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| | issue date = 03/28/1994 | | | issue date = 03/28/1994 |
| | title = Application for Amend to License DPR-75,requesting Change to Adds Footnote 21-24 BF-22 on TS 3.6.3,Table 3.6-1, Containment Isolation Valves. | | | title = Application for Amend to License DPR-75,requesting Change to Adds Footnote 21-24 BF-22 on TS 3.6.3,Table 3.6-1, Containment Isolation Valves. |
| | author name = HAGAN J J | | | author name = Hagan J |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 5 | | | page count = 5 |
| | | project = |
| | | stage = Request |
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| =Text= | | =Text= |
| {{#Wiki_filter:Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President | | {{#Wiki_filter:Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations MAR 281994 NLR-N94036 LCR 94-09 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: |
| -Nuclear Operations MAR 281994 NLR-N94036 LCR 94-09 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: | | LICENSE CHANGE REQUEST SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License DPR-75 for Salem Generating Station (SGS), Unit No. 2. Pursuant to the requirements of 10CFR50.90 (b) (1), a copy of this request has been sent to the State of New Jersey as indicated below * |
| LICENSE CHANGE REQUEST SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License DPR-75 for Salem Generating Station (SGS), Unit No. 2. Pursuant to the requirements of 10CFR50.90 (b) (1), a copy of this request has been sent to the State of New Jersey as indicated below * . The proposed change adds the # footnote to 21-24 BF22 on Technical Specification | | .The proposed change adds the # footnote to 21-24 BF22 on Technical Specification 3.6.3 Table 3.6-1 Containment Isolation Valves. |
| | Attachment A contains further discussion and justification for the proposed change. Attachment B contains a markup of the existing Unit 2 Technical Specifications to reflect the requested changes. |
| | PSE&G has reviewed the implementation requirements for the proposed amendment and requests a 60 day period from amendment approval to implementation. |
| | Should you have any questions on this transmittal, please contact us. |
| | Sincerely, |
| | ~\ |
| | 9404060042. 940328 *. |
| | PDR ADOCK 05000311 |
| | .P PDR |
|
| |
|
| ====3.6.3 Table====
| | MAR281994 Document Control Desk 2 NLR-N94036 c Mr. T. T. Martin, Administrator - Region I |
| 3.6-1 Containment Isolation Valves. Attachment A contains further discussion and justification for the proposed change. Attachment B contains a markup of the existing Unit 2 Technical Specifications to reflect the requested changes. PSE&G has reviewed the implementation requirements for the proposed amendment and requests a 60 day period from amendment approval to implementation.
| | : u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem |
| Should you have any questions on this transmittal, please contact us. -----------------9404060042.
| | : u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall (S09) |
| 940328 *. PDR ADOCK 05000311 .P PDR Sincerely, -......
| | USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 |
| Document Control Desk NLR-N94036 2 c Mr. T. T. Martin, Administrator | |
| -Region I u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 MAR281994 Mr. J. c. Stone, Licensing Project Manager -Salem u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 REF: NLR-N94 STATE OF NEW JERSEY SS. COUNTY OF SALEM J. J. Hagan, being duly sworn according to law deposes and says: I am Vice President | |
| -Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit No. 2, are true to the best of my knowledge, information and belief. Subscribed and Sworn to before me f.pA .*
| |
| o rT}jM1cA---4/1 ' 1994 .. * .
| |
| /!flmW!d 'N tary Jersey My Commission expires KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My CommhigR e*i;ires 21, 1990 PROPOSED LICENSE CHANGE SALEM GENERATING STATION UNIT NO. 2 ATTACHMENT A FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 I. Description of the Change LCR 94-09 This amendment request adds the # footnote to 21-24 BF22 on Technical Specification
| |
|
| |
|
| ====3.6.3 Table====
| | REF: NLR-N94 STATE OF NEW JERSEY SS. |
| 3.6-1 Containment Isolation Valves. II. Reason for the Proposed Change PSE&G forwarded License Change Request 91-04 on August 30, 1993. The proposed change replaced the main feedwater control and control bypass valves with the main feedwater stop check valves for the Containment Isolation.Function. | | COUNTY OF SALEM J. J. Hagan, being duly sworn according to law deposes and says: |
| This request was subsequently approved as Amendment 128. Our request neglected to include the # footnote for 21-24 BF22 (main feedwater stop check valves) on Table 3.6-1 Containment Isolation Valves. This note identifies those Containment Isolation valves that are not subject to Type .c leakage testing. The BF-22s are exempt from Type c leakage testing and should have been designated as such. III. Justification for the Proposed Change PWR main isolat:*ion | | I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit No. 2, are true to the best of my knowledge, information and belief. |
| * valves are exempt from Appendix J Type c leakage.testing. | | Subscribed and Sworn to before me |
| These valves connect to the steam generator and.are .not exposed, during normal or post-LOCA operations, to either the Containment atmosphere or the Reactor Coolant System. | | _'*--~his~ f.pA .* d_~y o rT}jM1cA-- ' 1994 |
| isolation is based on steam generator functional.requirements. | | -~ |
| The steam*generator and its connecting lines are a closed system inside Containment as defined by the NRC Standard Review Plan. LCR 91-04 did not include the # footnote when the BF-22s were added to Technical Specification Table 3.6-1. This was an oversight. | | .. * . ~,1,f -4/1 /!flmW!d |
| This footnote designates those valves exempt from Type C leakage testing. Salem UFSAR Table 6.2-13 lists those Containment Isolation Valves not subject to Type c leak rate testings. | | 'N tary Pubfc~New Jersey KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission expires My CommhigR e*i;ires A~ril 21, 1990 |
| The BF-22s are included in this list. Thus, the amended Technical Specifications are inconsistent with the Salem UFSAR. This amendment request will eliminate that inconsistency and correctly show that the BF-22s are exempt from Type c leakage testing. PSE&G considers this an editorial change. | | |
| *). IV. Significant Hazards Analysis Consideration The proposed Technical Specification change: 1. Does not involve a significant increase in the probability or consequence of an accident previously evaluated. | | ATTACHMENT A PROPOSED LICENSE CHANGE LCR 94-09 SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 I. Description of the Change This amendment request adds the # footnote to 21-24 BF22 on Technical Specification 3.6.3 Table 3.6-1 Containment Isolation Valves. |
| This change is editorial. | | II. Reason for the Proposed Change PSE&G forwarded License Change Request 91-04 on August 30, 1993. The proposed change replaced the main feedwater control and control bypass valves with the main feedwater stop check valves for the Containment Isolation.Function. |
| A previous amendment request neglected to designate the main f eedwater stop check valves as exempt from Type C leakage testing. That request was subsequently approved as Salem Unit 2 amendment 128. The amended Technical Specifications are now inconsistent with the Salem UFSAR, which correctly shows that these valves are exempt from Type C leakage testing. Valve functionality and operation are not affected by this change. Therefore, it may be concluded that the proposed change does not involve a significant increase in the | | This request was subsequently approved as Amendment 128. |
| * probability or consequences of an accident previously evaluated. | | Our request neglected to include the # footnote for 21-24 BF22 (main feedwater stop check valves) on Table 3.6-1 Containment Isolation Valves. This note identifies those Containment Isolation valves that are not subject to Type .c leakage testing. The BF-22s are exempt from Type c leakage testing and should have been designated as such. |
| | III. Justification for the Proposed Change PWR main .feedwat~r isolat:*ion |
| | * valves are exempt from Appendix J Type c leakage.testing. These valves connect to the steam generator and.are .not exposed, during normal or post-LOCA operations, to either the Containment atmosphere or the Reactor Coolant System. Valv~ isolation is based on steam generator functional.requirements. The steam*generator and its connecting lines are a closed system inside Containment as defined by the NRC Standard Review Plan. |
| | LCR 91-04 did not include the # footnote when the BF-22s were added to Technical Specification Table 3.6-1. This was an oversight. This footnote designates those valves exempt from Type C leakage testing. Salem UFSAR Table 6.2-13 lists those Containment Isolation Valves not subject to Type c leak rate testings. The BF-22s are included in this list. |
| | Thus, the amended Technical Specifications are inconsistent with the Salem UFSAR. This amendment request will eliminate that inconsistency and correctly show that the BF-22s are exempt from Type c leakage testing. PSE&G considers this an editorial change. |
| | |
| | *). |
| | IV. Significant Hazards Analysis Consideration The proposed Technical Specification change: |
| | : 1. Does not involve a significant increase in the probability or consequence of an accident previously evaluated. |
| | This change is editorial. A previous amendment request neglected to designate the main f eedwater stop check valves as exempt from Type C leakage testing. |
| | That request was subsequently approved as Salem Unit 2 amendment 128. The amended Technical Specifications are now inconsistent with the Salem UFSAR, which correctly shows that these valves are exempt from Type C leakage testing. Valve functionality and operation are not affected by this change. |
| | Therefore, it may be concluded that the proposed change does not involve a significant increase in the |
| | * probability or consequences of an accident previously evaluated. |
| : 2. Does not create the .possibility.of a new or different kind of accident from any accident previously evaluated.* | | : 2. Does not create the .possibility.of a new or different kind of accident from any accident previously evaluated.* |
| As stated above, the proposed change is editorial. | | As stated above, the proposed change is editorial. |
| It does not involve modifications to plant equipment or operation. | | It does not involve modifications to plant equipment or operation. Therefore, no new or different accident can be created by this change. |
| Therefore, no new or different accident can be created by this change. 3. Does not involve a significant reduction in a margin of safety. As. stated above, the proposed change is editorial. | | : 3. Does not involve a significant reduction in a margin of safety. |
| No modifications to plant equipment or operation are involved. | | As. stated above, the proposed change is editorial. |
| Feedwater system operation during normal and accident conditions remains the same. Therefore, this change does not result in a reduction in any margin of safety. v. Conclusions Based o.n the information presented | | No modifications to plant equipment or operation are involved. Feedwater system operation during normal and accident conditions remains the same. Therefore, this change does not result in a reduction in any margin of safety. |
| &hove, PSE&G has concluded that the proposed change satisfies the criteria for a no significant hazards consideration.}} | | : v. Conclusions Based o.n the information presented &hove, PSE&G has concluded that the proposed change satisfies the criteria for a no significant hazards consideration.}} |
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Application for Amends to Licenses DPR-70 & DPR-75,modifying TS for Containment Air Locks for Salem Units 1 & 2
ML18106A7911998-07-30030 July 1998
Application for Amends to Licenses DPR-70 & DPR-75,revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Following Phrase
ML18106A4271998-03-26026 March 1998
Application for Amend to License DPR-70,changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A4221998-03-26026 March 1998
Application for Amends to Licenses DPR-70 & DPR-75, Respectively,Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters.
ML18106A2521998-01-0808 January 1998
Supplemental Application for Amends to Licenses DPR-70 & DPR-75,respectively Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2111997-12-15015 December 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modifying Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1941997-12-11011 December 1997
Application for Amend to License DPR-70,requesting one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6771997-11-14014 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,providing TS Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6731997-11-14014 November 1997
Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
ML18102B6611997-11-0404 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.8.1 Re EDG & Deleting SR 4.8.1.1.2.d.1,calling for Diesels to Be Subjected to Insp Based on Vendor Recommendations
ML18102B6571997-11-0404 November 1997
Application for Amends to Licenses DPR-70 & DPR-75,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
ML18102B6371997-10-29029 October 1997
Application for Amend to License DPR-75,revising TS 3/4.4.6, Steam Generators, Making One Time Change to Unit 2 SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6411997-10-29029 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.8.1.1.2.d.2 Proposed in Util 960925 Submittal Re EDG Testing
ML18102B6471997-10-24024 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6441997-10-24024 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6291997-10-21021 October 1997
Application for Amends to Licenses DPR-70 & DPR-75,extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers in Closed Position
ML18102B6181997-10-14014 October 1997
Application for Amend to License DPR-70,modifying Pressure Isolation Valve Lco,Lco Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
ML18102B6061997-10-0606 October 1997
Application for Amend to License DPR-70,changing TS for LCOs 3.1.3.1, Movable Control Assemblies & 3.1.3.2.1, Position Indication Sys.
ML18102B5551997-08-27027 August 1997
Application for Amends to Licenses DPR-70 & DPR-75,providing Revised TS Bases Pages for TS 3.7.3, CCW Sys, to State That CCW Pumps Required to Be Operable to Meet LCO
ML18102B5281997-08-19019 August 1997
Application for Amend to License DPR-75,providing Addl Operational Flexibility to Allow Orderly Resumption of Startup & Preclude Unwarranted Power Transients at Plant Unit 2
ML18102B5321997-08-18018 August 1997
Application for Amend to License DPR-75,incorporating Plant Computer (P-250) Into TS Bases for Movable Control Assemblies
ML18102B4871997-08-0101 August 1997
Application for Amends to Licenses DPR-70 & DPR-75,rewording TS Section 4.2.1 to State That Util Will Adhere to Section 7 Incidental Take Statement Approved by Natl Marine Fisheries Svc
ML20148K0841997-06-0404 June 1997
Amends 194 & 177 to Licenses DPR-70 & DPR-75,respectively, Changing TSs 3.4.3 & 3.4.5, Relief Valves, to Ensure That Automatic Capability of PORVs to Relieve Pressure Is Maintained When Valves Are Isolated
ML18102B3041997-05-14014 May 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising SR 4.7.6.1.d.1 to Indicate That Specified Acceptable Filter Dp Is to Be Measured Across Filter Housing & to Reflecting Filter Dp Acceptance Value of Greater than 2.70 Wg
ML18102B2611997-05-0101 May 1997
Suppl Info to Util 970211 Application for Amends to Licenses DPR-70 & DPR-75,revising TS for Chilled Water Sys - Auxiliary Bldg Subsystem.Ref to Radiation Monitoring Signal Removed from Bases Section
ML18102B2581997-05-0101 May 1997
Application for Amend to License DPR-75,revising TS Section 3/4.7.7 to Reflect Extended Allowed Outage Times & Creating New TS Section 3/4.7.11 to Address Importance of Switchgear & Penetration Area Ventilation Sys
ML18102B0071997-04-30030 April 1997
Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger
ML18102B2511997-04-28028 April 1997
Submits Suppl to 970131 & 0314 Applications for Amends to Licenses DPR-70 & DPR-75,revising TS on Pressurizer Power Operated Relief Valves.Suppl Issued to State That Conclusion of NSHC Remains Valid
ML18102B0221997-04-25025 April 1997
Application for Amends to Licenses DPR-70 & DPR-75, Eliminating Flow Path from RHR Sys to RCS Hot Legs as Specified in LCO 3.5.2.c.2
ML18102A9791997-04-11011 April 1997
Application for Amends to Licenses DPR-70 & DPR-75, Increasing Cw Flow to 2550 Gpm for 31 Day Surveillance Fans Started & Operated in Low Speed
ML18102A8951997-03-0404 March 1997
Application for Amends to Licenses DPR-70 & DPR-75,modifying ECCS Surveillance Test Acceptance Criteria for Centrifugal Charging & SI Pumps
ML18102A8491997-02-11011 February 1997
Application for Amends to Licenses DPR-70 & DPR-75, Requesting Addition of New TS 3/4.7.10, Chilled Water Sys
ML18102A8361997-01-31031 January 1997
Application for Amends to Licenses DPR-70 & DPR-75,revising TS 3/4.4.3 to Ensure That Automatic Capability of Power Operated Relief Valve to Relieve Pressure Is Maintained When Valves Are Isolated by Closure of Block Valves
ML18102A8021997-01-31031 January 1997
Application for Amends to Licenses DPR-70 & DPR-75, Requesting Rev to TS Re Containment Systems Air Temp to Ensure Representative Average Air Temp Is Measured
ML18102A7861997-01-23023 January 1997
Application for Amend to License DPR-75,revising TS Bases 3/4.3.3.1 Re Radiation Monitoring Instrumentation Channel 2R41
1999-08-25
[Table view] |
Text
Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations MAR 281994 NLR-N94036 LCR 94-09 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
LICENSE CHANGE REQUEST SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating License DPR-75 for Salem Generating Station (SGS), Unit No. 2. Pursuant to the requirements of 10CFR50.90 (b) (1), a copy of this request has been sent to the State of New Jersey as indicated below *
.The proposed change adds the # footnote to 21-24 BF22 on Technical Specification 3.6.3 Table 3.6-1 Containment Isolation Valves.
Attachment A contains further discussion and justification for the proposed change. Attachment B contains a markup of the existing Unit 2 Technical Specifications to reflect the requested changes.
PSE&G has reviewed the implementation requirements for the proposed amendment and requests a 60 day period from amendment approval to implementation.
Should you have any questions on this transmittal, please contact us.
Sincerely,
~\
9404060042. 940328 *.
PDR ADOCK 05000311
.P PDR
MAR281994 Document Control Desk 2 NLR-N94036 c Mr. T. T. Martin, Administrator - Region I
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager - Salem
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
REF: NLR-N94 STATE OF NEW JERSEY SS.
COUNTY OF SALEM J. J. Hagan, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit No. 2, are true to the best of my knowledge, information and belief.
Subscribed and Sworn to before me
_'*--~his~ f.pA .* d_~y o rT}jM1cA-- ' 1994
-~
.. * . ~,1,f -4/1 /!flmW!d
'N tary Pubfc~New Jersey KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY My Commission expires My CommhigR e*i;ires A~ril 21, 1990
ATTACHMENT A PROPOSED LICENSE CHANGE LCR 94-09 SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 I. Description of the Change This amendment request adds the # footnote to 21-24 BF22 on Technical Specification 3.6.3 Table 3.6-1 Containment Isolation Valves.
II. Reason for the Proposed Change PSE&G forwarded License Change Request 91-04 on August 30, 1993. The proposed change replaced the main feedwater control and control bypass valves with the main feedwater stop check valves for the Containment Isolation.Function.
This request was subsequently approved as Amendment 128.
Our request neglected to include the # footnote for 21-24 BF22 (main feedwater stop check valves) on Table 3.6-1 Containment Isolation Valves. This note identifies those Containment Isolation valves that are not subject to Type .c leakage testing. The BF-22s are exempt from Type c leakage testing and should have been designated as such.
III. Justification for the Proposed Change PWR main .feedwat~r isolat:*ion
- valves are exempt from Appendix J Type c leakage.testing. These valves connect to the steam generator and.are .not exposed, during normal or post-LOCA operations, to either the Containment atmosphere or the Reactor Coolant System. Valv~ isolation is based on steam generator functional.requirements. The steam*generator and its connecting lines are a closed system inside Containment as defined by the NRC Standard Review Plan.
LCR 91-04 did not include the # footnote when the BF-22s were added to Technical Specification Table 3.6-1. This was an oversight. This footnote designates those valves exempt from Type C leakage testing. Salem UFSAR Table 6.2-13 lists those Containment Isolation Valves not subject to Type c leak rate testings. The BF-22s are included in this list.
Thus, the amended Technical Specifications are inconsistent with the Salem UFSAR. This amendment request will eliminate that inconsistency and correctly show that the BF-22s are exempt from Type c leakage testing. PSE&G considers this an editorial change.
IV. Significant Hazards Analysis Consideration The proposed Technical Specification change:
- 1. Does not involve a significant increase in the probability or consequence of an accident previously evaluated.
This change is editorial. A previous amendment request neglected to designate the main f eedwater stop check valves as exempt from Type C leakage testing.
That request was subsequently approved as Salem Unit 2 amendment 128. The amended Technical Specifications are now inconsistent with the Salem UFSAR, which correctly shows that these valves are exempt from Type C leakage testing. Valve functionality and operation are not affected by this change.
Therefore, it may be concluded that the proposed change does not involve a significant increase in the
- probability or consequences of an accident previously evaluated.
- 2. Does not create the .possibility.of a new or different kind of accident from any accident previously evaluated.*
As stated above, the proposed change is editorial.
It does not involve modifications to plant equipment or operation. Therefore, no new or different accident can be created by this change.
- 3. Does not involve a significant reduction in a margin of safety.
As. stated above, the proposed change is editorial.
No modifications to plant equipment or operation are involved. Feedwater system operation during normal and accident conditions remains the same. Therefore, this change does not result in a reduction in any margin of safety.
- v. Conclusions Based o.n the information presented &hove, PSE&G has concluded that the proposed change satisfies the criteria for a no significant hazards consideration.
