l
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TABLE B-1
- THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 22 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY MAKEUP MU-VIA/B(4) GATE 2-1/2" MOTOR 1 B T CCI)
SYSTEM (ID-ISI-FD-016) MU-V2A/B GLOBE 2-1/2" MOTOR 1 A L/P(5)/T R/Q/C (ID-ISI-FD-017) MU-V3 GATE 2-1/2" PNEU. 2 A L/P(5)/T(IX)/FS R/Q/C/C MU-V12 GATE 4" MOTOR 2 B T C(2)
MU-V14A/B STOP-CK 6" MOTOR 2 B/C T/F Q/R(III)
MU-V16A-D GLOBE 2-1/2" MOTOR 2 B T Q MU-V18 GATE 2-1/2" PNEU. 2 A L/T(IX)/FS R/C(3)/C MU-V20 GATE 4" PNEU. 2 A L/T/FS R/C(2)/C MU-V25 GLOBE 4" HOTOR 2 A L/P(6)/T R/Q/C MU-V26 GATE 4" PNEU. 2 A L/P(6)/T/FS R/Q/C/C MU-V36 GATE 2" MOTOR 2 B T Q HU-V37 GATE 2" MOTOR 3 B T Q MU-V47 STOP-CK 4" ----- 2 C F Q MU-VS1 DIAPH. 1" PNEU. 3 8 T(IX)/FS Q/Q l
MU-V73A-C CHECK 3" ----- 2 C P(7)/F Q/R(III)
MU-V86A/B CHECK 2-1/2" ----- 1 C F R(8)(III) l MU-V94 CHECK 2-1/2" ----- 1 C P/F Q/R(III)
MU-V95 CHECK 2-1/2" ----- 1 C F R(8)(III) 1577X/pe
TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 23 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY MU-V107A-D CHECK 2-1/2" ----- 1 C F R(8)(III)
MU-Vil6 CHECK 1-1/2" ----- 1 A/C L/F R/R(XI)
MU-V217(9) GLOBE 2-1/2" MOTOR 2 B P/T Q/C-MU-V219 CHECK 2-1/2" ----- 1 C F Q MU-V220 CHECK 2-1/2" ----- 1 C F R(8)(III)
Footnotes:
'1
- dIl MU-VIA/B is the upstream valve at the Primary Letdown Cooler. In accordance with B&W guidance and the failure history of the Letdown Coolers it is not advisable to thermal cycle the Letdown Coolers by closing MU-VIA/B.
~. ? Thermal cycles increase thermal stress which increases the potential for tub leakage. Therefore, in' _
accordance with ASME.Section XI INV-3412, these valves will be tested on.a~ cold. shutdown frequency.
~
(2)~ MU-V12 isolates the Makeup Tank from the suction of the Makeup Pumps. Part-stroking this valve during normal
- 2 plant operat19n would jeopardlie the continued operation of the running Makeup Pump if this valve completely closed dueLto valve operator malfunction. Likewise, part-stroking MU-V20 would jeopardize the continued
-operation of the Reactor Coolant Pumps, since this valve supplies seal injection water to.the Reactor Coolant-Pumps. Therefore, in accordance with ASME Section XI IWV-3412, these. valves will-be tested on a cold shutdown freque'ncyE~
(3) MU-V18 is in the normal makeup supply leg to the Reactor Coolant System. During normal plant operation, MU-V18 cannot be closed due to the limited number of allowable thermal cycles (40) on the high pressure injection nozzles. Therefore, in accordance with ASME Section XI, IWV-3412, MU-V18 will be. tested on a cold 1 shutdown frequency.
(4) MU-VIA/B are in the Primary Letdown piping to the Letdown Coolers. Normally one cooler is inservice. These non-safety related valves do not provide an essential safety function. MU-VIA/B may be used during certain abnormal conditions to place a second Letdown Cooler in service to maximize letdown flow.
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l l
TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 24 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY (5) MU-V2A/B and MU-V3 are part-stroked each quarter per ASME Section XI, IWV-3412(a) requirements. A full-stroke test is not required because it is impractical to isolate Letdown during power operation as this may preclude timely restoration of letdown flow. If letdown flow is totally isolated, the Reactor Coolant System loses its normal means of purification and compensation for volume addition due to design RC Pump Seal Injection in-leakage and may lead to reactor shutdown. Also thermal cycle considerations on the Letdown Coolers do not allow full closure of MU-V2A/B or MU-V3 during normal plant operation.
(6) MU-V25 and MU-V26 are in the RC Pump Seal Return line and are part-stroked each quarter. Isolation of the RC Pump Seal Return Line at power risks permanent damage to the RC Pump Seals and Reactor Coolant System leakage, and may result in reactor shutdown.
(7) MU-V73A/B/C are the discharge check valves on MU-PlA/B/C. During normal operation, MU-PIA or B or C supplies i normal makeup to the RCS, RC Pump seal injection, and recirculation flow. The total of these flow rates is much less than accident design flow rate and this is considered a partial stroke test of MU-V73A/B/C. No other testing method is practical during normal plant operation, because of thermal shock to the injection nozzles.
(8) Consideration of thermal shock to the injection nozzles prohibits testing these valves each quarter since the piping configuration provides no other flow path except pumping through these check valves to the injection nozzles.
(9) MU-V217 is non-safety related and has no essential safety function. However, it provides high makeup flow by manual actuation from the Control Room in the event of a reactor trip or other abnormal transient, thereby avoiding unnecessary challenges to the HPI system.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 25 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY NITROGEN NI-V26 GLOBE 1" MANUAL 2 A L/-(I) R/-
SUPPLY (ID-ISI-FD-023) NI-V27 GLOBE 1" MANUAL 2 A L/-(I) R/-
Footnote:
(I) This CIV is passive (a closed valve whose function is to remain closed). Therefore, this valve is exempted from the quarterly functional stroke requirement of IWV-3412 per NRC staff guidelines since no meaningful information would be gained.
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TABLE B-1 THREE MILE ISLAND UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES) f' PAGE 26 of 37 i SYSTEM / TYPE TEST (ISI DT/sHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY NUCLEAR NR-VIA-C B' FLY 16" MOTOR 3 B T Q 1
SERVICE RIVER HATER NR-V4A/B B' FLY 30" HOTOR 3 B T Q SYSTEM i (ID-ISI FD-002) NR-V20A-C CHECK 16" ----- 3 C F Q
, (ID-ISI-FD-014) NR-V22A-C CHECK 2" -----
3 C F Q i
NR-V44A-C CHECK 2" ----- 3 C F Q 1
NR-V45A-C BALL 2" PNEU. 3 8 T(IX)/FS Q/Q NR-V47A-C CHECK 1' ----- 3 C F Q NR-V48A-C CHECK 1" -----
3 C F Q NR-V66A-C CHECK 3/8" ----- 3 C F Q 1
I I
i J
l I.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 27 of 37 SYSTEM / TIPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY NUCLEAR SERV. NS-V4 GATE 8" MOTOR 2 A L/P(2)/T R/Q/C CLOSED COOLING NS-V10A-C CHECK 12" -----
3 C F Q (ID-ISI-FD-010)
NS-V11 CHECK 8" ----- 2 A/C L/F R/R(XI)
NS-V15 GATE 8" MOTOR 2 A L/P(2)/T R/Q/C NS-V35 GATE 8" MOTOR 3 A L/P(2)/T R/Q/C NS-V52A/B/C GATE 1" PISTON 2 B T(IX)/FS C(l)/C NS-V53A/B/C GATE 1" PISION 2 B T(IX)/FS C(l)/C NS-V54A/B CONTROL 1-1/2" DIAPH 3 B FT(XVI)/FS 0/0 NS-V55A/B CONTROL 3" DIAPH 3 B FT(XVI)/FS Q/Q NS-V56A/B CONTROL 2" DIAPH 3 B FT(XVI)/FS Q/Q footnotes:
(I) During normal plant operation, all three Reactor Building Coolers are inservice with NS-V52A/B/C and NS-V53A/B/C open supplying cooling water to Reactor Building fan Motor Coolers. If for testing purposes these valves were closed and in the unlikely event that they were not able to be reopened, this would jeopardize the continued cooling of the Reactor Building atmosphere since the fan motor would trip on high temperature. Therefore, in accordance with ASME Section XI IWV-3412 and NRC letter to Met-Ed dated November 17, 1976 Enclosure 2, paragraph 1, these valves will be tested on a cold shutdown frequency.
(2) NS-V4, V15, and V35 supply or return cooling water for the RC Pump Motor Coolers. If, for testing purposes, these valves were closed and they were not able to be reopened, this would shortly l
require de-energizing all four Reactor Coolant Pump Motors. Therefore, in accordance with ASME
' Section XI, IWV-3412 and NRC letter to Met-Ed dated November 17, 1976, Enclosure 2, Paragraph 1, these valves will be full stroke tested on a cold shutdown frequency and part-stroked each quarter.
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TABLE B-1
) THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 28 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY PENETRATION PP-V100 DIAPH. 1" DIAPH. 2 B T/FS Q/Q PRESSURIZA-
- TION SYSTEM PP-V101 CHECK 1" ----- 2 C F Q (ID-ISI-FD-OlS)
PP-V102 CHECK 1" ----- 2 C F Q PP-V103 DIAPH. 2" DIAPH. 2 B T/FS Q/Q PP-V132 DIAPH. 2" DIAPH. 2 B T/FS Q/Q f PP-V133 CHECK 2" ----- 2 C F Q l
TP-V134 CHECK 2" ----- 2 C F Q PP-V135 DIAPH. 1" DIAPH. 2 B T/FS Q/Q j
i i
i I i i
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PACE 29 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY REACTOR BLDG. RR-VIA/B B' FLY 16" MOTOR 3 B T Q EMERGENCY COOLING RR-V3A/B/C GATE 12" HOTOR 2 B T Q SYSTEM (ID-ISI-FD-O02) RR-V4A-D GATE 12" MOTOR 2 B T Q (ID-ISI-FD-010) RR-VS B' FLY 10" MOTOR 3 B T Q (ID-ISI-FD-014) RR-V6 CONTROL 10" DIAPH 3 B F(XV)/FS Q/Q VALVE RR-V7A/B CHECK 16" -----
3 C F Q RR-V8A/B CHECK 20" ----- 3 C F R(III)
RR-V9A/B/C CHECK 12" ----- 3 C F R(III)
RR-V10A/B PLUG 2" DIAPH 3 B T/FS Q/Q RR-V12A/B CHECK 2" ----- 3 C F Q RR-V20A/B CHECK 1" ----- 3 C F Q RR-V21A/B CHECK 1" ----- 3 C F Q RR-V29A/B CHECK 2" ----- 3 C F Q RR-V39A/B CHECK 3/8" ----- 3 C F Q i
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 30 of 37 SYSTO;I TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY REACTOR BLDG. RB-V7 GATE 8" MOTOR 2 A L/P(I)/T R/Q/C NORMAL COOLING SYSTEM RB-V2A GATE 8" MOTOR 2 A L/P(I)/T R/Q/C (ID-ISI-FD-010)
(1) RB-V7 and 2A are part-stroked each quarter. They are not full stroke tested because this would isolate normal cooling water to the Reactor Building atmospheric cooling coils. If in the unilkely event RB-V7 or 2A are not reopened, this could quickly lead to violation of Reactor Building air temperature Limiting Condition for Operation (Tech. Spec. 3.17) requiring plant shutdown. This agrees with the NRC staff position (Letter, R. H. Reid to R. C. Arnold, Novemoer 17, 1976) which states " valves whose failure in a non-conservative position during the cycling test would cause a loss of system function should not be exercised."
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 31 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY ,
REACTOR BS-VIA/B "Y" GLOBE 8" HOTOR 2 B T Q BUILDING SPRAY SYSTEM BS-V2A/B GATE 4" MOTOR 2 B T Q (ID-ISI-FD-012)
BS-V3A/B GATE 10" HOTOR 2 B T Q BS-V23A/B CHECK 10" ----- 2 C F Q BS-V30A/B CHECK 8" ----- 2 C P(VIII)/D Q/10Y(I)
BS-VS2A/B CHECK 4" ----- 2 C D(VII) 10Y(2)
Footnotes:
(I) If disassembly / inspection reveal that the full stroke capability of the disa sembled valve may be in question, the other valve (BS-V30A or B) will be disassembled and inspected at the same outage.
(2) If disassembly / inspection reveal that the full stroke capability of the disassembled valve may be in question, the other valve (BS-V52A or B) will be disassembled and inspected at the same outage.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 32 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY l REACTOR RC-Vl(4) GLOBE 2-1/2" MOTOR 1 B P/T Q/C COOLANT SYSTEM RC-V2 GLOBE 2-1/2" HOTOR 1 B T Q (ID-ISI-FD-019)
RC-V3(4) GLOBE 2-1/2" HOTOR 1 B T C(I)
RC-V4 "Y" GLOBE 2-1/2" MOTOR 1 B T C(2)
RC-V23 CHECK 2-1/2" ----- 1 C F C(2)
RC-RVIA/B RELIEF 2-1/2" ----- 1 C SP SY l
RC-RV2 RELIEF 2-1/2" SOLENOID 1 C SP SY RC-V28 GLOBE 1" MOTOR I B T C(3)
! RC-V40A/B GLOBE 1/2" SOLEN 0ID 1 B T(IX) C(3) i RC-V41A/B GLOBE 1/2" SOLENOID 1 B T(IX) C(3) 1 i RC-V42 GLOBE 1/2" SOLENOID 1 B T(IX) C(3) l RC-V43 GLOBE 1/2" SOLEN 0ID 1 B T(IX) C(3)
RC-V44 GLOBE 1" SOLENOID 1 B T(IX) C(3)
Footnotes:
(I) RC-V3 is the block valve for the pressurizer spray line. Part-stroking RC-V3 during normal cperation would jeopardize the ability to spray the pressurizer and reduce pressure if RC-V3 stuck closed. Therefore, in accordance with ASME Section XI IWV-3412 RC-V3 will be tested on a cold shutdown frequency.
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__ . _ _ _ _ - - - _ _ _ _ _ ~ _ - - _ _ _ - _ _ - _ - _ - _ - - _ _ _ _ _ . __
i
' TABLE B-l l THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 33 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY (2) RC-V4 and RC-V23 are the two high pressure valves in series that supply Auxiliary Spray to the Pressurizer.
These valves are used only during cooldown of the pressurizer. RC-V4 and RC-V23 will not be part-stroked during normal plant operation because the margin of safety would be reduced by opening either of these two pressure barrier valves. See NRC letter to Met-Ea dated November 17, 1976, Enclosure 2, paragraph 3.
Therefore, per ASME Section XI INV-3412 and IWV-3522, these valves will be tested on a cold shutdown frequency.
(3) RC-V28 and RC-V44 are the two in-series Pressurizer Vent Valves. RC-V40A/B and RC-V41A/B are the two High Point Vent valves in series. RC-V42 and RC-V43 are the two Reactor Vessel Head Vent valves in series. All >
of the valves are closed during normal plant operation. These valves will not be part-stroked during normal plant operation because failure of one of the valves in a non-conservative position (open) during the cycling test would cause a loss of double barrier isolation for the RC System. Therefore, per ASME Section XI i
l INV-3412, all of these valves will be tested on a cold shutdown frequency.
l (4) RC-VI's function is control of RCS pressure. During a transient which increases RCS pressure, RC-Vi opens to allow for cooler water to spray into the pressurizer, thus condensing steam and reducing RCS pressure.
l Should the RC-VI valve fall open, cooler water would continue to flow into the pressurizer, reducing pressure to below the normal operating point. For this reason, the line also contains RC-V3, which can be used to control the flow of cooler water to the pressurizer should the RC-V1 valve fall open. These non-safety related valves have no essential safety function but are important to plant operation.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 34 of 37 SYSTEM / TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY SCREEN HOUSE SH-V4A/B CHECK 6" -----
3 C F Q VENT SYSTEM (10-ISI-FD-002) SH-V6A/B CHECK 2" ----- 3 C F Q
.SW-V17A/B BALL 2" PNEU. 3 B T(IX)/FS Q/Q !
SW-V19A/B CHECK 1" ----- 3 C F Q ;
SW-V20A/B CHECK 1" -----
3 C F Q ;
SW-V24A/B CONTROL 4" DIAPH. 3 B FT(XVI)/FS Q/Q SH-V28A/B CHECK 2" ----- 3 C F Q NOTE: GPUN has determined that the Screen Wash and Slutce Valves are not needed to achieve cold shutdown or mitigate the consequences of an accident since AP across the screen is alarmed and if necessary manual means can be employed to wash the screens. Therefore, these valves have been deleted from this submittal.
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TABLE B-1 THREE MILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 35 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY SPENT FUEL SF-V23 GATE 8" MANUAL 2 A L/-(I) R/-
COOLING SYSTEM (ID-ISI-FD-018) i 1
1 i
Footnote:
l l
(1) This CIV is passive (a closed valve whose function is to remain closed). Therefore, this valve is exempted '
l from the quarterly functional stroke requirement of IHV-3412 per NRC staff guidelines since no meaningful l
information would be gained.
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_ _ _ m_. . _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _. _ _ _ _ . _ . _ _ _ _ . . ._ _ ._
TABLE B-1 THREE HILE ISLAND UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 36 of 37 SYSTEi4/ TYPE TEST (ISI DRAWING NO.) VALVE NO. TYPE SIZE OPERATOR CLASS CATEGORY OF TEST FREQUENCY WASTE WDG-V3 GLOBE 2" MOTOR 2 A L/T R/Q DISPOSAL GAS (10-ISI-FD-023) WDG-V4 GLOBE 2" SOLEN 0ID 2 A L/T(IX)/FS R/Q/0 t
l l
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TABLE B-1 THREE MILE ISLAND UNIT NO. I i PERIODIC INSERVICE INSPECTION PROGRAM - (VALVES)
PAGE 37 of 37 SYSTEM / TYPE TEST (ISI DRAHING NO.) VALVE NO. TYPE SIZE OPERATDR CLASS CATEGORY OF TEST FREQUENCY WASTE WDL-V49 DIAPH. 1-1/2" DIAPH. 3 B T(IX)/FS Q/Q DISPOSAL LIQUID SYSTEM WDL-V50 DIAPH. 1-1/2" DIAPH. 3 B T(IX)/FS Q/Q (ID-ISI-FD-021)
& WDL-V61 DIAPH. 1" DIAPH. 3 8 T/FS Q/Q (10-ISI-FD-023) i WDL-V62 DIAPH. 1" DIAPH. 3 B T/FS Q/Q WDL-V89 DIAPH. 2" DIAPH. 3 B T/FS Q/Q WDL-V90 DIAPH. 2" DIAPH. 3 B T/FS Q/Q WDL-V91 DIAPH. 2" DIAPH. 3 B T/FS Q/Q r
HDL-V92 DIAPH. 2" DIAPH. 3 8 T/FS Q/Q ,
HDL-V303 GATE 3" MOTDR 2 A L/T R/Q WDL-V304 GATE 3" DIAPH. 2 A L/T/FS R/Q/Q l
WDL-V353 CHECK 1-1/2" 3 C F Q ,
WDL-V354 CHECK 1-1/2" ----- 3 C F Q WDL-V361 CHECK 1" ----- 3 C F R(IV) i WDL-V362 CHECK 2-1/2" ----- 3 C F R(IV)
WDL-V534 GATE 6" PISTON 2 A L/T/FS R/Q/Q l WDL-V535 GATE 6" PISTON 2 A L/T/FS R/Q/0 1577X/pe
_-- ._= - . . - - - . - _ _ _ _ . . _ _- - - - _ . - _ . _ , _ _ _- - . _ ~ . _ _ .- _ --
l t
l TABLE B-2 l THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES i REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS
' PAGE 1 cf 21 GENERIC REQUEST FOR RELIEF I. Corrective Action for Inoperative Valves A. Valve Identification All the Class 1, 2, and 3 valves identified in Table B-1, THI-1 Valves Requiring Periodic Inservice Inspection.
B. ASME Code Section XI Requirement From Which Relief is Requested Corrective action for inoperable valves require condition be corrected before unit startup from a cold shutdown condittoa in accordance with paragraphs IHV-3417(b).
C. Basis for Requesting Relief Constraints and limits on plant startup with an inoperable valve depend on many specific plant design features and conditions. The limiting conditions for startup and operation have been analyzed and ara described in the THI-l Technical Specifications. Inoperable valves will be evaluated considering the THI-1 Technical Specifications to determine when an inoperable valve will limit plant startup from a cold shutdown condition. ,
II. Leak Testing of Category A Valves 4 A. Valve Identification All the Category A valves identified in Table I as L in the type of test column. These valves are containment isolation valves.
i B. ASME Code Section XI Requirement from Which Relief is Requested i
Relief is requested from paragraph IHV-3420, " Valve Leak Rate Test" through INV-3425.
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TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 2 of 21 i i
C. Basis for Requesting Relief All Appendix J, Type C valves are included in the IST Program and they are categorized A or A/C. All the ASME Code Category A, Containment Isolation Valves (CIVs) will meet Appendix J to 10 CFR Part 50 leak testing requirements in lieu of ASME Code Section XI requirements. CIVs are listed in THI-l's Technical Specifications and existing ,
requirements and exemptions listed therein shall apply to the IST Valve Program.
Appendix J is equivalent to and meets the intent of the code requirements. Therefore, valve operability is assured. Furthermore, a procedure is in place that meets the '
requirements of INV-3426 and IWV-3427 concerning individual valve leakrate limits and trend analysis of leakrate, respectively.
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TABLE B-2 THREE HILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE S : TION XI REQUIREMENTS PAGE 3 of 21 SPECIFIC REQUESTS FOR RELIEF I. Gategory B - Valves That Will Be Tested Only_During Refueling _ Outages A. Valve Identification Valve Name and Function Valve Number Reactor Bldg. Sump Recir. Suction DH-V6A/B River Water to EF Pumps EF-V4 River Water to EF Pumps EF-V5 B. ASME Code Section XI Requirement From Which Relief is Requested Paragraph IWV-3412(a) states that valves that cannot be operated during normal plant operation shall be full-stroke exercised during each cold shutdown. In case of frequent cold shutdowns these valves need not be exercised more often than once every three months.
C. Basis for Requesting Relief Prior to cycling DH-V6A and B the Reactor Building Sump must be drained, then blank flanges weighing ~140 lbs. must be installed in the sump on the piping leading to DH-V6A/B. In order to install the blank flange, considerable time and effort is required (i.e., maintenance personnel must enter the sump to install the blank flanges. After the test the blank flanges must be removed. There are no isolation valves other than DH-V6A/B that isolate the Reactor Building Sump from the DH System. The blank flanges are installed to prevent water in the DH piping from flooding the Reactor Building when DH-V6A/B is cpened for stroke timing. If the blank flanges were not installed, water would flow through the 14" line for -140 seconds while DH-V6A/B is opened and then closed. Because of ALARA concerns (~300 MR for installation and removal of the flanges), the proper frequency for stroke timing DH-V6A/B is refueling. Therefore, it is impractical to test DH-V6A/B on a cold shutdown frequency. In addition, a refueling interval stroke time test since 1978 has not shown any problem with DH-V6A/B.
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TABLE B-2 THREE MILE ISLAND - UNIT NO.1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 4 of 21 EF-V4 and EF-V5 supply river water as a last resort to the Emergency Feedwater Pumps (EF-P1, 2A/B). The function of the EFH System is to remove heat from the RCS when the main feedwater system is not available. Per Operating Procedure (OP 1106-6) EF-V4 and 5 are chained and locked shut and the breakers for the motor operators are open at the 480 volt power supply.
EF-V4 and 5 are opened by manual action if 1.) the Condensate Storage Tanks, 2.) Condenser Hotwell, 3.) Demineralized Water Storage Tank (Million Gallon Tank) are exhausted. The stroking of EF-V4 and 5 introduces river water, silt and corrosives into the suction of the EF-P1, 2A/B. It can be seen from the piping configuration in Figure B-2.1 that it is difficult to remove all river water from the suction piping once it has pas;ed through EF-V4 and 5. The flush involves a slow fill and drain procedure using small vent and drain lines and valves. The numerous batch fill and drain opert 'ons (fi!1 through EF-V14, drain through EF-V24 and vent through EF-V28A), which are required to minimize river water, silt and corrosives, would not be completely effective in removing the contaminants. The appropriate interval for this evolution is refueling.
II. Category C - Valves Which Will be Full Stroke Tested following A Refueling or A Cold Shutdown When Cold Shutdown Exceeds 30 Days. i A. Valve Identification Valve Name and Function Valve Number Condensate Storage Tank to EF Water Pumps CO-V16A/B Hotor Driven EF Water Pump Discharge EF-VilA/B EF Hater Pumps to OTSG EF-V12A/B '
Turbine Driven EF Water Pump Discharge EF-V13.
B. ASME Code Section XI Requirement From Which Relief is Requested Paragraph IWV-3522 states that check valves that cannot be operated during normal plant operation shall be full-stroke exercised during each cold shutdown. In case of frequent cold '
shutdowns these valves need not be exercised more often than once every three months.
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TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 5 of 21 C. Basis for Requesting Relief The above valves will be full service tested on a refueling basis in conjunction with Tech. .
Spec. 4.9.1.6 in accordance with Surveillance Procedure No. 1303-11.42. This procedure injects oxygenated water from the Condensate Storage Tanks through the Emergency Feed Hater pumps to the OTSGs and verifles the accident design flow rate. THI-l must limit the exposure of the secondary side of the OTSGs to omygentated water. It is not acceptable to challenge the OTSG tubes with oxygenated water in order to test the above valves more frequently than the Technical Specification requirement. The Technical Specification testing frequency meets the intent of ASME Section XI requirements. The basis of Tech. Spec. 4.9.1.6 states that refueling or cold shutdown when cold shutdown exceeds 30 days testing is adequate to insure that overall EFW system functional capability is maintained.
III. Category C Valves Which Will Be Full Stroke Tested Only During Refueling Outages A. Valve Identification Valve Name and Function Valve Number BWST to BS and DH (LPI) check valve DH-V14A/B(I)
HPI Pump Suction Stopcheck Valve From BWST MU-V14A/B HPI Pump Discharge Check Valve MU-V73A/B/C HPI Check Valve MU-86A/B HPI Check Valve MU-V94 HPI Check Valve MU-V95 HPI Check Valve MU-V107A-D HPI Check Valve MU-V220 R. B. Emergency Cooling Pump Discharge Check RR-V8A/B R. B. Emergency Cooling Coil Outlet Check RR-V9A/B/C Intermediate Cooling Water to CRD Cooling Coll CIV IC-V16 Intermediate Cooling Water to Letdown Cooler CIV IC-V18 (I) Full-stroke tested only for LPI (See Relief Request XII) r 1578XIpe ,
TABLE B-2 THREE MILE ISLAND - UNIT NO.1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS '
PAGE 6 of 21 B. ASM Code Section XI Requirement Fror. Which Relief is Requested Paragraph IWV-3522 states that check valves that cannot be operated during normal plant operation shall be full-stroke exercised during each cold shutdown. In case of frequent cold shutdowns these valves need not be exercised more often than once every three months. ;
C. Basis for Requesting Relief DH-V14A/B: These valves will be tested each refueling interval per Surveillance Procedure No.
1303-11.54 in accordance with Technical Specification 4.5.2.2b. The refueling test frequency assures that the LPI System can supply equal or greater flow than the flow assumed in the Safety Analysis. This Technical Specification test frequency should be adequate for ASME Section XI. See Table B-2.1 for a tabular presentation of the testing for DH-Vl4A/B.
All HPI valves listed above: These valves will be full-stroke exercised on = rafueling interval basis in conjunction with Surveillance Procedure No. 1303-11.8 in accordance with Technical Specification 4.5.2.1. The refueling interval test pumps borated water from the EWST to the reactor vessel and verifies accident design flow rate. The refueling test frequency specified by the Technical Specifications, should be adequate for ASME Section XI.
RR-V8A/B and RR-V9A/D: During the functional test of these check valves river water, silt, and corrosives are introduced into the Reactor Building Emergency Cooling Colls. After the test these cooling coils must be first drained and then flushed with Nuclear Service Closed Cooling Water. The drain and flush water is drained to the Reactor Building Sump and this l
produces large quantitles of water that must be processed through the liquid waste disposal system. Therefore, a quarterly or cold shutdown test is not practical. Per Technical Specification 4.5.2, these check valves will continue to be tested on a refueling frequency (approximately every 12 months).
IC-V16 and IC-V18: These check valves are CIVs that remain open during normal plant It is operation to supply cooling water to the CRD cooling coils and the Letdown coolers.
not possible to stop flow in these lines for a test of IC-V16 and IC-Vl8 without upsetting the reactor plar.t. The safety function of IC-V16 and IC-Vl8 is to close and act as CIVs.
Therefore, a leak rate Appendia J test of these valves will be conducted each refueling outage. ,
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i TABLE B-2 THREE MILE ISLAND - UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 7 of 21 IV. Concentrated Boric Acid Injection Valves That Hill Be Tested On a Refueling Interval Basis A. Valve Identification Valve Name and Function Valve Number CA-PIA /B to MU System CA-Vl77 CA-PIA /B and HDL-P13A/B to MU System WDL-V361 Isolation for CA-PIA /B and HDL-P13A/B to MU HDL-V362 B. ASME Code Section XI Requirement From Which Relief is Requested Relief is requested from paragraph IHV-3412 and IWV-3522 which states that if only limited operation is practical during plant operation, the valve shall be part-stroke exercised during plant operation and full-stroked during each cold shutdown.
C. Basis for Requesting Relief l
l The only method cf functionally testing check valves CA-Vl77, HDL-V361, and HDL-V362 during l normal operation is to inject concentrated toric acid into the Reactor Coolant Makeup System producing reactivity changes. This would adversely affect plant operation and result in significant volumes of additional radioactive waste. Testing these valves during each cold shutdown is not warranted because of the radioactive waste generated. All of the above valves are associated with the concentrated boric acid system. Also the system for these valves is l not relied upon for accident mitigation in Chapter 14 of the THI-l FSAR. The Borated Hater i Storage Tank is the accident source of Borated Water via LPI or HPI. However, general design criteria does require a concentrated boric acid injection system. In conclusion, GPUN telieves that refueling interval testing will assure the operational readiness of the above valves.
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1 TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES ,
REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 8 of 21 V. Pressure Isolation Check Valves That Hill Be Tested On A Frequency Per Technical Specification 371.6.10.
A. Valve Identification Valve Name and Function Valve Number ;
Core Flocd Tank to Reactor Vessel CF-V4A/B Core Flood Tank /LPI to Reactor Vessel CF-VSA/B LPI Pumps to Reactor Vessel DH-V22A/B B. ASME Code Section XI Requirement from Hhich Relief is Requested Paragraph IHV-3522 states that valves that cannot be operated during normal plant operation ;
shall be full-stroke exercised during each cold shutdown. In case of frequent cold shutdowns !
these valves need not be exercised more often than once every three months.
C. Basis for Requesting Relief The Reactor Safety Study (RSS), HASH-1400, identified a PWR intersystem loss of coolant accident (LOCA) which is a significant contributor to risk or core melt accidents (Event V).
The design examined in the RSS contained in-series check valves isolating the high pressure Primary Coolant System (PCS) from the Low Pressure Injection (LPI) System piping. The scenario which leads to the Event V accident is initiated by the failure of these check valves to function as a pressure isolation barrier. This causes an overpressurizatioa and rupture of the LPI low pressure piping which results in a LOCA that bypasses containment.
Valves CF-VSA/B and DH-V22A/B are inside containment and are located in the supply line from the LPI pumps to the Reactor Vessel. Therefore, these two valves are of the Event V .
l configuration. Valves CF-VSA/B and CF-V4A/B are in the line from the Core Flood Tanks to the '
Reactor Vessel. A pressure isolation failure of CF-V4A/B does not lead to a LOCA outside containment. Therefore, CF-V4A/B is not included in Technical Specification 3.1.6.10.
However, TMI-l has elected to test these valves for the pressure isolation function on the !
same frequency as CF-VSA/B and DH-V22A/B.
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TABLE B-2 THREE MILE ISLAND - UNIT no. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENIS PAGE 9 of 21 The NRC's Technical Evaluation Report (TER) prepared by Franklin Institute states that the testing frequency of CF-VSA/B and DH-V22A/B shall be prior to achieving hot shutdown following a cold shutdown of greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> duration unless testing has been performed within the previous 9 months, and prior to achieving hot shutdown after returning the valve to service following maintenance repair or replacement work. j The TER provides a comprehensive study and evaluation of the specific problem related to pressure isolation. Since the TER has specified and judged adequate the above testing frequency, there is reasonable assurance that these valves will perform their pressure barrier function.
VI. Valves That Will Only Be Part-Stroke Tested i
Valve Identification 6
A.
Valve Name and Function Valve Number l Core Flood Tank to Reactor Vessel CF-V4A/B i Main Steam to EF-UI HS-V9A/B i B. ASME Code Section XI Requirement from Which Relief is Requested ,
Relief is requested from paragraph IWV-3522 which states that if only limited operation is practical during plant operation, the check valve shall be part-stroke exercised during plant operation and full-stroke tested during each cold shutdown.
i C. Basis for Requesting Relief CF-V4A/B: These valves are part-stroke tested each cold shutdown per Surveillance Procedure 1303-11.21. Both CF-VSA/B and CF-V4A/B are of the same design and manufacturer. CF-VSA/B are in operation whenever the plant is on Decay Heat Removal and are normally closed during power operation. CF-V4A/B are in operation whenever Core Flood is required and are normally closed ,
during power operation and during Decay Heat Renoval System operation. CF-VSA/B are also in '
cperation whenever Core Flood is required. Therefore. CF-VSA/B are in operation more than CF-V4A/B and have a greater potential for degradation during cperation. The refueling 1578x/pe
VABLE B-2 1
THREE MILE ISLAND - UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 10 of 21 interval full-ficw LPI System testing of CF-VSA/B showing no degradation during service can be applied to CF-t4A/B because the service for CF-V4A/B is less severe than that of CF-V5A/B.
CF-VSA/B are full stroke tested per the code and CF-V4A/B are the same valve catalog number as CF-VSA/B. Therefore we feel confident that our proposal to only part-stroke CF-V4A/B should be adequate. Additionally, one of these valves (CF-V4A/B or CF-VSA/B) will be disassembled for visual examination at or near the end of the 10 year ISI interval per Table IWB-2500.
MS-V9A/B: Ihese check valves supply steam from the OTSGs to EF-UI. EF-UI is the turbine drive unit for the Steam Driven Emergency feedwater Pump (EF-Pi). During a cold shutdown, it is impractical to stroke tes tese /alves (full-stroke or partial-strcke) since the steam which would be naeded to cperate these valves is not available during cold shutdown conditions.
Full-stroke testing of MS-V9A/B is also impractical due to other limitations during plart conditions when steam is available. EF-PI must be tested using the recirculation line to the Condensate Storage Tank bypassing the OTSG. This is to prevent degradation of the OTSGs by excessive thermal stress cycling of the emergency feedwater nozzles. The number of thermal cycles on the emergency feedwater nozzles is limited to (40) cycles over the life of the pla.t. Due to the small size of the recirculation line, EF-P1 cannot be tested at full capacity (MS-V9A/B will not open fully). Under these restrictions it is only possible to obtain approximately 481 flow which corresponds to about 36% opening of MS-V9A/B.
Plant modifications which would be required to perform full stroke tests of MS-V9A/B either by piping in auxiliary steam or by replacing the recirculation piping with larger piping capable of recirculating the full EFH pump capacity would introduce exorbitant cost. GPUN has not fully examined the cost and safety impact of modifications which would be required to full stroke MS-V9A/B, however, we do not feel that such modifications would be beneficial.
MS-V98 was disassembled for IST examination perposes in late 1984 and found to be in excellent l condition. Since no indication of potential degradation was found, this provides additional assurance of the continued capability of MS-V9A/B to open fully when needed. In addition, MS-V9A will be disassembled and inspected at the next refuel!ng outage (end of cycle 5 refueling outage). Thereafter, either MS-V9A or B will be de.sassembled/ Inspected on a 10 year l
basis (nemt inspection due ~1994) if the inspection of MS-V9A proves satisfactory. If I degradation is found which would make the valve's full stroke capability questicnable, then the other valve (MS-V9A or B) would be disassembled and inspected during that same outage.
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TABLE B-2 ,
THREE MILE ISLAND - UNIT NO. 1 PERIGOIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 11 of 21 It is impractical to test MS-V9A/B when steam is not available and it is also impractical to perform a full stroke test on MS-V9A/B. GPUN concludes that quarterly testing of MS-V9 at 481 ,
flow (361 open) when steam is available and disassembly each 10 years meets the intent of the ASME Code Section XI and the relief which is being requested is therefore justified.
VII. Check Valves That Will Be Disassembled Once Eacn Ten Yeats A. Valve Identification Valve Name and Function Valve Number Sodium Hydroxide Tank Supply to Reactor Building BS-V52A/B
! Spray Pumps B. ASME Code Section XI Requirement from Which Relief is Requested Relief is requested from paragraph IWV-3522 which states that if only limited operation is practical during plant operation, the check valve shall be part-stroke exercised during plant operation and full-stroked during each cold shutdown.
C. Basis for Requesting Relief Given the pipe geometry there is no method of part-stroking or full-stroking these check valves without contaminating the RCS with Sodium Hydroxide and other chemical contaminants in the dead leg of piping from these valves to the Sodium Hydroxide Tarik. During January, 1984 (Survelliance Procedure No. 1300-3P and Job Ticket Nos. CC818 and CC819) these valves were disassembled and visually examined with satisfactory results. The valve internals were found to be in "like new condition. Disassembling each of these valves at or near the end of the ten year ISI interval provides reasonable assurance of the operational readiness of BS-V52A/B.
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TABLE B-2 :
THREE MILE ISLAND - UNIT NO. I PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 12 of 21 :
VIII.Chect Valves That Will Be Given A Part-Stroke Test Each Quarter and Olsassembled Once Each Ten Years A. Valve Indentification Valve Name and Function Valve Number Reactor Bldg. Spray Header Check Valve BS-V30A/B B. ASME Code Section XI Requirement from Which Relief is Requested l Relief is requested from paragraph IWV-3522 which states that if only limited operation is
! practical during plant operation, the check valve shall be part-stroke exercised during plant cperation and full-stroked during each cold shutdown. s
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C. Basis for Requesting Relief
('.- .
l Ihe full-stroke of BS-V30A/B would require initiation of Reactor Building Spray. This would . 't i* ' .6' '
i entall spraying the Reactor Building with borated water. ,
I On 6-20-84 (Job Ticket CE-IS4) BS-V30Awisdisasshmbledforvisualexaminationpurposes.
s The *
'N examination was satisfactory (nc, ur.usaal degradation and valve disc was free toiopen).
BS-Y30A has approximately 10 years of in-service time and th!fs is the first-time that the -x.
valve has been opened. GPUN will comitinue to disassemble either of tr.ese Mtatic valves V (alternating between A and B) during each ten year inspection interval. BS-V30A/B are '
s stainless steel and therefore, not subject to corrosive attack. GPUN is of the opinion that quarterly partial-stroke testing and disassembly, as degribed, will orovide reasonable assurance that BS-V30A/B would open if needed. In addition, if disadembly/ inspection reveals ~ ;
that the full-stroke capability of the disassembled valve may be in question, the other valve j will be disassembled and inspected at the same outage. .,
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i TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 13 of 21 IX. Valves Where Percent Increase In Valve Stroke Time Hill Not Be Calculated A. Valve Identification Valve Name and Function Valve Number Containment Purge CIV AH-VIA/D Reactor Coolant Sampling CIV CA-V2 OTSG Shell Side Sampilng CIV CA-VSA/B Containment Monitoring CIV CM-VI Containment Monitoring CIV CM-V2 Containment Monitoring CIV CM-V3 Containment Monitoring CIV CM-V4 Hydrogen Monitoring CIV HM-VIA/B Hydrogen Monitoring CIV HM-V2A/B .
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Hydrogen Monitoring CIV HH-V3A/B l
Hydrogen Monitoring CIV HM-V4A/B Hydrogen Recombiner CIV HR-V22A/B Hydrogen Recombiner CIV HR-V23A/B Makeup Letdm.n CIV MU-V3 Normal Makeup CIV MU-VIB i
Eoric Ac1d Mtx Tank to MU Tank MU-VSI Lube Water Pump NR-P2A/B/C Suction NR-V45A/B/C High Point Vent Isolation RC-V40A/B High Point Vent Isolation RC-V41A/B l NS-V52A/B/C
' Cooling Water to Reactor Building Coolers Cooling Water from Reactor Buliding Coolers NS-V53A/B/C ,
l RC-V42 l
Reactor Vessel Head Vent Isolation i
Reactor Vessel Head Vent Isolation RC-V43 Pressurizer Vent Isolation RC-V44 Lube Water P np SW-P4A/B Suction SW-V17A/B Haste Gas RC Drain Tank CIV HDG-V4
' HDL-Pl3A Discharge HDL-V49 HDL-P138 Discharge HDL-V50 1578X/pe
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! TABLE B-2 '
! THREE MILE ISLAND - UNIT NO. 1 I PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS
- PAGE 14 of 21 .
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! B. ASME Code Section XI Requirement from Which Relief Is Requested l 5 Paragraph INV-3417(a) which states that if a specified percent increase in stroke time is exceeded, test frequency shall be increased to once a month until corrective action is taken.
1 C. Basis for Requesting Relief l ..
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- The above valves have actual full-stroke times of less than one second. Thus, the valve I stroke time cannot effectively be measured using normal test equipment such as a stopwatch.
j Also it is considered impractical to rel.) ably measure changes in valve stroke times for valves
- which stroke open or closed in less than g,ne (1) second. For very short stroke times, the variation in measured stroke times can bsia large fraction of the established stroke time limit. Thus it is not practical to meaningfully identify or evaluate the stroke time changes '
', considering human reaction times and the normal timing equipment used.
In accordance with ASME Section XI IHV-3413, the maximum acceptable full-time stroke value for each of the above valves will be specified. This will ensure the operational readiness of .
j these valves. .i i
i X. FH-V12A/B ,
I During plant operation these valves are always open supplying feedwater to the OTSGs. 1Therefore it j is n_ot possible to part-stroke or full-stroke these valves closed during plant operation. Both FH-V12A/B were disassembled in 1980 after approximately four years of service and were found to be j! in satisfactory and operable condition.
l As discussed with NRC in a conference call on May 21, 1984, GPUN will develop and implement a test 4 i method (s) to verify the operability (closure capability) of FH-V12A/B before startup from Cycle 6 '
I Refueling Outage. If the test method which was discussed at that time is not feasible, GPUN will pursue other alternatives. In the interim, results of the 1980 disassembly of both FH-V12A/B j provide a reasonable basis for assurance that FH-V12A/B will remain operable.
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I TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 15 of 21 XI. Category A/C Valves That Hill Be Tested Closed On A Refueling Interval Basis A. Valve Identification Valve Name and Function Valve Number Demin. Water CIV CA-Vl92 RC Pump Seal Injection CIV MU-Vll6 NS Cooling Water CIV NS-Vil B. ASME Code Section XI Requirement From Which Relief is Requested Relief is requested from INV-3522 which states "if only limited operation is practical during alaat operation, the check valve shall be part-stroke exercised during cold shutdown."
C. 3 asis for Requested Relief CA-V192 During normal plant operation, check valve CA-Vl92 is open supplying 100 cc/ min reclaimed water purge to the No. 3 seal of each Reactor Coolant Pump. This purge supply was provided in the original design to enhance RC Pump seal reliability but is not required to maintain seal integrity and is therefore isolated on Reactor Building containment is lation signals.
CA-Vl92's only safety function is to close to provide containment isolation. The containment isolation function will be verified each refueling by leak testing per SP 1303-11.18.
MU-V116 During normal plant operation, check valve MU-V116 is open supplying ~32 gpm of seal injection to the four RC Pumps. RC Seal Injection cannot be stopped to verify MU-Vil6 closes each quarter without damaging the RC Pump Seals. HU-V116's only safety function is to close to provide containment isolation. The containment isolation function will be verified each refueling per SP 1303-11.18.
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TABLE B-2
. THREE MILE ISLAND - UNIT NO. I
! PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 16 of 21 t
1 j tlS-V11
' During normal plant operation, check valve NS-Vil is open supplying cooling water to the RC i Pump motor coolers. Cooling water to the RC Pump motor coolers cannot be isolated to verify j flS-V11's closed function. Without motor cooling the RC Pump Motor would overheat and trip the
- plant. NS-V11's only safety function is to close to provide containment isolation. The i containment isolation function will be verified each refueling per SP 1303-11.18.
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! XII. Dual function Valves That Are full Stroke Tested for Only One function
- A. Valve Identification Valve Name and Function Valve Number bHST to DHR and BS System DH-V14A/B j
r DHR and CF to Reactor Vessel CF-VSA/B i
- 8. ASME Code Section XI Requirement From Which Relief Is Requested Relief is requested from INV-3522 whichistates that check valves shall be full stroked exercised during cold shutdown.
l C. Basis for Requested Relief l
DH-V14A/B i '
j Check valve DH-V14A/B supplies borated water from the Borated Water Storage Tank (BHST) to the j Decay Heat Removal Pumps (DH-PlA/B) and the Reactor' Building Spray Pumps (BS-PIA /B). DH-PIA /B are THI-l's Low Pressure Injection (LPI) Pumps. Each refueling, Surveillance Procedure i 1303-11.54 verifies LPI flowrate of >3000 gpm through DH-V14A/B. The accident design flow
- ate through DH-PIA /B is 3000 gpm and the accident design flow rate for BS-PIA /B is 1500 gpm.
lherefore, SP 1303-11.54 verifles that DH-V14A/B can pass 2/3 - 3000 gpm/4500 gpm of total DH and BS flow rate. It is impractical to structure a test where 1.) a DH pump is injecting j 3000 gpm from the BHST through DH-V14A/B to the reactor vessel, 2.) a BS pump is' recirculating j the BHST through DH-V14A/B at 1500 gpm, and 3.) the second DH pump is providing its decay heat i
1578X/pe i __ _ .- . _ _ . _ _ - . _ - . . _ , _ -
TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 17 of 21 removal function by recirculating the reactor vessel. The complexity of this evolution, time and effort do not warrant this type of testing. Conceivably, this testing could be accomplished by filling the transfer canal part way then, switching to the next loop to be ,
tested. The risk of incorrect valve lineup leading to pump damage and hours spent switching loops and verifying valve lineups do not make such testing desirable. There are ALARA concerns when switching loops (see Relief Request XIII). An additional concern is refueling -
water clarity / cleanup due to crud that will be broken loose during the 3000 gpm injection into the reactor vessel. GPUN believes the burden of such testing is not warranted and that such testing is impractical. The refueling (2/3) flow rate test demonstrates that DH-V14A/B has the capability to open fully, if needed.
i CF-VSA/B CF-VSA/B's dual function is to provide LPI and core flooding. Immediately upstream of CF-VSA/B is CF-V4A/B. CF-V4A/B and CF-VSA/B see essentially the same service condition and they are the same size, manufacturer and catalog number. CF-V4B was disassembled in November 1983 and was found to be in satisfactory condition. This disassembly of CF-V4B, provides !
further evidence that CF-VSA/B can open fully if needed.
CF-V4A or CF-V4B or CF-VSA or CF-V5B (1 of the four) will be disassembled each 10 years for an inspection. If degradation which would make the valve's full-stroke Capability questionable.
.is found, then the remaining three valves will be disassembled and inspected during that cutage.
See Table B-2.1 for a tabular presentation of the testing for DH-V14A/B and CF-VSA/B.
XIII. DH-V16A/B i A. Valve Identification palve Name and function Valve Number LPI (DH) to Reactor Vessel DH-V16A/B 1578X/pe
- , - . - v -- -~-- e - . ,- ---r -- - - , - - - - - r
TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 18 of 21 B. ASME Code Sectio!. XI Requirement from Which Relief Is Requested INV-3412 states that valves shall be full stroked during each cold shutdown.
C. Basis for Requesting Relief Either DH-V16A or DH-V16B will be full-stroke tested on a cold shutdown frequency by the normal operation of providing Decay Heat Removal flow of >3000 gpm. In addition, both A and B valves will be full-stroke tested each refueling interval. See Table B-2.1 for a tabular presentation of testing for DH-V16A/B.
The full-stroke test for the idle DH-V16 would require a deliberate shift of Decay Heat Removal (DHR) Trains. For cold shutdowns of short duration, it is impractical to require a complete system realignment to the opposite DHR system for the sole purpose of cycling this single check valve at design system flow rate. The basis for this conclusion is that:
(1) The system realignment requires manipulation of several large manual valves (DH-V12A and B) inside radiation areas where doserate could be as high as 500 mR/hr. Stay time in the radiation area to cycle one DH-V12 is 15 minutes for three men. The extra radiation exposure and rad waste generation to cycle this one check valve (DH-V16A or B) is not consistent with ALARA principles.
(2) The system realignment may be critical path time on a recovery from a forced outage. The cost of delaying startup in order to stroke this one check valve makes testing at each cold shutdown impractical.
(3) A requirement to full-stroke this check valve each cold shutdown (if not performed within the last 3 months) would require the start of a large Engineered Safeguards (E.S.) pump and motor for the sole purpose of full-stroking this one check valve. The extra wear on this E.S. system merely to full-stroke one check valve is undesirable.
(4) For normal planned cold shutdowns, routine maintenance activities have and will require that each DHR system be operated while the other is down for maintenance. When this occurs both DH-V16A and B will be full-stroked.
1578X/pe
TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 19 of 21 XIV. MS-V6 A. Valve Identification Valve Name and Function Valve Number EF-P1 Main Steam Control Valve MS-V6 B. ASME Code Section XI Requirement from Which Relief Is_ Requested IHV-3412 and 3413 which state that valves shall be full-stroke exercised and that the-limiting value for full-stroke time of each power operated valve shall be specified by the Owner.
C. Basis for Requesting Relief 1 It is not possible to full-stroke and time MS-V6 since its stroke has been mechanically set to open no more than 65% to protect EF-01. EF-Ul is the steam drive unit for the Emergency Feedwater Pump (EF-PI). MS-V6 is the steam control supply valve to EF-Ul. The only method of opening MS-V6 to 65% open is to change the setpoint of the Pressure Controller (PC-5) for l MS-V6. It is impractical to change the setpoint of an Important to Safety component on a l
quarterly frequency. Changing the setpoint of PC-5 could place the plant in an unsafe condition by the loss of EF-P1 if the controller was not returned to the correct setpoint.
GPUN believes it impractical to change the setpoint of PC-5 on a quarterly frequency.
Therefore, MS-V6 will be part-stroke tested and fall safe tested each quarter when main steam is available to run EF-Pl. As an alternative to stroke timing MS-V6, the startup time of EF-P1 will be measured each quarter to assure that the startup time is within the time specified in the FSAR (~40 seconds). This will assure the operational readiness of MS-V6.
XV. RR-V6 A. Valve Identification Valve Name and Function Valve Number Energency Cooling Coll Control Valve RR-V6 1578X/pe
. . _ _ _ _ - - _ . . , _ _ _ _ _ _ - _ _ _ _ _ . ___.__m__ -
l TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 i
PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 20 of 21 B. ASME Code Section XI Requirement From Which Relief Is Requested IHV-3417 which provides acceptance criteria for acceptable percent increase in stroke time.
C. Basis for Requesting Relief RR-V6 is a control valve which falls open (air is bled from the diaphragm operator and a ,
spring in the operator pushes the valve open). The stroke time is a function of how fast the !
air is bled from the diaphragm and does not present any meaningful information to assess "
operational readiness of the valve. Percent increase in stroke time will not be calculated.
However, a limiting value for full-stroke time will be specified and used for acceptance criteria.
XVI. Control Valves That Fall Open on Area Coolers A. Valve Identification Valve Name and Function Valve Number Cooling Water to AH-E-8A/B NS-V54A/B (SF Pump Room Cooling Coils)
Cooling Hater to AH-E-24A/B NS-V55A/B (EFW/IA Room Cooling Coils)
Cooling Hater to AH-E-15A/B NS-V56A/B ,
(NS & DC Pump Area Air Cooler) :
Cooling Water to AH-E-27A/B SW-V24A/B (Screen House Area Air Cooler) ,
B. ASME Code Section XI Requirement From Which Relief Is Requested IHV-3413 states valves shall be stroke timed.
l l
[ 1578X/pe
TABLE B-2 THREE MILE ISLAND - UNIT NO. 1 PERIODIC INSERVICE INSPECTION PROGRAM - VALVES REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS PAGE 21 of 21 C. Basis for Requested Relief The above valves are control valves and they fail open. They are open when the cooler is idle and they throttle based on the cooling needs of the cooler when the cooler is placed inservice. The valves are interconnected with the operation of the coolers and there is no installed mechanism that will allow full-stroking of the valves. It is impractical to add hardware changes that will allow full-stroking of these valves since the increment of safety gained by such a hardware change would be negligible. Stroke timing of these control valves is not relevant to their operability, especially valves that fall open to the coolers. As an alternative to stroke timing, the respective cooler will be placed inservice and the control valve function will be demonstrated by acceptable cooler operation.
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1578X/pe
m l
TABLE B-2.1 TESTING FREQUENCY AND METHOD OF SEVERAL DH, BS AND CF VALVES VALVE VALVE FUNCTION QUARTERLY COLD SHUTDOHN(I) REFUELING DH-VI4A/B BWST to Reactor Build- Partial for both A&B None (See Relief Full stroke test for LPI(2) ing Spray & DH (LPI) valve (~1750 gpm) Request III) for both A&B valve (3000 gpm) l DH-V16A/B DH (LPI) to Reactor Partial for both A&B Full stroke test Full stroke test for both Vessel valve (~925 gpm) for elther A or B A&B valve (3000 gpm) valve (3000 gpm)(4)
DH-V22A/B DH (LPI) to Reactor None (See Table B-1, Full stroke test Full stroke test for both Vessel Decay Heat Removal, for both A&B valve ALB valve (3000 gpm)
Footnote 3) (3000 gpm) l
! CF-VSA/B Core Flood & DH (LPI) None (See Table B-1, Full stroke test Full stroke test for LPI(2),(3) l to Reactor Vessel Core Flood System, for LPI(2) for for both A&B valve (3000 gpm) l Footnote 3) both A&B valve (3000 gpm)
Footnotes:
(1) Cold shutdown test frequency as defined at the beginning Table B where " Symbols" are defined.
(2) Full stroke test for LPI. See Relief Request XII.
(3) Also disassembled / visual examined per Relief Request XII.
(4) See Relief Request XIII.
l i
1580X/pe i
r TABLE B-3 Page 1 of 5 Limiting Value of Stroke Time for IST Motor Operated Valves VALVE LIMITING STROKE TIME (Sec.) OPEN or CLOSE
- 1. AH-VIA <l.0 CLOSE
- 2. AH-VID <1.0 CLOSE
- 3. AH-VlB <2.0 CLOSE
- 4. AH-VIC <2.0 CLOSE
- 5. BS-V1A 20 OPEN
- 6. BS-VlB 20 OPEN
- 7. BS-V2A 27 OPEN
- 8. BS-V2B 25 OPEN
- 9. BS-V3A 65 OPEN
- 10. BS-V3B 60 OPEN
- 11. CA-V1 27.8 CLOSE
- 12. CA-V2 2 CLOSE
- 13. CA-V3 20.5 CLOSE
- 14. CA-V4A 25.5 CLOSE
- 15. CA-V4B 22.8 CLOSE
- 16. CA-V5A 2 CLOSE
- 17. CA-V5B 2 CLOSE
- 18. CA-V13 8.6 CLOSE
- 19. CA-V189 5.9 CLOSE
- 20. CF-V2A 23.3 CLOSE
- 21. CF-V2B 18.3 CLOSE
- 22. CF-Vl9A 3.0 CLOSE
- 23. CF-V19B 3.0 CLOSE
- 24. CF-V20A 3.0 CLOSE
- 25. CF-V20B 3.0 CLOSE
- 26. CM-Vi 2 CLOSE
- 27. CM-V2 2 CLOSE
- 28. CM-V3 2 CLOSE
- 29. CM-V4 2 CLOSE
- 30. DH-V1 144 OPEN
- 31. DH-V2 144 OPEN
- 32. DH-V3 120 OPEN
- 33. DH-V4A 12 OPEN
- 34. DH-V4B 12 OPEN 1579X/pe
- r. .
TABLE B-3 Page 2 of 5 Limiting Value of Stroke Time for IST Motor Operated Valves VALVE LIMITING STROKE TlME (Sec.) OPEN or CLOSE
- 35. DH-V5A 13 OPEN
- 36. DH-V5B 13 OPEN
- 37. DH-V6A 86.25 OPEN
- 38. DH-V6B 83.75 OPEN
- 39. DH-V7A 25.4 OPEN
- 40. DH-V7B 26.3 OPEN
- 41. DR-VIA 188 OPEN
- 42. DR-V1B 188 OPEN
- 43. EF-V4 39 OPEN 44 EF-V5 41 OPEN
- 45. EF-V30A 7.5 OPEN
- 46. EF-V30B 7.5 OPEN
- 47. HM-VIA 2 OPEN
- 48. HM-VIB 2 OPEN
- 49. HM-V2A 2 OPEN
- 50. HM-V2B 2 OPEN
- 51. HM-V3A 2 OPEN
- 52. HM-V3B 2 OPEN
- 53. HM-V4A 2 OPEN
- 54. HM-V4B 2 OPEN
- 55. HR-V22A 2 OPEN
- 56. HR-V22B 2 OPEN
- 57. HR-V23A 2 OPEN
- 58. HR-V23B 2 OPEN
- 59. IC-VIA 31 OPEN
- 60. IC-VIB 28 OPEN
- 61. IC-V2 38.0 CLOSE
- 62. IC-V3 18.0 CLOSE
- 63. IC-V4 15.0 CLOSE
- 64. IC-V6 3.0 CLOSE
- 65. MS-VIA <120 CLOSE
- 66. MS-V1B <120 CLOSE
- 67. MS-V1C <120 CLOSE
- 68. MS-VID <120 CLOSE 1579X/pe
TABLE B-3 Page 3 of 5 Limiting Value of Stroke Time for IST Motor Operated Valves VALVE LIMITING STROKE TIME (Sec.) OPEN or CLOSE
- 69. MS-V2A 74 CLOSE
- 70. MS-V2B 74 CLOSE
- 71. MS-V4A 5 OPEN
- 72. MS-V4B 5 OPEN
- 73. MS-V10A 33 OPEN
- 74. MS-V108 33 OPEN
- 75. MS-V13A 23 OPEN
- 76. MS-V138 23 OPEN
- 77. MU-VIA 36 OPEN
- 78. MU-VIS 37 OPEN
- 79. MU-V2A 31.3 CLOSE
- 80. MU-V2B 31.7 CLOSE
- 81. MU-V3 2.0 CLOSE
- 82. MU-V12 26 CLOSE
- 83. MU-V14A 14 OPEN
- 84. MU-V14B 15 OPEN
- 85. MU-V16A 13.7 OPEN
- 86. MU-V166 13.7 OPEN
- 87. MU "16C 13.7 OPEN
- 88. MU-V16D 13.7 OPEN
- 89. MU-V18 2.0 CLOSE
- 90. MU-V20 6 CLOSE
- 91. MU-V25 19.33 CLOSE
- 92. MU-V26 3.0 CLOSE
- 93. MU-V36 10 CLOSE
- 94. MU-V37 11 CLOSE
- 95. MU-V51 2.0 OPEN
- 96. MU-V217 9.0 OPEN
- 97. NR-VIA 183 OPEN
- 98. NR-VlB 188 OPEN
- 99. NR-VIC 176 OPEN 100. NR-V4A 196 CLOSE 101. NR-V4B 198 CLOSE 102. NR-V45A 2 OPEN 1579X/pe
r TABLE B-3 Page 4 of 5 Limiting Value of Stroke Time for IST Motor Operated Valves VALVE LIMITING STRCKE TIME (Sec.) OPEN or CLOSE 103. NR-V45B 2 OPEN 104. NR-V45C 2 OPEN 105. NS-V4 33.0 CLOSE 106. NS-V15 54.0 CLOSE 107. NS-V35 36.0 CLOSE 108. NS-V52A 2.0 OPEN 109. NS-V52B 2.0 OPEN 110. NS-V52C 2.0 OPEN 111. NS-V53A 2.0 OPEN 112. NS-V53B 2.0 OPEN 113. NS-V53C 2.0 OPEN 114. PP-V100 4.5 OPEN 115. PP-V103 17.0 OPEN 116. PP-V132 13.0 OPEN 117. PP-V135 4.65 OPEN 118. RB-V2A 47.0 CLOSE 119. RB-V7 36.0 CLOSE 120. RC-V1 7 OPEN 121. RC-V2 13.8 CLOSE 122. RC-V3 38 OPEN 123. RC.V4 32 OPEN 124. RC-V28 9.5 OPEN 125. RC-V40A 2.0 OPEN 126. RC-V40B 2.0 OPEN 127. RC-V41A 2.0 OPEN 128. RC-V41B 2.0 CPEN 129. RC-V42 2.0 OPEN 130. RC-V43 2.0 OPEN 131. RC-V44 2.0 OPEN 132. RR-V1A 183 OPEN 133. RR-V1B 181 OPEN 134. RR-V3A 75 OPEN 135. RR-V3B 75 OPEN 136. RR-V3C 75 OPEN 1579X/ce
TABLE B-3 Page 5 of 5 Limiting Value of Stroke Time for IST Motor Operated Valves VALVE LIMITING STROKE TIME (Sec.) OPEN or CLOSE 137. RR-V4A 73 OPEN 138. RR-V4B 73 OPEN 139. RR-V4C 74 OPEN 140. RR-V40 74 OPEN 141. RR-V5 191 OPEN 142. RR-V10A 25 OPEN 143. RR-V10A 29 CLOSE 144. RR-V10B 29 OPEN 145. RR-V10B 31 CLOSE 146. SW-V17A 2 OPEN 147. SW-V17B 2 OPEN 148. WOG-V3 10.5 CLOSE 149. WDG-V4 2 CLOSE 150. WOL-V49 2.0 OPEN 151. WOL-V50 2.0 OPEN-152. WOL-V61 5.25 OPEN 151. WOL-V62 2.90 CLOSE 154. WOL-V89 14.5 OPEN 155. WOL-V90 7.4 OPEN 156. WOL-V91 11.4 OPEN 157. WOL-V92 8.5 OPEN 158. WOL-V303 19.5 CLOSE 159. WOL-V304 3.0 CLOSE 160. WOL-V534 11.1 CLOSE.
161. WOL-V535 5.9 CLOSE 1579X/pe
FIGURE B-2.1 EMERGENCY FEEDWATER PIPING CONFIGURATION SKETCH 8"Pi s f/ soi-d' gap,f 'g,fgye 25' / 4'If W
/
V 3' 8
/ '*> * ~ J'
/ >o fff- V(,
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, J(N "1'Ai% $b r,
E/. 2 91' 7, 4 fgp ff hh 6f-PJA $
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[EF JLi'tT,c.)[Er-K~
&#frs t y 1 Jnipde sppnt.jeaf f p,p Adwan aines
^' 11 ll ag poje de beer EFVIA/G, EF- v'li sd EF Vd.
i
TABLE C.1 (SUPPLEl1 ENTAL)
DISASSEMBLY HISTORY OF TMI-1 VALVES sertice condition Problem and Piping Design Fluid Pressure (psig)/ Corrective Temo (*F) Use/E.w oggigd_ Wear _ ._lyng_.._S i2 C_.._QpffA10C_ h f3Cturer Hqdel Disaisembly Action Comments
__yalee Envi rontnent BS-930A Borated Water 200/300 Cycle open (part- Check 8" None AloyCo N2376 6/84 None None stroke) only for Special Storage Tank Water Inservice Testing each quarter /None i
MS V9B Main Steam 1050/600 Open (part-stroke) Check 6" None Walworth 5350WE 12/84 None None only for electri-l J
cal surveillance and Inservice Testing (supplies steam to Drive Unit for the Tur-bine Driven Emerg-ency Feedwater Pump)/ Slight 25/110 Cycled open (part- Check 6" None Walworth 5341WE 12/84 None Internals Ef-U3 River Water are sched-stroke) only for Inservice Testing uled to be each quarter /None removed dur-ing the March 1986 Eddy Current Outage I
I 4
s tats r /pe
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TABLE C.2 PHOTOGRAPH INDEX PHOTO NUMBER DATE DESCRIPTION 1 6/84 BS-V30A showing disc (face side), disc arm and hinge.
2 6/84 BS-V30A disc / arm nut connection.
3 6/84 Looking down into BS-V30A. Seat with some water in bottom of valve body.
4 12/84 MS-V9B disc and disc / arm washer and nut.
5 12/84 MS-V9B disc / arm stud and wasner and nut.
6 12/84 MS-V98, flashlight holding disc arm in up position. Disc arm was not removed from valva body.
7 12/84 EF-V3 disc (face side) hinge pin and ears on bonnet through which hinge pin was installed.
8 12/84 EF-V3 disc (face side).
9 12/84 Looking down into EF-V3 showing disc seating surface.
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