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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20127N2711992-11-24024 November 1992 Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20128M7701992-03-31031 March 1992 Amend 92-01 to Second Ten Year ISI Program ML20094P5411992-03-19019 March 1992 Rev 23 to Procedure 5.4.6, Primary Containment Venting & Purging Under Emergency Conditions, Revising Coversheet & Attachment 1,Sheet 3 of 5,page 8 of 20 ML20058E5281990-10-25025 October 1990 Rev 1 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20005F0791989-12-13013 December 1989 Rev 0 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program. ML20247N3611989-07-31031 July 1989 Rev 2 to Dcrdr Program Plan ML20245D6551989-04-21021 April 1989 Power Ascension Program Resumption Plan ML20235R3441988-12-28028 December 1988 Rev 26 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test ML20235R4671988-12-22022 December 1988 Rev 25 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test ML20155C0141988-09-28028 September 1988 Rev 3 to Appendices to Restart Plan ML20155F9041988-09-0707 September 1988 Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating Procedures ML20153H6481988-08-31031 August 1988 Ascension Program ML20235R3801988-08-0909 August 1988 Special Post-Startup Training Program to Satisfy Requirements of NUREG-1021,Section ES-109,Parts B.2.e & B.2.f for Reactor Operator Licensed Personnel & Parts D.2.e & D.2.f for Senior Reactor .. ML20150C0271988-05-26026 May 1988 Rev 2 to Vol 2 to Apps to Restart Plan ML20151F9481988-04-0606 April 1988 Rev 2 to Emergency Operating Procedure 1.3.4-13, Emergency Operating Procedures Verification Program ML20151C8111988-04-0606 April 1988 Rev 3 to Emergency Operating Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures ML20151F9681988-04-0606 April 1988 Rev 2 to Emergency Operating Procedure 1.2.4-14, Emergency Operating Procedure Validation Program ML20151C8151988-03-28028 March 1988 Emergency Operating Procedures Training Program Summary Description ML20153B1061988-03-14014 March 1988 Rev 1B to Inservice Testing Program for Pumps & Valves, Pilgrim Nuclear Power Station ML20236T2171987-11-20020 November 1987 Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating Procedures ML20236T2241987-11-20020 November 1987 Rev 3 to Apps to Pilgrim Nuclear Power Plant-Specific Technical Guidelines ML20236T2361987-11-20020 November 1987 Collection of Plant Operating Procedures Utilized to Develop,Process & Issue Plant-Specific Emergency Operating Procedures ML20236N7751987-11-12012 November 1987 Rev 1 to Procedure 3.M.1-1, Preventive Maint ML20236F0201987-10-26026 October 1987 Rev 1 to Vol 2 of Pilgrim Nuclear Power Station Apps to Restart Plan ML20155F9171987-10-16016 October 1987 Rev 1 to Procedure 1.3.4-13, Emergency Operating Procedure Verification Program ML20155F9111987-10-15015 October 1987 Rev 2 to Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures ML20235X2461987-10-15015 October 1987 Power Ascension Program ML20195H6341987-09-22022 September 1987 Rev 23 to Procedure 8.7.3, Secondary Containment Leak Rate Test ML20238E8311987-09-0101 September 1987 Revised Nuclear Operations Dept Procedures,Including Rev 5 to Procedure 5.7.4.1.1, Post-Accident Sampling Sys,Small Vol Liquid Sample from Jet Pump Flow Sensing Line & Rev 6 to Procedure 5.7.4.1.2, ...Undiluted Liquid Sample.. ML20236G4071987-07-30030 July 1987 Vol 1 to Pilgrim Nuclear Power Station Restart Plan. Rev 0 to Vol 2,appendices,encl ML20236F9531987-07-28028 July 1987 Matl Condition Improvement Action Plan ML20155F9201987-07-10010 July 1987 Rev 0 to Procedure 1.3.4-14, Emergency Operating Procedure Validation Program ML20204F7431986-06-16016 June 1986 Rev 1 to Temporary Procedure Tp 86-85, RHR Intersys Leakage Assessment & Controlled Leakoff ML20204F7301986-06-10010 June 1986 Rev 11 to Procedure 2.3.2.1, Panel Procedures Panel 903 Left ML20204F7481986-06-10010 June 1986 Rev 0 to Temporary Procedure Tp 86-84, RHR Discharge Piping Venting Procedure ML20137M4811985-08-21021 August 1985 Rev 1 to Procedure 5.7.5, Estimating Core Damage ML20138R4501985-07-19019 July 1985 Rev 0 to Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures ML20128N9341985-03-0606 March 1985 Rev 0 to Procedure 5.7.5, Estimating Core Damage ML20101S7121984-12-13013 December 1984 Rev 11 to Procedure 2.1.12, Daily Diesel Generator Surveillance ML20101S7201984-12-12012 December 1984 Rev 15 to Procedure 8.9.1, Manually Start & Load Each Diesel Generator Once Per Month 1999-03-23
[Table view] |
Text
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i i
BOSTON l
EDISON -
PILGRIM NUCLEAR POWER STATION RHR INTERSYSTEM LEAKAGE ASSESSMENT AND CONTROLLED LEAK 0FF f
TP 86-85 l
I List of Effective Pages l
7 TP 86-85-1 TP 86-85-2 TP 86-85-3 TP 86-85-4 TP 86-85-5 Attachments TP 86-85A-1 TP 86-85A-2 TP 86-858-1 TP 86-858-2 Approved A L 4 A cee.easea
@leardp'erationsManager I Date G,//(, /%
! 8608040295 860616 PDR ADOCK 05000293 G PDR Expiration Date To!/6!Pfr l A4-1 TP 86-85-1 Rev. 1
I. PURPOSE: ,
To provide station personnel with a method of establishing a controlled leakoff of the RHR Discharge Piping to prevent increases in pressure due to leakage past the RHR Injection Isolation Valves. His proce: lure may be used to establish a controlled leakoff when the RER system becomes pressurized from leakage past its isolation valves, or in advance of such leakage.
II. DISCUSSI 2:
Leakage past th'e RHR Injection Isvlation Valves, principally the MOV1001-28B and MOV1001-29B, have lead to repeated annunciation of the "PRR Discharge or Shutdown Cooling Suction High Pressure" alarm. Prior to maintenance on the MOV1001-28B valve, leakage was measured at .33 gpm at 975 psig. Mis procedure will establish a controlled leakoff from the RHR Punp Discharge Piping to the Torus via the 2" 100D valve bypass around the Punp Discharge check valve. His will prevent BHR punp discharge piping pressure from pressurizing when in-leakage rates less than 1.0 gpm are present.
III. REFERE2CES:
A. P&ID M-241, Sheet 1 & 2 B. RHR Task Force Report, Revision 1 Dated 5/5/86 C. ESR Response 86-153 Dated 4/24/86 D. PDC 86-30 -
- IV. PREREKIIISI'IES
J A. Radiation Work Permit and Maintenance Request to accouplish testing.
l B. Watch Ihgineer's permission to start test as indicated on this L Procedure and/or Maintenance Request.
C. Inplementation of procedural step VIIA 4 will make 1 PHR pung unavailable. Se requirements of Technical Specification 3.5A5 nust be a$ dressed prior to inplementing procedure step VII.A.4.
V. PRBCAUTIONS:
A. When draining and venting systems that are potentially contaminated, Standard PNPS Radiological Protection practices nust be followed.
B. If an abnormal condition is encountered during the performance of this test, place the system in a safe condition, terminate the test and investigate the cause.
C. If a controlled leak-off is sucessfully inplemental by this procedure, a flow of approximately 1 GPM will be continuously
'IP86-854 Rev.1 A4-2 l
l
diverted to the torus. Operations should be aware of this inventory addition and the need for increased water level
, control for the torus.
VI. APPARATUS:
A. Venting bottle B. BLbber hose, various lengths VII. PIOCEDURE:
STEPS A and B may be performed in any sequence. Step B may be performed separately for information purposes.
A. Determine the In-Ieakage Rate and Establish Controlled Leakoff NOIE: RHR IOCP 'B' MUST NOT BE IN SERVICE WHEN C0tOUCTING THIS STEP.
THIS STEP USES THE B IOCP. THE CBOSS-TIE MAY BE mnRm IF ESSENTIAL TERATION T THE A BHR IOCP EKISTS.
- 1. Record system pressures as indicated on attachment A before clearing alarm (if possible) by reducing system pressure, per alarm procedure 2.3.2.1 annuncator B-7.
- 2. Close the 801001-10(D valve if open.
(Note number of turns to seat valve)
- 3. Iet system pressure reset to approximately 150 psi.
l 4. Close the 'D' BHR suction valve MO 1001-7D an interlock will prevent inadvertant pung start when there is no suction path, i
- 5. Attach hosing to the 3/4 inch vent connection that is on the l punp side of valve H01001-100D and connect other end to vent bottle.
- 6. Route petcock drain hose to floor drain , open the petcock.
- 7. Open the vent valves HD 1001-34(D and 341D.
- 8. Batablish a leak off flow rate to maintain a system pressure of 150 psig by slightly opening valve H01001-10(D note the nunber of turns open.
- 9. When pressure he stabilized at approx.150 psig close the petcock at the bottom of the vent bottle. Time the interval required to fill the bottle from the 1 gallon nark to the 5 gallon mark to measure the in-leakage. Record the time to fill the 4 gallons. A time of less thm 4 minutes is not i
acceptable per the acceptance criteria.
I 2P86-85-3 Rev. 1 l
l A4-3
~
i l
- 10. If the acceptance criteria is met, tie wrap the 1001-100D in its present position. If the acceptaice criteria is not met inform the Watch Engineer.
- 11. Close the BD 1001-340D and 341D valves and replace the vent l l cap. Double verification is required. l
} 12. Re-open MO 1000-7D with the control switch.
B. Conduct a Tenperature Survey of M Piping f
l 1. Tenperature sensitive monitors (self alhesive strips) have been installed on the M system piping at the locations as shown on Attachment B. Se indicators are located below the thermal insulation on the piping. m rigid insulation, a block of the insulation nust be removed prior to reading the tenperature indicators. m blanket type insulation, the insulation uust be pushed aside in order to real the tenpera-ture indicators. Insulation nust be restored to the as-found condition after each tenperature reading is taken.
Check the tenperature indicators for change and record the temperatures on Attachment B.
! 2. Use a portable temperature monitoring device to survey M system piping and record the location and present pipe wall tenperature on Attachment B.
- 3. Record M system pressures in locations indicated by Attach-ment B.
l 4. Forward the temperature survey data sheet to the STA on shift for further disposition by NED.
I e
VIII. ACCEP1NCE CRI'IERIA:
A. His procedure will be suitable for controlling systect pressure i with system inleakage rates of 1 gpm or less. If system inleakage
! is greater than 1 gpm, a controlled shutdown should be initiated and a NED Disposition should be obtained.
B. Compare pipe wall tenperatures outboard of the nornelly closed <
- isolation valve (i.e. 1001-28A or 1001-28B) to the saturation temperatures at the pressure indicated on the local guages (PI l 1001-80A or 1001-80B). If pipe wall tenperature is equal to or within 15 F of saturation tenperature stean void formation may be present. Inform the watch engineer of this condition, and request additional aid from NED.
'IP 86-85-4 Rev 1 A4-4
i l
IX. ATDCEDENTS 7
i A. RER Leakage Assessment Setup and Data Sheet B. RHR Temperature Survey Data Sheet ,
l l
i l 'IP 86-85-5 Rev 1 1
A4-5 I
l 1
1
'IP 86-85 PHR Ieakage Assessment Set-Up md Data Sheet Watch Engineer's permission grmted to perform this procedure:
NHE date/ time / ,
EGJIPMENT SKE'ICHES FOR REFERE2CE: ,
e N 6 Coty/ PC Y 1o ver rt
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- 1. Initial Conditions: .8C }
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- 'Ihis investigation includes data for RER loops A and B.
To read loop pressures, slowly open the instrument root valves to obtain the readings, then close the root valves when the rea31ngs have been taken.
INS'IBUMENT FIEID I4 CATION READING (psig) NN BY PI 1001-30A in CIO shop west wall PI 1001-30B outside B RHR valve room PI 1001-80A A RHR Quadrmt at rack 2259 PI 1001-80B B RHR Quadrmt at rack 2262 Instrument root valves verified closed by: date
- 2. Ieakage Assessment / Controlled Ieakoff:
- Close valve HD 1001-10(D (if open) record the ntmber of turns to seat the valve: turns
- Iet RER system pressure rise to approx.150 psig.
'IP 86-85-Al Dev.1 l A4-6
'IP 86-85 RER Ieakage Assessment Set-Up and Data Sheet (Cont.) .
- RHR pung "D" suction valve MO 1001-7D closed. Verified by:
- Attach hose from venting bottle to the 3/4 inch vent downstream of B0 1001-100D. Performed by:
- Venting bottle petcock drain hose routed to floor drain, petcock opened.
Performed by:
~
- 3/4 inch vent valves HD 1001-340D , 341D cracked open.
Perfoned by:
- Determine leakage rate by throttling HD 1001-10(D and maintaining approx.
150 psig on guage PI 1001-80B or test guage installed at HD 1001-341D.
- When pressure has stabilized, close venting bottle petcock.
- Measure the time required to fill the venting bottle from the lower mark to the upper mark. 'Ihis difference is 4 gallons. Record the fill time and the set pressure.
Fill time minutest secortis Set Pressure psig
- Compute leakoff rate : 4 gallons / time (minutes)= apn
- Acceptance criteria is 1.0 gpm or less ( or a fill time of 4 min or more)
Criteria met or Not met determined by If the acceptance criteria is met tie wrap the B01001-10(D valve securely in its present position.
BE ANARE 'IBAT KEEP FILL SYSTEM WA'IER IS BEING DIVER'ITD PElEANENILY 'IO 'IHE
'ICEUS - AN INCREASED ANARNESS CF '!OEUS LEVE[, IS NECESSARY.
NCPIE: If the acceptance criteria is not met, then inform the Watch 1 Ehgineer inmediately and return the B01001-100D vaJ ve to the closed position. A CCNfirmn SHLFIDOWN SHALL BE INITIA'ITD AE 'IHE NUCLEAR E2EINEERING DEPARIMENT ALER'IED 'IBAT ADDITICNAL EVALUATICN IS NEEDED.
- Close the HD 1001-34(D and 341D 3/4 inch vent valves:
closed by: date verified by: date Forward this signoff sheet with the Shift Technical Advisor for m3ditional i
evaluation. When evaluations are couplete the Shift AA is to tratsmit this form to DOC for permanent record.
f
'IP86-85-A2 Rev. 1 A4-7
. - - - - - , . , _ - . _ , -_ _, r , , _ , . . , , , _ -
TP 86-85 Attachnnet B ME System Teaperature Survey Data Sheet Note: Tenperature sensitive monitors (self adhesive strips) have been installed on the Mm system piping at the locations as shown on the sketch below. 'Ihe indicators are located below the thermal insulation on the piping. On rigid insulation, a block of the insulation nust be removed prior to reading the tenperature indi-cators. On blanket type insulation, the insulation nust be pushed aside in order to read the tenperature indicators. Insulation nust be restored to the as-found condition after each tenperature reading is taken.
Note: An IMP is required for equipment room entry.
I4 CATION SKE7CH T Mm TEMPEPA'IURE MONITORS (Note: See data sheet on following page.)
A RIR IDOP B RIH 4 "RP A RIR Valve Room B RIR Valve Room LI[^U j 4
f 8 BG f '
m 4@/
3 F Q" A3 - m -A y M o roor-19A 3p aggy anB gg -c By i
) /
fao i ooi-28A Mo @/-( sa AL r-A2 2I - BL Vs5NXNNN\
f4 0; a >
\ F~L
\ \ OOR
\ \ \\\\ \
I TP 86-85-B1 A4- 8
1P 86-85 Attachnnet B -
RRR System Tenperature Survey Data Sheet (Cont.)
Temperature Survey Instrument Used:
Time of Highest Current Data reation DM ina - DM ina DM ina Taken Bv Al l l l l l A2 l l l I I A3 l l l l l A4 l l l l l B1 l l l l l B2 l l l l l B3 l l l l l B4 l l l l B5 l l l l B6 I I I I I B7 l l l l l ,
B8 l l l l l
~
To read loop pressures, slowly open the instrument root valves to obtain the readings, then close the root valves when the readings have been taken.
INSIMMEtTP F M c L TATIm READING (psig) Tsat ( F) l PI 1001-30A in CIO shop west wall
! PI 1001-30B outside B RER valve room PI 1001-80A A RHR Quadrant at rack 2259 PI 1001-80B B RHR Quadrant at rack 2262 Instrument root valves closed by: date verified by: cete Compare current pipe wall tenperature readings Al, A2 with raturation tenperature at pressure of PI 1001-80A.
Compare current pipe wall tenperature readings B1, B2 with saturation temperature at pressure of PI 1001-80B.
If pipe wall temperature is equal to or within 15 F of the saturation tenperature, steam void formation may exist. Inform the Watch Ehgineer that NED assistece is needed for additional evaluation.
'IP 86 85 B2 Rev.1 A4-9
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9 ATTACHMENT 5 Temporary PNPS Procedure TP 86-84 RHR Discharge Piping Venting Procedure l
l
!