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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR ML18152B7551998-06-19019 June 1998 Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML18153A3481997-12-18018 December 1997 Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431 ML18153A1761997-11-0505 November 1997 Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers ML18153A3941997-11-0505 November 1997 Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel ML18153A5231997-04-24024 April 1997 Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling ML18153A6761995-11-20020 November 1995 Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing ML18153A7141995-07-20020 July 1995 Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6991995-07-14014 July 1995 Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation ML18153A8371995-06-0808 June 1995 Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license ML18153B2301995-02-14014 February 1995 Proposed Tech Specs Re App J Testing Requirements ML18153B2131995-01-24024 January 1995 Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1621994-11-29029 November 1994 Proposed Tech Specs Implementing Zirlo Fuel Cladding ML18153B1581994-11-22022 November 1994 Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1501994-11-10010 November 1994 Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0941994-10-11011 October 1994 Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers ML18152A5061994-09-0606 September 1994 Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities ML18152A1191994-08-30030 August 1994 Proposed Tech Specs to Accomodate Core Uprating ML18153B0061994-07-14014 July 1994 Proposed Tech Specs Changes Will Eliminate Remaining References to cycle-specific Parameters in Surry TS ML18152A1821994-06-0909 June 1994 Proposed TS Re Chemical & Vol Control Sys & Safety Injection Sys ML20065P6111994-04-19019 April 1994 Proposed Tech Specs,Modifying Control Rod Movement Surveillance Frequency ML18153A8821994-02-25025 February 1994 Proposed Tech Specs Modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys ML18153B4321993-12-27027 December 1993 Proposed Tech Specs Reflecting Revised Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML18153B4081993-12-10010 December 1993 Proposed Tech Specs,Establishing Upper Limit on Allowable COLR Mtc Values ML18153B4021993-12-10010 December 1993 Proposed Tech Specs,Modifying Surveillance Frequency of Auxiliary Feedwater Sys Pumps from Monthly to Quarterly Per Generic Ltr 93-05 & NUREG-1431 ML18153B4051993-12-10010 December 1993 Proposed Tech Specs,Updating Augmented Insp Program for Sensitized Stainless Steel by Incorporating Newer Code Requirements,While Maintaining Augmented Insp Philosophy ML18153B3751993-11-15015 November 1993 Proposed Tech Specs Implementing Revised 10CFR20,revising Frequency Radiological Release Repts from Semiannual to Annual & Clarifying Site Maps ML18153B3501993-10-19019 October 1993 Proposed Tech Specs for RSHX Svc Water Outlet Radiation Monitors ML18153B3321993-09-29029 September 1993 Proposed Tech Specs Modifying Required Insp Frequency of Low Pressure Turbine Blades to Permit Blade Insp to Be Performed Concurrent W/Disk & Hub Insp ML18152A0481993-07-20020 July 1993 Proposed Tech Specs Deleting Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3921993-07-16016 July 1993 Proposed Tech Specs for Operation W/Three Degree Increase in Svc Water Temp Limit for Containment Air Partial Pressures of 9.1,9.2 & 9.35 Psia ML18152A0461993-07-16016 July 1993 Proposed Tech Specs Implementing Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from semi-annual to Annual,& Clarify Site Maps ML18152A4511993-07-0202 July 1993 Proposed Tech Specs to Include COLR Which Presents reload- Specific Limits for Key Core Operating Parameters ML18153D3811993-07-0202 July 1993 Proposed TS Table 4.2-1 Re Miscellaneous Insps & Sensitized Stainless Steel Exams ML18153D3331993-05-0606 May 1993 Proposed Tech Specs Supporting Operation of Unit 2 w/100 Psi Reduction in RCS Nominal Operating Pressure Through End of Operating Cycle 12 1999-08-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18151A6641999-08-0606 August 1999 Rev 0 to Surry Unit 2 Cycle 16 Startup Physics Tests Rept. ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18151A5511999-02-10010 February 1999 to NE-1187, Surry Unit 1,Cycle 16 Startup Physics Tests Rept. ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18152B7551998-06-19019 June 1998 Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML20249B9911998-05-0606 May 1998 Analysis of Capsule X Virginia Power Surry Unit 1 Reactor Vessel Matl Surveillance Program. W/Evaluation of Surry Unit 1 Surveillance Capsule X Results & Response to NRC RAI Re GL 92-01,rev 1,suppl 1 ML18151A1931998-05-0404 May 1998 Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program. ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20199B0711998-01-0505 January 1998 Rev 0 to NE-1148, Surry Unit 2,Cycle 15 Startup Physics Test Rept ML18153A3481997-12-18018 December 1997 Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431 ML18150A4661997-12-16016 December 1997 ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2 ML18153A3941997-11-0505 November 1997 Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel ML18153A1761997-11-0505 November 1997 Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers ML18150A4641997-10-27027 October 1997 Risk-Informed ISI (RI-ISI) Pilot Program Submittal. ML18151A3911997-10-16016 October 1997 Rev 8 to VPAP-2103, Odcm. ML18151A7231997-08-0707 August 1997 Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products. ML20210J5031997-07-31031 July 1997 Rev 0 to NE-1132, Surry Unit 1,Cycle 15 Startup Physics Tests Rept ML18150A4441997-06-0909 June 1997 Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003. ML18153A5231997-04-24024 April 1997 Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18151A9761996-08-13013 August 1996 Cycle 14 Startup Physics Test Rept. W/960830 Ltr ML20134J9861996-07-30030 July 1996 /Unit 2 Fuel Assembly Insp Program ML18152A4701996-06-13013 June 1996 Cycle 13 Control Rod Performance Test Results. ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling ML18152A0571995-12-20020 December 1995 Startup Physics Test Rept,Surry Unit 1,Cycle 14. W/960111 Ltr ML18153A6761995-11-20020 November 1995 Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing ML18151A6421995-08-0101 August 1995 Change 3 to Rev 0 to Third Interval IST Program ML18153A7141995-07-20020 July 1995 Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6991995-07-14014 July 1995 Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation ML18153A8371995-06-0808 June 1995 Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license ML20083C9951995-05-0808 May 1995 Rev 0 to Surry Unit 2,Cycle 13 Startup Physics Tests Rept ML18153B2301995-02-14014 February 1995 Proposed Tech Specs Re App J Testing Requirements ML18153B2131995-01-24024 January 1995 Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1621994-11-29029 November 1994 Proposed Tech Specs Implementing Zirlo Fuel Cladding ML18153B1581994-11-22022 November 1994 Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1501994-11-10010 November 1994 Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0941994-10-11011 October 1994 Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers ML18152A5061994-09-0606 September 1994 Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities ML18152A1191994-08-30030 August 1994 Proposed Tech Specs to Accomodate Core Uprating 1999-08-06
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l e e ATTACHMENT 1 Proposed Technical Specification Change 8501100202 850104 P DR ADOCK 05000281 P PDR
TS 4.17-2 No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period*
0 18 months +/- 25%
1 12 months +/- 25%
2 6 months +/- 25%
3,4 124 days +/- 25%
5,6,7 62 days +/- 25% II
\
8 or more 31 days +/- 25%
- 2. The snubbers may be categorized int*o two groups: Those access-ible and those inaccessible during reactor operation. Each group may be inspected independently in* accordance with the above schedule.
B. Visual Inspection Acceptance Criteria
- 1. Visual inspections shall verify:
- a. That there are no visible indications of damage or impaired operability,
- b. Attachments to the foundation or supporting structure are secure, and
- c. In those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
- The inspection interval shall not be lengthened more than one step at a time.
II The current inspection period for Unit 2 may be extended to the 1985 refuel-ing outage.
I
-< .-: ? 's - ~..
ATTACHMENT 2 Discussion of Proposed Changes
e e DISCUSSION OF PROPOSED CHANGES BACKGROUND Technic.~l Spec:l,fication "4i'l7 ,A :§pedf-i.es the visual inspection interval for_
shock ]!uppressors (snul>b;rs). *;'. Th~ *. interval specification serves as an~
admini~rative control tc{ assu1:e t:nat, snubbers are periodically inspected?
based on performance. Specification 4.17.B specifies the acceptance criteria for the visual inspections. Based on inspection results during the last visual snubber inspection, conducted November 9-17, 1984, at Surry Power Station Unit No, 2, the next inspection interval was determined to be 62 days
+/- 25 percent, or no later than February 1, 1985.
Because inspection of all snubbers sufficient to satisfy the criteria in Specification 4.17.B cannot be conducted at power, Unit 2 must be shutdown for approximately ten days in late January, 1985, to conduct the required inspection. However, a major refueling and ten-year !SI inspection outage is scheduled to begin shortly thereafter on or about March 22, 1985. During this refueling/IS I outage, visual and functional testing of the snubbers, asF' required by Technical Specification 4.17.C, is scheduled to be performed.
Because the refueling/IS! outage will be conducted only a short time after the currently scheduled visual inspection, a one-time change to the Technical Specifications to defer the January visual inspection appears warranted. The change would extend the interval in Specification 4.17.A to permit conducting the visual inspection during the March, 1985 refueling outage. In addition, the deferral would minimize the additional exposure incurred by eliminating duplicate inspection efforts.
EVALUATION The purpose of the visual inspection requirement is to insure that no observable deficiencies exist with any snubber installation that would render a snubber inoperable. During the November, 1984 outage, seven snubbers were declared inoperable due to low fluid levels in the snubber reservoirs. Of the seven, three were in individual installations, while the remaining four were all connected to a common reservoir. .No other type of visual failure was discovered and the seven snubbers were repaired or replaced.
Current visual inspection criteria assure: a) that there are no visual indications of damage or impaired operabili'ty; b) attachments to the foundation or supporting structure are secure; and c) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Criterion "a" is verified during visual inspections by observing reservoir fluid level.
Adequate fluid level indicates lack of leakage. Historically, the majority of failures identified as a result of visual inspections are related to fluid level. Only rarely has a snubber been declared inoperable due to a mounting deficiency, which is the concern addressed by Criteria "b" and "c".
I **
In addition, in early 1984, Surry upgraded its snubber program. This upgrade has been demonstrated effective. During the recent Surry Unit 1 refueling out~g~, functional testing i;esulted in. only about one-fifth of the failures wh1c1i 0 had occurred during functional testing prior to the upgrade. This upgrade was also implemented in early 1984 for Unit 2 and provides additional assurance that the snubbers will perform their safety function if required.
This approach not only maintains. the required level of assurance that the snubbers are operable, but also significantly reduces the incurred dose since substantial scaffolding, climbing, and shielding will not be employed. If the January inspection was performed, the dose would be doubled since the same inspection must effectively be performed at the refueling outage a short time later.
50.59 and SIGNIFICANT HAZARDS REVIEW Pursuant to 10 CFR 50 ;59, we have reviewed the proposed Technical Specification changes .and have concluded that no unreviewed safety question exists: (i) the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report is not increased. Extending the inspection interval is an administrative action. In addition, the recent snubber program upgrade serves to reduce the likelihood of these events; (ii) the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report is not created. The proposed change affects inspection scheduling only and has no impact on any accident analysis; (iii) the margin of safety as defined in the basis for any Technical Specification is not reduced. The change in the inspection interval does not affect the capability of the snubbers to perform their function. Rather, due to the recent upgrade in the Surry snubber program, the margin of safety has increased.
In a similar manner, the proposed change has been reviewed and we have concluded that no significant hazards considerations exist. The
- proposed change is similar to Example (iii) of the examples specified in the Federal Register, 48 FR 14870, which lists examples of amendments likely to involve significant hazards considerations. Example (iii) involves a significant relaxation of a limiting condition for operation not accompanied by compensatory changes, conditions or actions that maintain a commensurate level of safety. It could be argued that the surveillance requirement is being relaxed. However, unlike the example, a commensurate level of safety is being maintained through the recent program upgrade. In addition, the nature of the specification is administrative; it specifies inspection frequencies based on past results to assure periodic inspections. Thus, because the change is administrative, it is also similar to Example (i) of the examples of amendments that are considered not likely to involve a significant hazards consideration.
t ,.
CONCLUSION In order to m-inim.ize duplication and reduce unnecesary personnel exposure, Vepco proposes,~ to amend the Technical Specifications to extend the* current snubber visual inspection interval from January, 1985, to the March, 1985, refueling outage. Because the specified intervals are primarily an administrative control to assure periodic snubber inspection, and because of Surry's recent snubber program upgrade, the one-time extension would have no adverse impact on plant safety.
ATTACHMENT 3 Basis For Exigent Request
t '
e BASIS FOR EXIGENT REQUEST 10 CFR 50.~l(a) (6) provides for handling proposed amendment requests where exigent circumstances exist and time does not permit the NRC to publish a Federal Register notice allowing thirty days for prior public comment. One subsection, paragraph (iv), requires the licensee to provide a reason for the exigency and why the licensee cannot avoid it. Where the NRC determines that the licensee has failed to use its best efforts to make a timely application in order to create the exigency and to take advantage of this procedure, the NRC will use its routine public notice and comment procedures.
The proposed change to the snubber surveillance requirement originated as a result of a previous snubber surveillance conducted November 9-17, 1984. As a result of that inspection, which consisted of a visual inspection of all snubbers, seven snubbers were declared inoperable.
In hindsight, what would appear now as an obvious consequence, i.e., that the next inspection interval would nearly coincide with the 1985 refueling outage and result in duplicate inspection efforts and unnecessary personnel exposure, was simply not immediately obvious following the inspection. Rather, the focus in late November and early December was on the detailed examination of the snubbers' failure mechanism and its implications.
When the implications of the November results were realized,* an effort was conducted to identify and consider alternatives. The effort was hampered by the unavailability of key personnel during the holiday season. Nonetheless, the various alternatives, including performing engineering analyses and alternative inspection methodologies, were considered and rejected. The only reasonable alternative to mitigate the adverse impact of the required February inspection was the amendment process. Once management approval was given to proceed in this fashion, the required reviews and concurrences-were conducted and obtained on a priority basis.
There has never been any intent by Vepco to create and take advantage of an exigent situation. On the contrary, we, too, would prefer to handle the proposed change in a routine manner. Also, we are unaware of any advantage to be gained by this approach. However, we are convinced that the proposed Technical Specification change is warranted and cannot be avoided if we are to maintain personnel exposures as low as reasonably achievable. The schedular deferral to achieve this fifty days is reasonable. The action is administrative in nature. Therefore, we request that the Commission process the proposed amendment on an exigent basis.