Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means 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 ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 ML18102B6081997-10-0606 October 1997 Proposed Tech Specs Revising LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys. ML18102B5571997-08-27027 August 1997 Proposed Tech Specs,Providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, Which States That Three CCW Pumps Required to Meet LCO ML18102B5301997-08-19019 August 1997 Proposed Tech Specs,Providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Salem Unit 2 ML18102B5341997-08-18018 August 1997 Proposed Tech Specs,Incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies ML18102B4891997-08-0101 August 1997 Proposed Tech Specs Section 4.2.1 Rewording Section to State Util Will Adhere to Section 7,Incidental Take Statement Approved by Natl Maring Fisheries Svc ML18102B3911997-06-12012 June 1997 Proposed Tech Specs,Representing Addition of New Spec 3/4.7.10, Chilled Water Sys - Auxiliary Bldg Subsystem. ML18102B3061997-05-14014 May 1997 Proposed Tech Specs,Revising SR 4.7.6.1.d.1,to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & Reflecting Filter Dp Acceptance Value Greater than 2.70 Water Gauge ML18102B2631997-05-0101 May 1997 Proposed Tech Specs,Adding New Spec 3/4.7.10, Chilled Water Sys - Auxiliary Bldg Subsystem. ML18102B2601997-05-0101 May 1997 Proposed Tech Specs 3/4.7.7 Revising Certain Allowed Outage Times & Creating 3/4.7.11 to Address Switchgear & Penetration Area Ventilation Sys ML18102B0341997-04-25025 April 1997 Proposed Tech Specs 3.5.2 Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2 1999-08-25
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9 ML20211Q8771999-08-27027 August 1999 Rev 0 to Inservice Testing Manual for Pumps & Valves Program ML18107A5171999-08-25025 August 1999 Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2 ML18107A5121999-08-23023 August 1999 Procedure 71151, Performance Indicator Verification. ML18107A5091999-08-23023 August 1999 Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability. ML18107A4961999-08-23023 August 1999 Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. ML18107A4671999-07-29029 July 1999 Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements ML18107A4601999-07-23023 July 1999 Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown ML18107A4241999-07-0202 July 1999 Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR ML18107A3811999-06-10010 June 1999 Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means 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 ML18107A2961999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9 ML18107A2131999-04-14014 April 1999 Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431 ML18106B1591999-03-31031 March 1999 Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918 ML18106B0801999-02-22022 February 1999 Proposed Tech Specs Re CR Emergency Air Conditioning Sys ML18106B0641999-02-0808 February 1999 Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing ML18106B0611999-02-0808 February 1999 Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions. ML18106B0531999-02-0202 February 1999 Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel ML18106B0431999-01-19019 January 1999 Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys ML18106B0241999-01-15015 January 1999 Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1 ML18106A9231998-10-12012 October 1998 Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03 ML18106A9181998-10-12012 October 1998 Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10 ML18106A8941998-09-29029 September 1998 Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch ML18106A8781998-09-17017 September 1998 Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity ML18106A8371998-08-12012 August 1998 Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door ML18106A7931998-07-30030 July 1998 Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase ML18106A6961998-07-0707 July 1998 Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan ML18106A6631998-06-17017 June 1998 Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements 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 ML18106A5571998-04-16016 April 1998 Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents ML20239A1251998-03-31031 March 1998 Rev 11 to Salem Nuclear Generating Station Odcm ML18106A4241998-03-26026 March 1998 Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters. ML18106A4291998-03-26026 March 1998 Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2 ML18106A3921998-03-13013 March 1998 Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency. ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML18106A3221998-02-18018 February 1998 Marked-up TS Pages for Section 4.2.1 of App B ML18106A3091998-02-0202 February 1998 Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation ML18106A2541998-01-0808 January 1998 Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page ML18106A2141997-12-15015 December 1997 Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18106A1961997-12-11011 December 1997 Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4 ML18102B6791997-11-14014 November 1997 Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels ML18102B6751997-11-14014 November 1997 Proposed Tech Specs Re Administrative & Editorial Corrections ML18102B6591997-11-0404 November 1997 Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid ML18102B6631997-11-0404 November 1997 Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown ML18102B6431997-10-29029 October 1997 Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing ML18102B6391997-10-29029 October 1997 Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10 ML18102B6491997-10-24024 October 1997 Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases ML18102B6461997-10-24024 October 1997 Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1 ML18102B6321997-10-21021 October 1997 Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position ML18102B6201997-10-14014 October 1997 Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2 1999-09-10
[Table view] |
Text
Document, Control LR-N96071
'Attachment 3 LCR S96-04 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS INCORPORATION OF 10CFR50 APPENDIX J OPTION B TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications are affected by this requested amendment:
Facility Operating License No. DPR-70 (Unit 1)
Technical Specification Page 4.6.1.2 3/4 6-2 4.6.1.2.b-e 3/4 6-3 4.6.1.2.f 3/4 6-4 4.6.1.6.1 3/4 6-8 Facility Operating License No. DPR-75 (Unit 2)
Technical Specification Page 4.6.1.2 3/4 6-2
- 4. 6 .1. 2. b-g 3/4 6-3 4.6.1.6.1 3/4 6-8 9604290189 960422 PDR ADOCK 05000272 ~.,
P PDR *1 .
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION
==================================================================
3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of s La, 0.10 percent 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 design pressure, (47.0 psig).
- b. A combined leakage rate of s 0.60 La for all penetrations and valves subject to Type Band C tests as identified in Table 3.6-1, when pressurized to Pa.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant system temperature above 200°F.
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4.6.1.2 The containment leakage rates shall be demonstrated at the following est schedule and shal e etermined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 +/- 10 month intervals during shut~otom at design pressure (47.0 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.
- The second inservice Integrated Leak Rate Test shall be performed at the fifth refueling outage, but no later than May, 1984.
SALi::M - UNIT 1 3/4 6-2 Amendment No. 171
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. If any periodic Type A test fails to meet .75 L , the test schedule for subsequent Type A tests shall be r~viewed and approved by the Commission. If two consecutive Type A tests fail to meet .75 L , a Type A test shall be performed at least every 18 months un~il two consecutive Type A tests meet .75 L at which time the above test schedule may be resumed. a
- c. The accuracy of each Type A test shall be verified by a supple-mental test which:
- l. Cor1firtrr.: the c;.ccuracy of tre Type A test by verifying that the differ*ence between supplemE:!ntal and Type A test data is within 0.25 La.
- 2. Has a (;tir*ci."i:ion <;pffir.ic1*.t tr' f'Stfl!*li.sh ri.ccurately the change in le;;ka~r* :.ci.\*!r.:r.n u*1c:: Typ"."* A tw:*L. c-nd the supple-men ta 1 test. .
- 3. Requires the quantity of g~s injected intQ the containment or bled from the conto.in;*,;,"'.t1t during the supr1ementai test to be equivalent to at l~ast 25 percent of the total j measured le2kage rate at dPs~gn pressure (47.0 psig).
a.I* Type 8 and C test~ s:*!::i*i be conc!uC.ed v i 1)1 gas at design pressure 1
(47.0 psig) at intervals no greater than 24 months except for tests involving air locks.
Air locks shQll be testE:!d and demonstrated OPERABLE per Surveillance RE!quirernent 4.6. l. 3.
SALEM - UN IT l 3/4 6-3
CONT.A.INMENT SYSTEMS SU RV EI LLANCE REou*r REMENTS (Continued)
All test leakage rates sha11 be calculated using obser*l"ed ~
converted*~o absolute values, Error analyses shall be per- /
fonned to select a balanced integrated leakage measurement system.
\ )
I J/ SALEM - UNfT l 3/4 6-4
e CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION J.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.~.
APPLICABILITY: MODES 1, 2,. 3 and 4.
ACTION:
With the *tructural integrity of the containment not conforming to.the above requirement*, re*tor* the structural integrity to within the limits prior to increa*ing the Reactor Coolant System temperature above 200°F.
SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Surfaces The structural integrity of the exposed
-acces*ibl* interior and exterior *urfac** of the containment, including the liner plate, *hall be determined d~*isg th* *INedewn !e~ eaea 'l'ype A*
eeneainmene l*.-..9* EAC* te*t (reference SpecLfLcacLan 4.6 1.~) by a visual in*pection of th*** *urfac*** This in*pection *hall be performed prior to the Type A containment leakage rate test~o v~ify no apparent changes in appearance or other abnormal degradation. ('L~~fl'ltf ~,y.,c.A.""'\\'1>"( '\*IP*\*"2.)
Repo;t*- Any abnormal degradation of the containment structure detected during th* above required inspection* *hall b* evaluated for reportability pur*uant to 10CFRS0.72 and 10CFRS0.73. Th* evaluation shall be documented and shall include a description of the condition of the concrete, th* inapection procedure, th* tolerance* on cracking, and the corrective action taken.
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SALEM - UNIT l 3/4 6-8 Amendment :*::
CONTAINMENT e?TEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage ~ates shall be limited to:
- a. An overall integrated leakage rate of less than Qr equal to La, 0.10 percent 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 design pressure (47.0 psig).
- b. A combined leakage rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to Pa.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than or equal to 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La prior to increasing the Reactor Coolant System temperature above 200°F.
SURVEILLANCE REQUIREMENTS The containment leakage rates shall be demonstrated at the following est schedule an s a e eterm1ne n con ormance with the criteria specified in Appendix J of 10 CFR SO using the methods and provisions of ANSI N45.4-1972:
- a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 +/- 10 month intervals* during shutdown at design pressure (47.0 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.
- The test interval for conducting a Type A test shall be extended from 40 +/- 10 months to allow the third Type A test, within the first 10-year service period, to be completed during the 10-year plant in-service inspection outage (6th refueling outage). This extension expires upon completion of the 6th refueling outage.
~'~ IDC'FR..5'D1'::>-"-/(o) ,41 A[~::;.-,-
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. If any periodic Type A test fails to meet .75 L, the test schedule for subsequent Type A tests shall be reviewed aRd approved by the Commission. If two consecutive Type A tests fail to meet .75 La, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet .75 La at which time the above test schedule may be resumed.
- c. The accuracy of each Type A test shall be verified by a supplemental test which:
- 1. Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La.
- 2. Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at design presS'Ure (47.0 psig).
Type B and C tests shall be conducted with gas at design pressure (47.0 psig) at intervals no greater than 24 months except for tests involving air locks.
11 Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6. 1.3.
- f. All test leakage rates shall be calculated using observ8~ :ata converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement system.
- g. The provisions of Specification 4.0.2 are not applicable.
SALEM - UNIT 2 3/4 6-3
~NTAXNMENT SYSTEMS CONTAINMENT SIRUCTURAI. INTEGRITY LIMITING CONDITIONS FOR OPERATION
- a*************************************
3.6.l.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILITY: HODES 1, 2, 3 and 4.
ACTION:
With the structural integrity of the containment not conforming to the above requirement*, restore the structural integrity to within the limit* within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hour* and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.6.1 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined dYEiRg ~he ah~~dewn fer each ~ype A aeR~aiRIReR~ leakage ra~e ~es~ (refereftee Speeifica~ion 4.6.1.2) by a visual inspection of these surfaces. This inspection shall be performed prior to the Type A containment l_eakage rate test1Co verify no apparent changes in appearance or other abnormal degradation. (~~'Y~tl-tlit-f.. ~fCC.\~,'c...~::-r10 ...I 'f,j.,\,2.)
Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFRS0.72 and 10CFRS0.73. The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective action taken.
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SALEM - UNIT 2 3/4 6-8 Amendment No. 112