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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 REPORT
MONTHYEARML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test ML20056E2221993-05-19019 May 1993 Final Pilgrim Nuclear Power Station Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20045H5381993-01-29029 January 1993 Procedure 8.7.3,Secondary Containment Leak Rate Test. BECO-91-148, Reactor Containment Bldg Integrated Leakage Rate Test Rept1991-08-0505 August 1991 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20076D4891991-07-22022 July 1991 Procedure 8.7.3, Secondary Containment Leak Rate Test, Containment Results of Leak Rate Tests Performed on 910505 & 0620 ML20204H3501988-09-26026 September 1988 Restart Readiness Assessment Rept for Pilgrim Nuclear Power Station BECO-88-049, Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test1987-12-31031 December 1987 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test ML20209D4721987-04-23023 April 1987 Secondary Containment Leak Rate Test Rept ML20236M1111987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1021987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1001987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M0911987-03-0404 March 1987 Smoke Density Test (Nbs) ML20236M1211987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1281987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M0811987-03-0404 March 1987 Smoke Density Test (Nbs) ML20112F8381985-01-0808 January 1985 Rev 15 to Secondary Containment Leak Rate Signoff ML20100F6031984-12-31031 December 1984 Reactor Containment Bldg Integrated Leakage Rate Test,Type A,B & C Periodic Test,Pilgrim Nuclear Power Station,Unit 1 ML20107A1861984-09-30030 September 1984 Rev 1 to Statistical Analysis of Boundary Strengths for Masonry Walls from Field Test Data ML20064B8921982-10-27027 October 1982 Mark I Containment Program:Plant-Unique Analysis Rept of Torus Suppression Chamber for Pilgrim Station - Unit 1 ML19331D1341980-08-18018 August 1980 Results of Startup Physics Testing Program Conducted for Cycle V Operation. ML19344B3271980-05-31031 May 1980 Primary Containment Integrated Leak Rate Test,Second Periodic Test & Local Leak Rate Tests Results,Jan-May,1980. ML19312E0011980-04-30030 April 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Power Generating Station, Final Rept for 790907 Testing ML19320C9891980-04-23023 April 1980 Secondary Containment Leak Rate Test Data.Includes Test Conditions,Base Reading & Standby Gas Treatment Sys a & B Performance ML19312D9971980-03-31031 March 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Generating Station, Final Rept for 790829 Testing ML19305D2591980-03-20020 March 1980 Secondary Containment Leak Rate Test Data. ML20126B3691980-03-0303 March 1980 Secondary Containment Leak Rate Test Data ML19312D9951980-01-31031 January 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Power Generating Station, for 790531 Testing ML20236Q8821976-11-0505 November 1976 Friction Coefficients of Water-Lubricated Stainless Steels for Spent Fuel Rack Facility 1995-09-01
[Table view] |
Text
. . . . . - .-_ - . _ _
,-- ATTACHMENT A SECONDARY CONTAINMENT LEAK RATE SIGNOFF A. Prerequisites (Step IV)
- 1. Match Engineer permission to perform test Initial J.G.
2 Turbine Bu11 ding, H&V System operating at J. .03 p on operating floor and 1 04" in ,
condenser compartment; two exhaust and two RM l-supply fan in service. Initial RM
- 3. DP-A-22 and DP-A-32 calibrated. Initial RM 1 4. At least one door at each access closed. Initial Standby gas treatment system operable. RKM per WF
- 5. Initial
- 6. All automatic ventilation system isolation dampers operable or secured in the isolated condition. Initial, RKM
- 7. All manometers filled and zeroed. Initial RKM
- 8. Secondary containment checkoff considered and accepted. ' Initial : RM Specific purpose for test performance. RM
- 9. Initial i
To verify secondary containment integrity prior to RF0 #7 fuel offload.
B. Test Performance i
j Nind Direction W .
Hind Velocity 9 mph .(11,5 mph) ,
l Barometric pressure 29.62 "Hg Outside Temperature 20 : .p Inside Temperature 70 7 1 1. Base Readings (Step 4)
Manometer P Rx Bldg El 91', ,
j N (1) +.14 "H0'
~
) E (2) +.10 "H0-M (3) 0 "H0 l S (4) +.16 " HiO a Average in " H 0 (0" 10 1" H 0) .
i l
! 8.7.3A-1 Rev. 18 8704290292 870423 PDH ADOCK 05000293 p PDR l
. - _ . . - . . . _ . _ . _ _ _ - _ _ - - - -_- __ _ .- -_-__-_ _.. -_. - _ _ , _ _ _ . . _ _ - _ - _ . _ _ ~ . _ . _ . . . , _ _
- Elevation 51' Turbine Building:
Turb op. floor .32 "H 0 Condenser Compt. .35 "H 0
- 2. SGTS "A" Performance Inner Truck Lock Door Open, Outer Door Shut.
Manometer Stabilization Time' 3 Min.
DP-A-22 .85 "H 0/ 2900 CFM DP-A-32 .In "H 0/ insn CFM Total nosn CFM f
FI-8126 4000 CFM 4
Standby fan reverse rotation yes no x Man 6 meter Stabilization Time 3 Min.
Elevation 91' Rx. 81da. manometer:
8ase - Test - Corrected
+ 14 .17 " H:0 .31 "N0 N (1) " Ha0 ,
+.10 .29 "H0
- l. E (2) "H0 19 " H:0 W (3) 0 "H0 .30 " H:0 .30 "H0 1 S (4) +.16 "H0 .14 "H0 .30 " H2O Average corrected manometer DP . 30 ' "H0 Elevation 51' Turb 81da manometers:
Turb op Floor .20 "H 0 Condenser Compt. .22 a y,o Net Change from 8ase Turb .12 "H0 I
4 Cond .13 "H0 I 3. SGTS "A" Performance Inner Truck Loe.k Door Shu't, Outer Door Open.
DP-A-22 .85 "H0 2900 CFM DP-A-32 .10 "H0 insn CFM Total nosn CFM ,
FI 8126 Annn CFM ,
Standby fan reverse rotation yes no x
" ~ '
8.7.3A-2 Rev. 18 e,- ,- - , -,.n,. -..._ - ._ . , . . ~ ~ , - , - . . . . , . ,.-,,._,,,,-,-.,,-,--.,,.,n. > ,-,----.-,_n-n,, , - , - - .,----,,,,n,,,,-- ...,--~,
Manometer Stabilization Time 3 Min.
Elevation 91' Rx Blda Manometers:
Base - Test - Corrected N (1) +.14 "H0 .19 "H0 .11 "H0
+.10 .20 "H0 .30 " H:0 E (2) " H:0 0 .32 "H0 .32 " H2O W (3) " H2O __
+.16 "H0 .16 "H0 .32 "H0 S (4)
Average corrected manometer DP .3175 " H2O l
- Elevation 51' Turb Blda manometers:
Turb op Floor .25 "H2O Condenser Compt. .25 "H 0 j Net Change from Base Turb _n7 " H2O .
Cond .10 "H0 4
- 4. SGTS "B" Performance Inner Truck Lock Door Shut, Outer Door Open.
~
DP-A-22 .075 "H 0 900 CFM j . DP-A-32 .80 "H:0 2800 CFM I Total 3700 CFM 4
FI 8127 4000 CFM X
Standby fan reverse rotation - yes - no Manometer Stab 1112ation Time 3 Min.
Elevation 91' Rx BIda. manometers:
Base - Test = Corrected M (1) +.14 "H0 .18 "H0 .32 "H0 E (2) +.10 "H0 '
.20 " Ha0 .30 "H0 N (3) 0 " H:0 _99 "H0 99 "H0 5 (4) +_1A "H0 _in "H0 _31 "H0 Average corrected manometer DP .2875 "H0 8.7.3A-3 Rev. 18
Elevation 51' Turb 81da Manometers:
! Turb op Floor .31 =H0 i
Condenser Compt. .31 "H0 i Net Change from Base Turb . 01 "N0 Cond .os "H0 I 5. SGTS "8" Performance Inner Truck Lock Door Open, Outer Door Shut.
DP-A-22 .075 "H0 900 CFM
]
DP-A-32 .85 "H0 2950 CFM Total 3850 CFM .
4 FI 8127 4000 CFM l
Sta'ndby fan reverse rotation .yes no x Manometer Stabilization Time a Min. ,
t ;
Elevation 91' Rx B1da Manometers:
)
1 i Base - Test - Corrected l
1- N (1) +.14 "H0 .16 ' "H0 . 30 ~" H:0 j ,
E (2) +.10 "H0 .17 "H0 . 27 " H:0 i N (3) 0 "H0 .26 "H0 .26 "H0 i
l S (4) +.16 "H0 .12 "H0* an "H0-4 Average corrected DP .2775 . ...
"H0 Elevation 51' Turb bida manometers: -
Turb op Floor .22 "
H0 Condenser Compt. .22 "
H0 ,
i Net Change from Base Turb .10 "H0 i
Cond . .13 - "H0
- 6. System Returned to Normal: (Two Independent Verifications Required) -
Richard r. i,:1ck/D. O' Leary Date 1/25/87 - -
l- Stephen C. Power Date 1/25/87 -
i ,
i i
8.7.3A-4 Rev. 18 i -
4 i
b e
A
, , , , - , - , , - , r c----- - , - - . -..._w,,,-- . -,----;---..,e_ . - - - . ~ . - . . - . . ,--,,,,.r.-,--_--.-.,,---w,i,...--.w_.--%-.-wy --~=-~.--,.---.--~-e,,
m-,,--y--
. Discrepancies:
l None RKM 1/25/87 Acceptance Criteria. as stated in Section VIII of the procedure was met.
Joe Giar 1/25/87 Signature on file.
Hatch Engineer Reviewed By Joe Giar Signature on file.
Watch Engineer .
Test data forwarded to Compliance Eng. by Watch Engineer .Date 1/25/87 7 Reporting Compliance Engineer submitted report to the NRC within 90 days.
P.F. Giardiello Signature on file. 4/23/87 Report Letter # 87-063 Compilance Engineer Date
- 8. Route to Control Room Annex for Filing.
i 8.7.3A-5 Rev. 18 1
L.. .)