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MONTHYEARML20212P5851986-08-27027 August 1986 Forwards Request for Relief from ASME Code Section XI Hydrostatic Testing Requirements for Portions of Safety Injection Sys.Requirements Impractical.Exemption Previously Granted Under Project stage: Request ML20211H1001986-10-27027 October 1986 Advises That Nuclear Station Mods to Replace Cold Leg Accumulator Check Valves Described in LER 369/85-11 Postponed Indefinitely for Unit 2.Work Proceeding on Unit 1. Unit 2 Has Not Experienced Leakage from RCS Project stage: Other ML20212D7411986-12-29029 December 1986 Safety Evaluation Re Util 850827 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys.Relief Justified Project stage: Approval ML20212D7331986-12-29029 December 1986 Forwards SER Re Util 850827 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys.Relief Justified.Alternate Program of NDE & Hydrostatic Testing Acceptable Project stage: Approval 1986-12-29
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20249B6281998-06-12012 June 1998 Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower ML20248B0441998-05-27027 May 1998 Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety ML20197A6551998-03-0202 March 1998 Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet ML20203B1071998-02-0404 February 1998 Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20199F3361998-01-28028 January 1998 Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2 ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211E6871997-09-22022 September 1997 SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20148S2231997-07-0202 July 1997 Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2 ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20134P2421997-02-20020 February 1997 Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications ML20134G5551996-11-0707 November 1996 Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel ML20059G8601993-10-29029 October 1993 SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval ML20057F4121993-10-12012 October 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i) ML20057A0361993-08-26026 August 1993 Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively ML20056H3191993-08-24024 August 1993 SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations ML20126H3171992-12-28028 December 1992 Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage ML20058N7961990-08-0909 August 1990 Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247H7611989-07-18018 July 1989 Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively ML20246C4621989-06-29029 June 1989 Safety Evaluation Granting Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code ML20247C0171989-05-18018 May 1989 Safety Evaluation Supporting Util Actions to Recover from 890307-08 Unit 1 Steam Generator Tube Rupture Event ML20235M7781989-02-23023 February 1989 Safety Evaluation Supporting Util 890505 Relief Request 88-04 Re Addition of Insp Port on Containment Spray HX 1A ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program ML20236M9631987-11-0606 November 1987 Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue ML20236A2901987-10-14014 October 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20236H5291987-07-31031 July 1987 Safety Evaluation Granting Util 870407 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing ML20209B1511987-01-28028 January 1987 SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing ML20207E7551986-12-30030 December 1986 SER Supporting Removal of RCS Thermal Sleeves ML20212D7271986-12-29029 December 1986 SER Re Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs for Reactor Trip Sys Components. Response Acceptable.Item 2.1 Closed ML20212D7411986-12-29029 December 1986 Safety Evaluation Re Util 850827 Request for Relief from Hydrostatic Testing Requirements of ASME Code Section XI for Portions of Safety Injection Sys.Relief Justified ML20206M5621986-08-13013 August 1986 SER Accepting 840808 & 850621 Responses to IE Info Notice 84-90, Main Steam Line Break Effect on Environ Qualification of Equipment. Higher Temp Will Not Preclude Ability to Shut Down Reactor in Safe Shutdown Condition ML20215A9671986-05-22022 May 1986 SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl ML20137Y1761986-02-28028 February 1986 SER Accepting SPDS for Interim Implementation Until Listed Open Items Resolved ML20137T8871986-02-0606 February 1986 Safety Evaluation Supporting SPDS as Interim Implementation Until Open Issues Resolved.Issues Include Hot Leg Temp,Rhr Flow Rate,Stack Monitor,Steam Generator Radiation & Containment Isolation ML20138R5841985-10-31031 October 1985 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.1.3,3.2.1,3.2.2,3.2.3,4.1 & 4.5.1 ML20134B8221985-08-0606 August 1985 Sser Supporting Dcrdr ML20128G1111985-06-21021 June 1985 SER of Util Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability).Response to Item 1.2 Complete & Acceptable ML20129D5521985-05-30030 May 1985 SER Accepting Licensee Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program Description & Procedure ML20126J3601981-04-30030 April 1981 Safety Evaluation Re Emergency Preparedness Evaluation Rept 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
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ENCLOSURE SAFETY EVALUATION OF REQUEST FOR RELIEF FROM RE0VIREMENTS OF ASME SECTION XI .
MCGilIRE, UNITS 1 AND 2 DUKE POWER COMPANY
- By letter dated August 27, 1986, Duke Power Company (the licensee) requested
! relief from the ASME Boiler anet Pressure Vessel (R and PV) Code,Section XI, inservice hydrostatic test requirements on portions of the Safety Injection Systems for McGuire Nuclear Station, Units 1 and 2. The reason for this re-quest was that the licensee had determined that conformance with the Code hydrostatic test was impractical.
These Safety Injection (NI) System modifications involve replacing the dis-charge check valves for the cold leg accumulators. These valves also serve as a path for return flow to the Reactor Coolant (NC) System from the Decay Heat Removal (ND) System during a shutdown mode. A total of sixteen valves (2 per loop x 4 loops x 2 plants) will be replaced due to excessive seal and hinge pin wear.
Replacement of four of the check valves was performed during the recent Unit 1 end of cycle (EOC) 3 refueling outage (September 1986), with the remaining Unit I valves to be replaced during the next refueling outage (E0C A). It was initially intended to replace all of the valves in Unit 2 during E00-3.
Because these valves are currently not leaking, the replacement of the valves in Unit 2 will be postponed. It is, however, anticipated that replacement will be necessary within the current 10-year inspection plan interval. So, this relief evaluation is for both units.
Relief from hydrostatic testing has previously been granted for this same por-tion of the NI System for a similar modification (reference Mr. T.M. Novak's (NRC/0NRR) letter to Mr. H.R. Tucker (DPC) dated December 29,198?). -
Recause of the difficulties in performing h"hostatic tests on these portions of the systems, and the return of the syste a to operation in a timely schedule, the licensee requested this relief. The licensee stated that the alternate examinations specified in this relief request are equal to or better than the required testing per the Code.
The specific details on the requested relief are as follows:
- 1. The Specific ASME Code Section XI Requirement That Licensee Claims To Be Impractical ASME R and PV Code,Section XI, 1980 Edition through Winter 1980 Addenda, IWA - 4a00, IWR - 5000 requires a hydrostatic test to be performed following repair or replacement by weldino.
hko$h369 PDR
- 2. Component For Which Relief Is Required:
A. Name and Numbers Units 1 and 2 Safety In.fection (NTI System primary and secondary check valves to the Reactor Coolant (NC) System (Reference Fig. I and 2 in the licensee's submittal) will be replaced.
B. Function The NI system provides emergenc.y core cooling to the Reactor Vessel. This particular portion of the system also provides a flow path for removal of decay heat in the shutdown condition, and is the primary flow path for the cold leg accumulators.
C. The ASME Section III Code Class is equivalent to Class 1 P. VALVE CATEGORY
- 1. The replacement valves are designed and fabricated in accordance with the ASME B&PV Code Section III - Class 1, 1983 Edition - Winter 1984 Addenda.
- 2. The valves are rated in accordance with ANSI B16.34-1981 1515 # special.
E. MATERIALS AND WELDS The materials used are:
- 1. 10" x 10" x 6" Reducing tee, schedule 140 x 160 (1.00" x
.718") SA-403 WP316 (P No. 8 Group li.
- 2. 10" 90* Elbow, Sch. 140, (1.00") SA-403 WP316 SMLS BW (P No. 8 Group 1).
- 3. 10" Pipe, Sch. 140, (1.00") SA 376 TP 316 (P No. 8 Group 1).
- 4. Valves, SA351 Grade CF8M (P No. 8 Group 1) (Reference Fig.
I and 2 in the licensee's submittali.
All welds are to be open root groove type utilizing a 37.5 5* bevel made to an IAN approved welding program. The root opening (1/8" 1/32") is to be filled by a minimum of two passes of gas tungsten are welding and finished up by shielded metal arc welding.
The reason that the licensee is recuesting relief is that there are no isolation valves downstream of these primary and secondary check valves to the NC system, therefore, it is impossible to isolete these portions of systems.
There are several approaches to partially pressurizino the system. The first approach would be to pressurize the Reactor Coolant (hC) System to 2,235 psi, and then use the Safety In,iection (NI) pumps to pressurize the NI Systems against one of the check valves. However, this pump pressure is only 1,600 psi, which falls far short of the required test pressure.
The second approach would be to remove the internals from the primary check valves which go to the NR System, and then pressurize the NC System to 1.02 times 2,236 pounds at 500 F temperature. However, this method would still not achieve the desired test pressure and temperature per the Code, because this portion of the system would be a dead leg pipe with no flow and uninsulated and, therefore, the convective and conductive effect of heat transfer would possibly make the 500 F temperature minimum unattainable.
This would also require draining the system in order to replace the internals in the check valve, a time consuming and costly procedure.
Therefore, due to orientation of the valves within the system, it is not possible to hydrostatically test the system. However, the alternate examinations as specified below are equal to or better than the required .
testing per the Code.
In lieu of the required hydrostatic test, the licensee has proposed to perform a 100% radiographic examination plus a 100% penetrant (PTT examination on the completion of all pressure boundary walds. A PT examination of all weld root passes will also be performed.
Also, a hydrostatic test will be performed at the 10-year inspection interval per Section XI of the ASME Code. An inservice leak test cannot be performed on this system because if the check valves hold, the system will not see system pressure. In addition, an ultrasonic (UT) examination will be performed on the welds for preservice baseline inspection per ASME Section XI.
The licensee has stated that these examinations, with the exception of the hydrostatic test, will be carried out after the modification on the Safety iniection (Nil System is complete, and prior to the system being declared operable.
Staff Evaluation: The relief reouest is acceptable for both Units 1 and 2 based on the following considerations.
- 1. Requiring the ASME Code hydrostatic tests to be performed at this time would result in a substantial additional manpower expenditure, additional occucational radiation exonsure, and possibly would delav plant startup. Therefore, hydrostatic testino at this time would result in hardships or unusual difficulties without a commensurate increase in the level of quality and safety.
- 2. Perforr:ance of the radiographic, surface, and ultrasonic examinations would oenonstrate e/Feuate structural integrity.
Duke Power Compery Frr ccrr;itted to performing the requirec 10-year intersel hycrcstatic tests which would irclude the niodifiec pcrtien of the NI system.
C0hCLUSIONS Relief from the inservice hydrottotic tests required by Section T! ic itstified.
The alternative rrogran, as proposed by Duke Power Coritary, of nor' destructive examinations ers bycrcstatic testing at prettritre 10-year intervals will pre -
vice at eccepte.ble level of structerei irtegrity. The specific requirener.it O' bection XI of the ASl'E Loiler tre Pressure Vessel Code,1980 Editiu. ttrcugh Winter ISEL l.ccci de , are impractical in this ce!.t . Ir/piercentation of the requirenients would rcsvit in hardships or unusual difficu'ities without a com-pensating increase it, the level of quality and safety. /ccr.roingly, the Cor.t,ission tts vetermined to grant relfe' froo the Lycrostatic test requite-rients as requested basec upoi the cct clusion that it is authorizet by 1to, l will ret endancer life or property or the conocn defense and security, nr.d *!
otterwise iri the public interest givei c'ue consideration to the burdar trcr the licensee that could resu't if the requirements were iraposed or tFr facility, l
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