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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 ML20248D7491998-05-28028 May 1998 Safety Evaluation Accepting Licensee Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping ML20217A7211998-04-17017 April 1998 Safety Evaluation Supporting Proposed Alternative for ANO-1 to Implement Code Case N-533 (w/4 H Hold Time at Test Conditions Prior to VT-2 Visual Exam) ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216D6111998-03-12012 March 1998 Safety Evaluation Supporting Amend 188 to License NPF-6 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20216E9921997-09-0404 September 1997 Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants ML20141H8411997-07-30030 July 1997 Safety Evaluation Accepting Use of Code Case N-508-1 for All Four Plants for Rotation of Serviced Snubbers & Pressure Relief Valves for Purpose of Testing in Lieu of ASME Code ML20138K0561997-05-0505 May 1997 SER Approving Licensees IPE Process Capable of Identifying Severe Accidents & Severe Accident Vulnerabilities,For Plant,Unit 2 ML20149M4221996-12-12012 December 1996 Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl ML20134P8411996-11-25025 November 1996 Safety Evaluation Denying Request for Relief 96-001 Re Second 10-yr Interval ISI Program Plan,Due to Failure to Provide Basis for Impracticality ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20149K9451996-02-16016 February 1996 Safety Evaluation Authorizing Relief Request for Second 10-yr Interval IST Program Plan for Pumps & Valves at Facility ML20058L6111993-12-13013 December 1993 Safety Evaluation Approving Second ten-year Interval Inservice Insp Request for Relief Re Use of IWA-5250 Requirements Listed in 1992 Edition of ASME Code ML20058F6661993-11-24024 November 1993 Safety Evaluation Accepting Licensee Proposed Use of New DG as Alternate AC Power Source for Coping W/Sbo Subject ML20056H1331993-08-23023 August 1993 Supplemental Safety Evaluation Re Conformance to Reg Guide 1.97.Plant Design in Conformance W/Guidance of Subj Reg Guide ML20056H0001993-08-19019 August 1993 Safety Evaluation Accepting Licensee 920918 Response to GL 87-02,suppl 1 ML20128C9181993-01-22022 January 1993 Safety Evaluation Supporting Inservice Testing Program Relief Requests for Pumps & Valves ML20126H8661992-12-30030 December 1992 Safety Evaluation Granting Relief from Certain Inservice Insp Requirements of Section XI of ASME Boiler & Pressure Vessel Code,Determined to Be Impractical to Perform ML20126F7571992-12-18018 December 1992 Safety Evaluation Accepting Util Conceptual Design for Proposed Alternate Ac Power Source ML20062A5751990-10-10010 October 1990 Safety Evaluation Re Station Blackout Rule.Util Response Does Not Conform W/Station Blackout Rule ML20062A5881990-10-10010 October 1990 Safety Evaluation Re Station Blackout Rule.Util Response Does Not Conform W/Station Blackout Rule ML20059A7081990-08-17017 August 1990 Sser Concluding That Rochester Instrument Sys Model SC-1302 Isolation Device Acceptable for Use at Plant for Interfacing SPDS W/Class IE Circuits ML20056A7511990-08-0707 August 1990 Safety Evaluation Accepting Licensee Fire Barrier Penetration Seal Program & Commitment to Complete 100% Review of All Tech Spec Fire Penetration Seals by 911231 ML20062C8341990-05-24024 May 1990 Safety Evaluation Granting Relief from Certain Inservice Insp Requirements of ASME Code,Section Xi,Per 881103 & 890823 Requests ML20245K3671989-08-11011 August 1989 Safety Evaluation Accepting Licensee Actions in Response to 890120 High Pressure Injection Backflow Event ML20247N7451989-07-31031 July 1989 Safety Evaluation Concluding That Isolation Devices Acceptable for Use in Spds,Contingent on Licensee Submittal of Followup Evaluation Verifying That Failure of RIC SC-1302 Was Randomly Deficient Device Prior to Testing ML20247A8371989-07-11011 July 1989 Safety Evaluation Re Generic Ltr 83-28,Item 4.5.3 Concerning Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20246J5421989-07-0707 July 1989 Safety Evaluation Re NRC Audit of Util Resolution of IE Bulletin 79-27.IE Bulletin Concerns Adequately Resolved for Facility.Periodic Test Program for Devices Recommended to Be Developed by Licensee ML20245K5971989-06-21021 June 1989 Safety Evaluation Concluding That Diverse Scram Sys & Diverse Initiation of Turbine Trip Meet Requirements of ATWS Rule (10CFR50.62) ML20245F3921989-04-25025 April 1989 Safety Evaluation Granting Util Relief from ASME Section XI Insp Requirements for Reactor Coolant Pump Casing Weld Indications Due to Impractical Requirements,Per Util 881027 Request & 10CFR50.55a ML20247E0191989-03-23023 March 1989 Safety Evaluation Supporting Instrumentation for Detection of Inadequate Core Cooling for Plants ML20206F5021988-11-15015 November 1988 Safety Evaluation Supporting Transfer of Operating Responsibility to Sys Energy Resources,Inc ML20205H8751988-10-25025 October 1988 Safety Evaluation Supporting Util 861124 & 880603 Responses to Generic Ltr 86-06,TMI Action Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps ML20151D4131988-07-12012 July 1988 Safety Evaluation Supporting Util 831105 Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability Online Testing ML20236A7581987-10-15015 October 1987 Evaluation Supporting Justification for Continued Operation Re High Reactor Bldg Temps ML20235W7011987-07-15015 July 1987 Safety Evaluation Re HPI Makeup Nozzle Cracking.Util Agreement to Record HPI Flowrate & Duration of Flow During HPI Actuation When SPDS Available Acceptable 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION HIGH PRESSURE INJECTION MAKEUP N0ZZLE CRACKING FACILITY OPERATING LICENSE NO. DPR-51 ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR ONE, UNIT NO. 1 DOCKET NO. 50-313 INTRODUCTION By letter dated March 10, 1986 (Reference 1), Arkansas Power and Light Company (AP&L; the licensee) submitted information to the Office of Nuclear Regulation (NRR) regarding implementation of recommendations contained in the B&W Owners Group Safe-End Task Force final report. The recommendations concerned operation of the makeup system, in particular the need for continuous makeup flow and the recommendation regarding logging of information about high pressure injection (HPI) initiations. Additional information was transmitted by licensee letter dated October 30, 1986 (Reference 2).
BACKGROUND Inspection Report 50-313/85-23 included a Notice of Deviation from previous commitments relative to implementation of the B&W Owners Group Safe-End Task Force Recommendations. The deviations concerned logging of HPI flow rate and duration for HPI actuations, and measurement of continuous makeup flow through the nozzles via bypass of Pressurizer Level Control Valve. The licensee's response to the Notice of Deviation (Reference 3) was in part:
"A continuous flow of makeup to the makeup nozzle is desirable to prevent severe thermal transients to the safe-end nozzle by maintaining it at the makeup temperature. In Inspection Report 50-313/85-23 the Inspector stated that the recommendation regarding a miminum bypass flow had not been met due to a flowmeter being pegged high. As stated in our letter of April 22, 1985, ANO-1 has a required minimum bypass flow of 1.0 gpm.
However, the flowmeter referenced by the Inspector cannot ensure this minimum flow. Due to the physical configuration of the makeup system the minimum makeup flow is approximately 15 gpm whenever the makeup system is operating. Normal makeup flow is from 30 to 60 gpm with a maximum of 160 gpm. Thus, the recommendation is satisfied by normal systems operations.
AP&L has re-reviewed our letter of April 22, 1985 regarding the logging of HPI initiations. This review has shown that the statement regardingThe logging of HPI initiations is not clear and could be misinterpreted.
intent of this statement was that AP&L had implemented the recommendation l to record HPI initiations. However, it was not intended to implyFour that of l
j all the parameters listed in the recommendations were recorded.
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the recommended six parameters are logged as noted by the inspector in the inspection report. The two remaining parameters, HPI flowrate and duration of HPI flow, are indicated but not recorded. The intent of the recommendations was to obtain information that might be used in analyses of future problems. Therefore, the additional parameters, while useful information, are not necessary for the safe operation of the HPI nozzles.
Additionally, the time and attention required to log these indications.
would distract the operators during unit trip recovery."
Region IV concluded that the licensee's reply constituted a revision of the commitments made in the April 22, 1985 letter (Reference 4) and recommended that it be brought to NRR's attention for review (Reference 5).
EVALUATION The basic consideration of the review is whether the ections taken by AP&L at ANO Unit 1, are consistent with the owners group recommendations (Reference 6);
and, if so, have they been implemented properly? The following recommendations were made by the owners group:
- 1. In terms of future repairs, it is recommended that:
Nozzles with Original Design Thertaal Sleeves
- a. Reroll the upstream end of the thermal sleeve when inspections indicate that a gap exists. A 5.0% wall reduction is suggested to achieve an adequate interfacial residual stress and avoid stress corrosion cracking of the thermal sleeve.
Nozzles with Modified Design Thermal Sleeve
- b. Repair and/or replace the damaged components if inspections reveal that abnormal conditions are present.
- c. In either case, the affected utility should also verify that the components attached to the safe end meet the design constraints used in the stress analysis.
- 2. In order to ensure proper HPI/MU system operation, it is recommended that:
- a. A continuous makeup flow via bypass of the Pressurizer Level Control l Valve should be maintained.
- b. A known amount of bypass flow wh'.ch is greater than 1.5 gpm should be maintained and checked frequently (increased flows of up to about 10-15 gpm may be preferable depending upon plant configuration and operating practices).
- c. There should be a consistent set of procedures to initiate continuous bypass flow RCS temperature RCS pressure Bypass flow rate Frequency of adjustment and calibration
- d. The makeup tank temperature should be maintained within the proper control band as determined by other plant parameters.
- e. In the event that future anomalies are discovered, proper logging of HPI initiations will be invaluable. This procedure should include:
Nozzles used Teinperature of BWST Temperature of cold leg before and after HPI initiation Pressure Flow rate Duration of HPI flow
- 3. An augmented inservice inspection plan as stated in Section 12.0 should be implemented.
- 4. A detailed stress analysis of a nozzle with a modified therual sleeve design should be performed to justify long term operation.
Section II of Reference 6 makes clear the intent of recommendation 2a. The closing paragraph of this section states:
In light of these findings, a minimum continuous makeup flow of 1-3 gpm (as originally specified) should adequately maintain all design parameters within analyzed limits and prevent thermal stratification.
However, it must also be pointed out that increasing continuous makeup flow may decrease the nozzle thermal stresses.
In the case of ANO Unit 1, the staff finds acceptable a 1.0 gpm continuous makeup flow via bypass of the Pressurizer Level Control Valve. Recommendation 2b requires the amount of bypass flow be known, be maintained and be checked frequently. The licensee has not made clear how this part of the recommendation :
is satisfied at ANO Unit 1. The information regarding the minimum makeup tiow of 15 gpm whenever the makeup system is operating is not an issue in relation to Recommendation 2b. It is the capability to readily ascertain the minimum bypass makeup flow of 1.0 gpm that is the deviation from the licensee's commit-ment to comply with Recommendation 2b.
1 Regarding recommendation 2e, AP&L has agreed to record HPI flowrate and du'.'ation of HPI flow when SPDS is available (Reference 4). If SPDS is highly available (for more than 50% of HPI actuations), then along with previous ;
l
y ' r l commitments AP&L has satisfied this recommendation. However, at the time of the inspection the licensee was deviating from the recommendation of the B&W Owners Group Safe-End Task Force.
CONCLUSION The licensee committed to implement at ANO Unit 1, the recommendations of the B&W Owners Group Safe-End Task Force. A NRC inspector noted two instances of recommendations that were not wholly implemented. First, the continuous s4akeup flow via a bypass could not, on demand, be known or checked to assure that it is being maintained. The licensee should implement this part of the recommendation or provide a justification for not doing so.
Second, at the time of inspection the HPI flowrate and HPI duration of flow were not recorded. The licensee did not make it clear in early correspondence that the intent was not to record these two parameters. Subsequently, the licensee agreed to record these parameters during a HPI actuation when SPDS is available. The staff's understanding that the availability of SPDS is high; therefore the licensee's proposal is acceptable.
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Principal Contributor: R. Wright Date:
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REFERENCES
- 1. Letter from J. T. Enos, Arkansas Power and Light Company, to J. F. Stolz, USNRC, dated March 10, 1986, Accession Number 8603180144 860310.
- 2. Letter from J. T. Enos, Arkansas Power and Light Company, to J. F. Stolz, USNRC, dated October 30, 1986, Accession Number 8611120354 861030.
< 3. Letter from J. T. Enos, Arkansas Power and Light Company, to R. P. Denise, USNRC, dated November 29, 1985.
- 4. Letter from J. T. Enos, Arkansas Power and Light Company, to J. F. Stolz, USNRC, dated April 22, 1985, Accession Number 8505090334 850422.
- 5. Letter from J. E. Gagliardo, USNRC, to J. M. Griffin, Arkansas Power and Light Company, dated January 27, 1986.
- 6. Babcock and Wilcox, 177 Fuel Assembly Owners Group, Safe-End Task Force Report on Generic Investigation of HPI/MU Nozzle Component Cracking, B&W Document Number: 77-1140611-00, Accession Number 8302230370 830216.
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