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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program ML17355A3221999-05-0505 May 1999 Safety Evaluation Supporting Amends 200 & 194 to Licenses DPR-31 & DPR-41,respectively ML17355A3291999-05-0505 May 1999 Revised SE Supporting Evaluation for Certain Fire Zones in Tubine Building at Plant,Units 3 & 4 & Granting Licensee Request for Exemption from Technical Requirements of Section III.G.2a ML17355A2791999-03-26026 March 1999 Safety Evaluation Concluding That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 for Plants ML17355A2161999-02-0303 February 1999 Safety Evaluation Supporting Amends 199 & 193 to Licenses DPR-31 & DPR-41,respectively ML17354B1021998-09-14014 September 1998 Correction to SER Page 5 of SE & Page 6 of Ineel Technical Ltr Rept to Reflect Change of Word Then with Also, Submitted on 980817 in Response to Util 980409 Request Relief from Certain Requirements of ASME Code,Section XI ML17354B0901998-08-17017 August 1998 SER Accepting Revised Requests for Relief Numbers 11 & 18 for Turkey Point,Units 3 & 4 ML17354B0541998-07-16016 July 1998 SER Accepting Alternative Proposed by Licensee in That Revising FSAR 6 Months After Refueling Outages for Each Unit Not Necessary to Achieve Underlying Purpose of Rule (10CFR50.71(e)(4)) ML17354B0421998-07-0909 July 1998 Safety Evaluation Supporting Amends 198 & 192 to Licenses DPR-31 & DPR-41,respectively ML17354A9651998-06-0909 June 1998 Safety Evaluation Supporting Amends 197 & 191 to Licenses DPR-31 & DPR-41,respectively ML17354A9351998-05-12012 May 1998 Safety Evaluation Supporting Amends 196 & 190 to Licenses DPR-31 & DPR-41,respectively ML17354A7541997-12-20020 December 1997 Safety Evaluation Supporting Amends 195 & 189 to Licenses DPR-31 & DPR-41,respectively ML17354A7451997-12-15015 December 1997 Safety Evaluation Denying 970429 Request to Revise FPL Topical QA Rept (Fpltqar 1-76A).Concludes Proposed Rev Does Not Adequately Satisfy Regulatory Requirement to Clearly Delineate in Writing Functional Responsibilities ML17354A7351997-11-12012 November 1997 Errata to Safety Evaluation Re GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Page Was Inadvertently Omitted from 971112 SER ML17354A7201997-11-12012 November 1997 Safety Evaluation Accepting Completion of Licensing Action for GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves, for Plant ML17354A7091997-10-27027 October 1997 Safety Evaluation Supporting Amends 194 & 188 to Licenses DPR-31 & DPR-41,respectively ML17354A6921997-10-20020 October 1997 Safety Evaluation Re Use of Safety Injection Pumps for Use as Safe Shutdown Equipment Under App R for Turkey Point Units 3 & 4 ML17354A6711997-09-29029 September 1997 SE Accepting Licensee 970924 Request for Relief from ASME Code,Section Xi,Requirements Requesting Removal of All Bolting from 4B Reactor Coolant Pump ML17354A4431997-03-26026 March 1997 Safety Evaluation Accepting Licensee Proposed Alternative Re Code Case N-533 ML17354A4091997-02-11011 February 1997 Safety Evaluation Supporting Amends 193 & 187 to Licenses DPR-31 & DPR-41,respectively ML17354A3591996-12-0404 December 1996 Safety Evaluation Supporting Relief Requests 14 & 15 of Licenses DPR 31 & 41,respectively.Relief Request 17 Denied ML17354A3031996-10-22022 October 1996 Safety Evaluation Accepting Revised Relief Requests PR-4 & PR-5 ML17354A3041996-10-22022 October 1996 Supplemental Safety Evaluation Re Audit on 951205-08 & GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Ors,Usi A-46 ML17353A9171996-10-0404 October 1996 Safety Evaluation Supporting Amends 192 & 186 to Licenses DPR-31 & DPR-41,respectively ML17353A9071996-09-26026 September 1996 Safety Evaluation Supporting Amends 191 & 185 to Licenses DPR-31 & DPR-41,respectively ML20136F1411996-09-19019 September 1996 Supplemental Safety Evaluation Denying Separate Insp at Plant,Unit 1,based on Results of Plant,Units 3 & 4 Insps ML17353A8541996-08-13013 August 1996 Safety Evaluation Supporting Amends 190 & 184 to Licenses DPR-31 & DPR-41,respectively ML17353A8401996-08-0606 August 1996 Safety Evaluation Supporting Amends 189 & 183 to Licenses DPR-31 & DPR-41,respectively ML17353A8181996-07-22022 July 1996 Safety Evaluation Supporting Amends 187 & 181 to Licenses DPR-31 & DPR-41,respectively ML17353A7911996-07-12012 July 1996 Safety Evaluation Supporting Amends 186 & 180 to Licenses DPR-31 & DPR-41,respectively ML17353A7011996-05-13013 May 1996 Safety Evaluation Supporting Amends 184 & 178 to Licenses DPR-31 & DPR-41,respectively ML17353A5941996-03-11011 March 1996 SE Approving Code Case N-416-1 as Alternative to Required Hydrostatic Pressure Test ML17353A5541996-02-13013 February 1996 Safety Evaluation Supporting Amends 182 & 176 to Licenses DPR-31 & DPR-41,respectively ML17353A5151995-12-28028 December 1995 Safety Evaluation Supporting Amends 181 & 175 to Licenses DPR-31 & DPR-41,respectively ML17353A4741995-12-12012 December 1995 Safety Evaluation Supporting Amends 180 & 174 to Licenses DPR-31 & DPR-41,respectively ML17353A4591995-11-29029 November 1995 Safety Evaluation Accepting Plant Containment Structural Reanalysis ML17353A4271995-10-17017 October 1995 Safety Evaluation Supporting Amends 177 & 171 to Licenses DPR-31 & DPR-41,respectively ML17353A4231995-10-17017 October 1995 Safety Evaluation Supporting Amends 178 & 172 to Licenses DPR-31 & DPR-41,respectively ML17353A4001995-10-10010 October 1995 Safety Evaluation Accepting Licensee 951220 & 0406 Requests Re Relief from Certain Requirements Concerning Second 10-yr Interval Inservice Insp Program at Plant,Units 3 & 4 ML17353A3431995-08-24024 August 1995 Safety Evaluation Supporting Amend 176 & 170 to Licenses DPR-31 & DPR-41,respectively ML17353A3121995-08-0808 August 1995 Safety Evaluation Supporting Amends 175 & 169 to Licenses DPR-31 & DPR-41,respectively ML17353A2441995-06-23023 June 1995 Safety Evaluation Supporting NRC Independent Flaw Calculations to Evaluate Licensee LBB Analysis of Large Diameter Reactor Coolant Piping for Plant,Units 3 & 4 ML17353A2321995-06-13013 June 1995 Safety Evaluation Supporting Approval of Request for Relief 4 for Licenses DPR-31 & DPR-41 ML17352B2101995-06-0909 June 1995 Safety Evaluation Accepting Licensee Requests for Relief. Relief Request Nine Involves Alternative Scheduling of Exams & Request Ten Involves Removal of Insulation from Bolted Connections on Borated Sys for Insp ML17352B1721995-05-12012 May 1995 Safety Evaluation Authorizing Relief on one-time Basis for Second 10-yr Interval ISI ML17352B1131995-04-12012 April 1995 Safety Evaluation Supporting Amends 172 & 166 to Licenses DPR-31 & DPR-41,respectively ML17352B0831995-03-31031 March 1995 Safety Evaluation Re Third ten-year Interval Inservice Program Plan & Associated Requests for Relief ML20136F5831995-01-20020 January 1995 Safety Evaluation Re Evaluation of Licensee Response to GL-87-02 ML17352A9751994-12-28028 December 1994 Safety Evaluation Supporting Amends 170 & 164 to Licenses DPR-31 & DPR-41,respectively ML17352A8771994-10-31031 October 1994 Safety Evaluation Accepting Util 930303,0517 & s Responding to NRC Bulletin 90-01,Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L9371999-10-20020 October 1999 Safety Evaluation Supporting Licensee Proposed Alternative from Certain Requirements of ASME Code,Section XI for First 10-Yr Interval Request for Relief for Containment Inservice Insp Program L-99-221, Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Turkey Point,Units 3 & 4.With L-99-202, Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Turkey Point,Units 3 & 4.With L-99-179, Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Turkey Point,Units 3 & 4.With 05000250/LER-1999-001-02, :on 990623,manual RT from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With1999-07-20020 July 1999
- on 990623,manual RT from 100% Power Following Multiple Control Rod Drops Was Noted.Caused by Manual Action Taken by Reactor Control Operator.Inspected & Repaired Stationary Gripper Regulating Cards.With
L-99-163, Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Turkey Point,Units 3 & 4.With ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17355A3611999-06-30030 June 1999 Refueling Outage ISI Rept L-99-134, Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Turkey Point,Units 3 & 4.With ML17355A3291999-05-0505 May 1999 Revised SE Supporting Evaluation for Certain Fire Zones in Tubine Building at Plant,Units 3 & 4 & Granting Licensee Request for Exemption from Technical Requirements of Section III.G.2a ML17355A3221999-05-0505 May 1999 Safety Evaluation Supporting Amends 200 & 194 to Licenses DPR-31 & DPR-41,respectively ML20217B9871999-04-0808 April 1999 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408 ML17355A2881999-04-0505 April 1999 COLR for Turkey Point Unit 4 Cycle 18 L-99-087, Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Turkey Point,Units 3 & 4.With ML17355A2791999-03-26026 March 1999 Safety Evaluation Concluding That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 for Plants L-99-063, Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Turkey Point Nuclear Power Plant,Units 3 & 4.With ML17355A2161999-02-0303 February 1999 Safety Evaluation Supporting Amends 199 & 193 to Licenses DPR-31 & DPR-41,respectively L-99-033, Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Turkey Point,Units 3 & 4.With ML17355A2201999-01-20020 January 1999 Refueling Outage ISI Rept L-99-004, Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Turkey Point,Units 3 & 4.With L-98-297, Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Turkey Point,Units 3 & 4.With 05000250/LER-1998-007-02, :on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With1998-11-18018 November 1998
- on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With
ML17354B1891998-11-0909 November 1998 Simulatory Certification Update 2 L-98-281, Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Turkey Point,Units 3 & 4.With 05000250/LER-1998-006-02, :on 981006,unescorted Access Was Granted to Contractor Employee Who Falsified Background Info.Caused by Individual Who Knowingly Provided False Info.Denied Access to Individual on 981006.With1998-10-27027 October 1998
- on 981006,unescorted Access Was Granted to Contractor Employee Who Falsified Background Info.Caused by Individual Who Knowingly Provided False Info.Denied Access to Individual on 981006.With
ML17354B1591998-10-23023 October 1998 COLR for Turkey Point Unit 3 Cycle 17 05000250/LER-1998-005-02, :on 980924,suspended Safeguards During Severe Weather Due to Personnel Safety.Caused by Severe Weather Associated with Effects of Hurricane Georges.Fully Instituted Compensatory Measure.With1998-10-16016 October 1998
- on 980924,suspended Safeguards During Severe Weather Due to Personnel Safety.Caused by Severe Weather Associated with Effects of Hurricane Georges.Fully Instituted Compensatory Measure.With
05000250/LER-1998-004-02, :on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With1998-10-16016 October 1998
- on 980921,automatic Reactor Trip Occurred. Caused by Inadequate re-correlation of Intermediate Range Neutron Flux Instrumentation Reactor Trip Bistable. Enhanced Applicable Plant Procedures.With
L-98-262, Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Turkey Point Unit 3 & 4.With ML17354B1021998-09-14014 September 1998 Correction to SER Page 5 of SE & Page 6 of Ineel Technical Ltr Rept to Reflect Change of Word Then with Also, Submitted on 980817 in Response to Util 980409 Request Relief from Certain Requirements of ASME Code,Section XI ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils L-98-236, Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Turkey Points,Units 3 & 4.With ML17354B0901998-08-17017 August 1998 SER Accepting Revised Requests for Relief Numbers 11 & 18 for Turkey Point,Units 3 & 4 L-98-206, Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 41998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Turkey Point,Units 3 & 4 ML17354B0541998-07-16016 July 1998 SER Accepting Alternative Proposed by Licensee in That Revising FSAR 6 Months After Refueling Outages for Each Unit Not Necessary to Achieve Underlying Purpose of Rule (10CFR50.71(e)(4)) 05000250/LER-1998-003-02, :on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves1998-07-15015 July 1998
- on 980619,discovered That Auxiliary Feedwater Sys Was Inoperable Due to Inadequate Inservice Testing of Valves.Caused by Misunderstanding of Testing Criteria.Util Revised Procedures & Verified Operability of Valves
ML17354B0421998-07-0909 July 1998 Safety Evaluation Supporting Amends 198 & 192 to Licenses DPR-31 & DPR-41,respectively L-98-187, Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 41998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Turkey Point,Units 3 & 4 ML17354B0171998-06-29029 June 1998 Rev 1 to PTN-FPER-97-013, Evaluation of Turbine Lube Oil Fire 05000250/LER-1997-007, :on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps1998-06-18018 June 1998
- on 970730,automatic Reactor Trip Occurred Due to Closure of B Msiv.Caused by Failed BFD22S Relay.Six Relays on 3A,3B & 3C MSIVs Were Replaced & Implemented Plant Change to Disable Electronic Trip Function on 3 AFW Pumps
ML17354A9651998-06-0909 June 1998 Safety Evaluation Supporting Amends 197 & 191 to Licenses DPR-31 & DPR-41,respectively 05000250/LER-1998-002-02, :on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays1998-06-0909 June 1998
- on 980513,discovered Potential LOCA-initiated Electrical Fault Which Places ECCS Outside Design Basis. Caused by Inadequate Review of Effect on non-safety Circuit failures.Re-powered PC-*-600A Relays
L-98-163, Monthly Operating Repts for Turkey Point,Units 3 & 41998-05-31031 May 1998 Monthly Operating Repts for Turkey Point,Units 3 & 4 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML17354A9351998-05-12012 May 1998 Safety Evaluation Supporting Amends 196 & 190 to Licenses DPR-31 & DPR-41,respectively L-98-128, Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 41998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Turkey Point,Units 3 & 4 L-98-095, Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 41998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Turkey Point,Units 3 & 4 05000250/LER-1997-009, :on 971114,discovered That CR Console Switch for 3B SGFP Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR1998-03-24024 March 1998
- on 971114,discovered That CR Console Switch for 3B SGFP Was Not in Start Position.Caused by Inadequate Procedural Guidance.Revised Procedures 3/4-OP-074,informed Personnel of Event & Performed Walkdown of CR
ML17354B0001998-03-18018 March 1998 Florida Power & Light Topical Quality Asurance Rept, Dtd June 1998 05000250/LER-1998-001-02, :on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be Revised1998-03-18018 March 1998
- on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be Revised
1999-09-30
[Table view] |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ELATED TO THE INSERVICE TESTING PROGRAM RE UESTS FOR RELIEF FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 DOCKET NUMBERS 50-250 AND 50-251
1.0 INTRODUCTION
The Code of Federal Regulations, 10 CFR 50.55a, requires that inservice testing (IST) of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable
- addenda, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to Sections (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a.
In proposing alternatives or requesting relief, the licensee must demonstrate that:
(1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for its facility.
NRC guidance contained in Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs,"
provides alternatives to the
, Code requirements determined acceptable to the staff.
Alternatives that conform with the guidance in GL 89-04 may be implemented without additional NRC approval.
Relief requests that conform with GL 89-04 are not evaluated in the TER, though they have been reviewed to determine conformance and any concerns identified by such reviews are discussed in Section 5,
" IST Program Recommended Action Items."
Section 10 CFR 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making the necessary findings.
The NRC staff's findings with respect to authorizing alternatives and granting or not granting the relief requested as part of the licensee's IST program are contained in this Safety Evaluation (SE).
The IST program-evaluated in this SE covers the third 10-year IST interval for the Turkey Point Plant, Units 3 and 4.
The interval for Unit 3 began February 22,
- 1994, and ends February 21, 2004.
The interval for Unit 4 began April 15,
- 1994, and ends April 14, 2004.
The third 10-year interval IST programs are based on the requirements of the 1989 Edition of the ASME Section XI Boiler and Pressure Vessel Code (the Code).
2.0 EVALUATION The Office of Nuclear Reactor Regulation, with technical assistance from Brookhaven National Laboratory (BNL), has reviewed the information concerning IST program requests for relief submitted for the updated IST program for the Turkey Point Plant, Units 3 and 4, in Florida Power and Light Company's letter dated January 12, 1994.
94ii020ii3 94i027 I
PDR ADOCK 05000250 P
PDR ~
~ ~
~
The staff adopts the evaluations and recommendations for granting relief or authorizing alternatives contained in the attached Technical Evaluation Report (TER) prepared by BNL.
Relief is granted from, or alternatives are authorized to, the testing requirements which have been determined to be impractical to perform, where compliance would result in a hardship without a compensating increase in
- safety, or where the proposed alternative testing provides an acceptable level of quality and safety.
A summary of the relief requests and NRC actions is provided in Table l.
The NRC has identified a number of generic deficiencies that affect plant safety and have frequently appeared as IST programmatic weaknesses.
These are addressed by GL 89-04.
In that letter, the staff delineated positions that describe deficiencies and explained alternatives to the ASHE Code that the staff considers acceptable.
If alternatives are implemented in accordance with the relevant position in the generic letter, the staff has determined that relief should be granted pursuant to 10 CFR 50.55a(g)(6)(i)
[now (f)(6)(i)] on the grounds that it is authorized by law, will not endanger life or property or the common defense and
- security, and is otherwise in the public interest.
In making this determination, the staff has considered the burden on the licensee that would result if the requirements were imposed.
For any relief granted pursuant to GL 89-04 the staff (with technical assistance from BNL) has reviewed the information submitted by the licensee to determine whether the proposed alternative follows the relevant position in the generic letter.
If an alternative conforms to a position of the generic letter, it is listed as having been approved pursuant to GL 89-04 in Table 1 of the safety evaluation.
Any action items in the relief request are addressed in the TER.
A sampling of systems was selected for a review of the scope of the IST program.
The review identified a few weaknesses or errors in the scope or in the program document that are listed in Action Item 5. 1 of Section 5 of the TER.
Test deferrals are addressed in Section 4 and in Action Items 5.5 and 5.6 of the TER.
The licensee should refer to the TER, Section 5, for a discussion of recommendations identified during the review.
The licensee should address each recommendation in accordance with the guidance therein.
The IST program relief requests are acceptable for implementation provided the action items identified in Section 5 of the TER are addressed within one year of the date of this SE or by the end of the next refueling outage, whichever is later.
The licensee should respond to the NRC within one year of the date of this SE describing actions
- taken, actions in progress, or actions to be taken, to address each of these items.
The staff concludes that the r'elief requests as evaluated and modified by this SE will provide reasonable assurance of the operational readiness of the pumps and valves to perform their safety-related functions.
The staff has determined that granting relief pursuant to 10 CFR 50.55a (f)(6)(i) and authorizing alternatives pursuant to 10 CFR 50.55a (a)(3)(i) or (a)(3)(ii) is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest.
In granting relief pursuant to 10 CFR 50.55a(f)(6)(i),
the staff has considered the impracticality of performing the required testing and the burden on the licensee if the requirements were imposed.
Principal Contributor:
Patricia Campbell, DE/EHEB
Turkey Point Units 3 and 4 SE Table 1 - Summary of Pump and Valve Relief Requests
'.-"":.-,,::,-:ReHef.:'::'--::':"
qRequest.Ão."-;
PR-1 PR-2 2.1 2.2
$5.2(d), inservice test conducted at specified test reference conditions, measuring hP, flow rate and vibration.
$5.2(b), system hP varied until fiow rate equals ref.
value or flow rate varied until hP equals reference value.
Boric Acid Transfer Pumps *-P203A&B Residual Heat Removal (RHR) Pumps
Quarterly testing - hP and vibration measured using fixed resistance flow path.
Refueling - hP, flow rate and vibration measured using variable resistance per
.$5.2(b).
Quarterly testing-Pump hP and fiow rate varied and compared to reference values using fixed resistance test circuit per $5.2(c).
Relief granted pursuant to 50.55a(f)(6)(i).
Relief granted pursuant to 50.55a(f)(6)(i).
Cold Shutdown and Refueling - Pump hP, flow rate, and vibration recorded per
$5.2(b).
SE Table 1 (Cont'd)
'.;.Reque'stiwo.::.-,,'.
'.--'.,Section
- jg~pJdentification"gl:~;-'; ',"::;-,'~Method':of.'.Testing!.."'-.::..g~~'~$ '-NRC."Action'",.'~;".-'."';"";.
PR-3 PR-4 PR-5 2.3 2.4
$4.6.1.2(a), full-scale range of each analog instrument shall be not greater than 3 times the reference value.
$4.6.2.1, static correction of indicated pressure measurement for liquid in gage line producing more than 0.25% difference in reading.
$4.6.1.6, frequency response range of vibration measurement system shall be 1/3 min. pump shaft rotational speed to at least 1000 Hz.
Residual Heat Removal (RHR) Pumps
Allpumps in IST program Intake Cooling Water Pumps *-P9A, B, C.
Use alternate instrument accuracy acceptance criteria.
Static correction of gage line reading for pump suction pressure producing more than 0.25% difference in calculated value of pump differential pressure.
Vibration measurement system frequency response range lower limit does not meet required lower limit.
Authorized pursuant to 50.55a(a)(3)(i).
Authorized pursuant to 50.55a(a)(3)(i), with provisions.
Authorized separately pursuant to 50.55a(a)(3)(ii) by NRC letter to licensee dated May 19, 1994 (Ref.
11).
SE Table 1 (Cont'd)
C A'"j?yQ'Request;Tw Q i~,;:c~$c ',""Acr'...x"'>> Pclkloll~~g'.':g';,;";.":p VR-1
$4.3.2.1, check valve testing frequency, and $4.3.2.4(d),
valve obturator movement by disassembly and inspection at refueling outages Containment Spray System check valves 3-0890 A&B(4-0890 A&B)
Disassembly/
inspection at refueling outages, manual full-stroke operation, part-stroke open test with fiow and seat leakage test following reassembly.
Authorized per Generic Letter 89-04, Position 2.
VR-2 3.1
$4.3.2.1, check valve testing frequency Safety Injection System check valves 5-0873 A&B(4-0873 A&B), 3-0874 A&B (44874 A&B)
Seat leakage test per Tech Spec 4.4.6.2.2 and Table 3.4-1 for Pressure Isolation Valves.
Relief not required.
Accepted as a deferral, with provlslolls.