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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M5961997-03-31031 March 1997 Proposed Tech Specs,Representing Changes to TS 2.1.2,action a.1.c for LCO 3.4.1.1 & Bases for TS 2.1 ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program ML20135E8101997-03-0303 March 1997 Proposed Tech Specs 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.2 Re Isolation Actuation Instrumentation & 3/4.3.3 Re Emergency Core Cooling Sys Actuation Instrumentation ML20134M0921997-02-11011 February 1997 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20134B5511997-01-24024 January 1997 Proposed Tech Specs 3.1.3.5 Re Control Rod Scram Accumulators ML20132F1791996-12-11011 December 1996 Revised Tech Specs Re Changes to TS Bases B 3/4.3.1, Reactor Protection Sys Instrumentation, & B 3/4.3.2, Isolation Actuation Instrumentation ML20135D6851996-12-0404 December 1996 Proposed Tech Specs 3.1.3.5, CR Scram Accumulators, for Improvement & Clarifies Statement of 961025 Initial Request ML20134F3831996-10-25025 October 1996 Proposed Tech Specs 3/4.3.1,3/4.3.2 & 3/4.3.3 Re Reactor Protection Sys Instrumentation,Isolation Actuation Instrumentation & Emergency Core Cooling Sys Actuation Instrumentation ML20134F4311996-10-25025 October 1996 Proposed Tech Specs 3.1.3.5 Control Rod Scram Accumulators ML18102A2561996-07-12012 July 1996 Proposed Tech Specs Re Qualifications of Operations Manager ML18101B3831996-05-22022 May 1996 Proposed Tech Specs,Requesting Approval of Changes to QA Program 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20216E6201999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206T8941999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9 ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20206G2281999-03-31031 March 1999 Rev 18 to ODCM for Hope Creek Generating Station ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20197H8511997-12-0808 December 1997 Rev 0 to IST Program Submittal Interval 2,Dec 21,1997 Through Dec 20,2006 ML20198J6431997-10-10010 October 1997 Rev 0 to 55-WP3/F43TB3-05, Weld Procedure ML20211M6121997-10-0707 October 1997 Cycle 4 Startup Physics Testing ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20198J6541997-08-20020 August 1997 Rev 3 to 55-PQ7001-03, Procedure Qualification Record ML20198J6501997-08-20020 August 1997 Rev 5 to WP3/F43TB3-05, Welding Procedure Specification ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program 1999-09-30
[Table view] |
Text
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ATTACHMENT 2
.HCGS LICENSE CHANGE REQUEST 89-05, NLR-N89100, ,
HYDROSTATIC APPENDIX;J TESTING'
' a The following Technical: Specifications have.
b e e n r e v i s e d t o . r e f l e c t -.:. t h e p r o p o s e d -.c h a n g e ::.
Technical Specification ~ Pace 3.6.1.2.e 3/4.'6-2land'. ,
'3/4'.6-3 3/4?6-4
~
4'.6.1.2.1 Table 3.6.3-1 3/4-6-42o
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[. ,
CONTAINMENT SYSTEMS' PRIMARY CONTAINMENT LEAKAGE -
d LIMITING CONDITION FOR OPERATION q
.)
3.6.1.2 Primary containment leakage rates shall be limited to:
- a. An overall integrated. leakage rate of less than or equal to La , 0.5 per-cent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 48 y p j, g
- b. A combined leakage rate of less than or equal to 0.60 L for all penetrationsandallvalveslistedinTable3.6.3-1,ex8eptformain I steam line isolation valves *, valves which form the boundary for the long-term seal of the feedwater lines, and other valves which are -
hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests when pressurized to P,, 48.1 psig. ]
- c. *Less than or equal to 46.0 scfh combined through all four main steam j lines when tested at 5 psig (seal system AP).
- d. A combined leakage rate of less than or equal to 10 gpm for; all con-tainment isolation valves which form the boundary for the long aterm seal of the feedwater lines in Table 3.6.3-1, when tested at 1.10 Pa, 52.9 psig.
gg ,
- e. , A combined leakage rate of less than or equal to 10 gpm for all other/
containment isolation valves in~hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment, when tested atgPa,
- 52. 9 = g psig ap. 1.10 APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.
ACTION:
With-
- a. The measured ov'erall integrated primary containment leakage rate exceeding 0.75 L, or
- b. The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation !
valves *, valves which form the boundary for the long-term seal of the feedwater lines, and other' valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests exceeding 0.60 La ' I
- c. The measured leakage rate exceeding 46.0 scfh combined through all four main steam lines, or
- d. The measured combined leakage rate for all c..,ntainment isolation valves which form the boundary for the long-term seal of the feedwater lines in Table 3.6.3-1 exceeding 10 gpm, or INSERT
- e. The measured combined leakage rate for all other/ containment isolation valves in hydrostatically tested lines in Table 3.6.3-1 which penetrate the primary containment exceeding 10 gpm, restore:
- a. Theoverallintegratedleakagerate(s)tolessthanorequalto0.75La'""!
HOPE CREEK 3/4 6-2
7 %L <
' CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continue'd)
' ACTION (Continued) -
- b. The combined leakage rate for all penetrations'and all valves listed. !
.in Table 3.6.3-1, except for main steam line isolation. valves *, valves ;
which form the boundary for the long-term seal; of. the feedwater. lines, and l other valves wh4b are hydrostatic.11y tested per Table 3.6.3-1, subject to Type 8 and C tests to.less than or equal to 0.60 L,, and 1
- c. The leakage rate t> less than or equal to 46.0 scfh combined through 1 all four main steam lines, and ;
- d. The combined leakage rate for all containment isolation valves which form .
.the boundary for the long-term seal of the feedwater lines in. Table 3.6.3 !
to less than or equal to 10 gps, and-
- e. The combined leakage rate for all other/ containment l isolation valves-in j hydrostatically tested lines in Table 3.6.3-1 which penetrate the >
primary. containment to less than or equal to 10 gpm,-
prior to increasing reactor coolant system temperature above 200'F. ,
J l
SURVEILLANCE REQUIRC4ENTS .
1 1
4.'.1.2 6 The primary containment leakage rates shall be. demonstrated at thei i following test schedule and shall be determined in conformance with the criteria.
specified in Appendix J of 10.CFR 50 using the methods and provisions of ANSI i N45.4 - 1972:
- a. 'Thre, Type A Overall Integrated Containment Leakage Rate tests'shall-be conducted at 40 + 10 month intervals during shutdown at P,,.
48.1 psig, during each 10 year service' period. 'The. third-test of.
each set shall be conducted during the shutdown for the 10 year plant-inservice. inspection. ' '
- b. If any periodic Type A test fails to meet 0.75,L,, the 'est~t schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L,, a Type A test shall be performed at least every 18 months until two consecutive Type A- tests: meet 0.75 L,, at which time the above test-schedule may be resumed,
- c. The accura:y of.each Type A test shall be verified Dy'a supplemental test which:
, .1. Confirms the accuracy of-the test by verifying that.the difference--
- between.the supplemental data and the Type A test data is within-0.25 L,.
- 2. Has' duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
- 3. ' Require's the quantity of gas injected into the containment'or ,
, bled from the' containment during the supplemental test to be,
~
between 0.75 L, and 1.25 L,.
HOPE CREEK , 3/4 6-3
- __N - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _
5 w 1
-]
I j
INSERT.'for Technical Specification 3.6.1.2.e, pages 3/4-6-2 & 6-3'-
{
" . .. penetrations and..." 1 4
o I i
1 1
1 I
i
, ~ , . .
.~ ..
t .:
. CONTAINMENT' SYSTEMS.
ERVEILLANCE REQUIREMENTS (Cor,tinued) '
.The formula to be used is: [L, + L,, .0.25 L,] s Lc Y El o *L am
+
0.25 L,] where L es supplement test result; L,s superimposed. leakage;
~
and L,a measured Type A-leakage..
d.
Type B and C tests shall be conductedw 'ith gas at P,, 48.1 psig*,
at intervals no ' greater'than 24 months ** except for tests involving: '
- 1. Air locks,
- 2. Main steam line isolation valves,- 1
- 3. Valves pressurized with fluid from a seal system, 4.
~
All containment isolation valves in hydrostatically't'sted lines e
in Table.3.6.3-1 which penetrate the primary containment, and j 4 5.. Purge supply and exhaust isolation valves with resilient material seals. -
- e. Air locks shall be tested and demonstrated OPERABLE per Surveillance'e Requirement 4.6.1.3.
'f.
Main per 18steam line isolation valves shall be~ leak tested at least once-months. I l
i
- g. 'i Containment isolation valves which form the boundary for the;1ong- -
i term seal of the feedwater lines in Table 3.6.3-1 shall be hydrostati- !
cally tested at 1.10 P,, 52.9 psig, at least once per 18 months. I
- h. All containment isolation valves in hydrostatically tested lines in
. Table 3.6.3-1 which penetrate the primary containment shall.be leak tested at least once per 18, months. i
- 1. a
' Purge supply and exhaust isolation valves with resilient material seals l shall be tested and demonstrated OPERABLE per. Surveillance.Regbirements 4.6.1.8.2.In d '.5.1.0.0.I ,
. % i j.
The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.c, 4.6.1'2.d. and 4.6.1.2.e.
s
- Unless a hydrostatic test is' required per Table 3.6.3-1.
C*A Type C test interval extension to the first refueling outage is permissible i
i for. primary containment isolation valves listed in-Table 3.6.3-1, which are i identified in Public Service Electric & Gas Company?s letter to~ the NRC-(letter No. NLR-N87047), dated April 3,1987, as needing a plant outage to i
test. ;For this one time test interval, tha' requirements of Section 4.0.2
.are not applicable.
i 1
j HOPE CREEK 3/4 6-4 Amen'dment No.4 l
TABLE 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES
~
NOTES NOTATION ~
- 1. Main Stear ' solation Valves are sealed with a' seal system that maintains a positive pressure.of 5 psig above reactor pressure. Leakage is in-leakage and is not added to 0.60 La allowable leakage.*
- 2. Containment Isolation Valves are sealed'with a water seal from the..'HPCI and/or RCIC system to. form the long-term seal boundary of.the feedwater; lines. . The valves are tested with water at 1.10 Pa, 52.9 psig, to ensure the' seal boundary will prevent by pass leakage. . Seal boundary l liquid leakage will be limited to 10 gpm.
~
- 3. ' Containment Isolation Valve, Type C gas test at Pa, 48.1 psig. Leakage.
added to 0.60La allowable leakage. -
( 1 10
- 4. Containment Isolation Valve, Type C water. test a Pa, 6 sig A P.-
Leakage added to 10 gpm allowable leakage. .
gy,q
- 5. Containment boundary is discharge nozzle of relief valve, leakage tested during Type A test.*
- 6. rywell and suppression chamber p~ressure and level instrument root valves and excess flow check valves, leakage tested during Type A.*
- 7. Explosive shear valves (SE-V021'through SE-V025) not Type C tested.*
- 8. Surveillance to be performed per Specification 3.6.1.8.
- 9. All valve I.D. numbers are preceded by a numeral I which represents an -
Unit 1 valve. !
- 10. The reactor vessel head seal leak detection.line (penetration J5C) excess flow check valve (BB-XV-3649) is not subject to OPERABILITY testing. This valve will not be exposed to primary system pressure except under the unlikely conditions of a seal failure where it could ;
be partially pressurized to reactor pressure. Any leakage path is ^
restricted at the source; therefore, this valve need not be ,
OPERABILITY tested. .
l' ,
HOPE CREEK 3/4 6-42
_ _ _ _ _ _ _ _ - _ _ _