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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
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| By letter dated February 3,1988 (BECo 88-018), the Licensee provided technical evaluations and acceptance criteria to address fire door-to-frame, frame-to-wall and anchor bolting irregularities. The Licensee provided this information as a result of staff concerns expressed at a meeting with BECo on November 24, 1987, 2.0 EVALUATION The Licensee submitted a detailed and fomal Fire Protection Engineering Evaluation (FPEE) for each class of irregularity noted above. The object of each FPEE was to address fire door installation and establish acceptance criteria that ensure the doors provide the required fire protection. | | By {{letter dated|date=February 3, 1988|text=letter dated February 3,1988}} (BECo 88-018), the Licensee provided technical evaluations and acceptance criteria to address fire door-to-frame, frame-to-wall and anchor bolting irregularities. The Licensee provided this information as a result of staff concerns expressed at a meeting with BECo on November 24, 1987, 2.0 EVALUATION The Licensee submitted a detailed and fomal Fire Protection Engineering Evaluation (FPEE) for each class of irregularity noted above. The object of each FPEE was to address fire door installation and establish acceptance criteria that ensure the doors provide the required fire protection. |
| The staff reviewed and evaluated each FPEE separately. The results of this review and evaluation are presented below: | | The staff reviewed and evaluated each FPEE separately. The results of this review and evaluation are presented below: |
| A. Fire Door Clearance (FPEE 88, Rev. 1 dated 1/27/88) | | A. Fire Door Clearance (FPEE 88, Rev. 1 dated 1/27/88) |
Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt IrregularitiesML20154J910 |
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Pilgrim |
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05/17/1988 |
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Office of Nuclear Reactor Regulation |
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ML20154J900 |
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NUDOCS 8805270178 |
Download: ML20154J910 (6) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20137D0511997-03-20020 March 1997 Safety Evaluation Approving Third 10 Yr Interval ISI Program & Requests for Relief ML20134K2621997-02-10010 February 1997 Safety Evaluation Accepting Licensee one-time Request to Defer Insp of N2A & N2B safe-end Welds,Per GL 88-01 ML20129H3901996-10-30030 October 1996 Safety Evaluation Re Facility IPE Submittal for Internal Events & Internal Flood ML20129F4031996-09-27027 September 1996 Safety Evaluation Accepting Second ten-year Interval Inservice Insp Program Plan Request for Relief ML20059C3751993-12-29029 December 1993 Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402 ML20058G2781993-11-29029 November 1993 Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv) ML20056F5301993-08-11011 August 1993 Safety Evaluation Re Licensee Response to Reg Guide 1.97, BWR Neutron Flux Monitoring. Criteria of NEDO-31558, Acceptable for Current BWR Operating License & Const Permit Holders ML20127P5431993-01-25025 January 1993 Safety Evaluation Supporting Amend 145 to License DPR-35 ML20126F8121992-12-23023 December 1992 Safety Evaluation Accepting Facility Design W/Respect to RG 1.97 ML20244C2901989-06-0606 June 1989 Draft Safety Evaluation of Util Compliance W/Atws Rule (10CFR50.62) Re Alternate Rod Injection & Recirculation Pump Trip Sys.Alternate Rod Injection Sys Not in Compliance W/Atws Rule Re Diversity ML20235V7341989-03-0303 March 1989 Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station ML20154P6611988-09-28028 September 1988 SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4) ML20151D0551988-07-18018 July 1988 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20151E2041988-07-15015 July 1988 Safety Evaluation Supporting Incorporation of Reactor Protection Sys Circuitry Into Tech Specs & Deletion of 6- Month Channel Functional Test ML20154J9101988-05-17017 May 1988 Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt Irregularities ML20155F8871988-03-24024 March 1988 Safety Evaluation Concluding That Internal Smoke Seals for Conduits Passing Through Fire Barriers from One Fire Area to Another Consistent W/Branch Technical Position 9.5-1 & Acceptable,Per Util 880203 Submittal ML20236Y3991987-11-10010 November 1987 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Equipment Classification.Salp Input Encl ML20236V3081987-10-28028 October 1987 Safety Evaluation Supporting Acceptance of Offsite Dose Calculation Manual Updated Through Rev 1 on Interim Basis. App D to Technical Evaluation Rept EGG-PHY-7725 Encl ML20235M1611987-09-30030 September 1987 Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing ML20236Y3591987-07-22022 July 1987 Safety Evaluation Accepting Licensee Request to Modify Standby Liquid Control Sys Tech Specs,Per Requirements of ATWS rule,10CFR50.62.C.4.SALP Input Also Encl ML20206G8141987-03-26026 March 1987 Safety Evaluation Re Util Requests for Relief from Inservice Insp Requirements for Surface & Volumetric Exam of RHR Sys HX Nozzles & Exam of 100% Required Vol for nozzle-to-vessel Welds.Requests Granted W/Listed Conditions ML20215H9581987-03-17017 March 1987 Safety Evaluation Supporting Tech Spec Change Re Control Room High Efficiency Air Filter Sys.Salp Input Encl ML20212L8941987-01-15015 January 1987 Safety Evaluation Supporting Vacuum Breaker Analysis Performed to Predict Impact Velocities & Resulting Stresses ML20236Y3501986-09-0303 September 1986 Safety Evaluation Accepting Licensee 850813 Response Re Generic Ltr 83-28,Item 1.1 on post-trip Review.Salp Input Encl ML20212N8401986-08-22022 August 1986 SER Supporting Util Response to Item 1.C of NRC Re No Specific Time Limit Necessary on Containment Purging & Venting During Reactor Operation ML20155F8931986-08-20020 August 1986 Safety Evaluation Accepting Util 831116 Request for Four Exemptions from 10CFR50,App R,Section Iii.G.Level of Fire Safety in Listed Fire Zones Equivalent to Safety Achieved by Compliance W/Requirements ML20206L9511986-08-12012 August 1986 Safety Evaluation on Util Response to Generic Ltr 83-28, Items 3.1.1,3.1.2,.3.2.1,3.2.2 & 4.5.1 Re Maint & Test Procedures for safety-related Equipment & on-line Functional Testing of Reactor Trip Sys.Responses Acceptable ML20205C0621986-07-31031 July 1986 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1, Post-Trip Review. BWR Parameter List Encl ML20236Y3361986-07-10010 July 1986 Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 1.2 on post-trip Review & Data & Info Capability ML20199L2541986-07-0101 July 1986 Safety Evaluation Supporting Amend 96 to License DPR-35 ML20206D1741986-06-0606 June 1986 Safety Evaluation Supporting Util Response to IE Bulletin 80-11 Re Reevaluation & Testing Requirements in Items 2(b) & 3 Concerning Masonry Wall Design ML20203N3801986-04-30030 April 1986 Safety Evaluation Supporting Util 840625,1204,06,850521 & 1011 Responses to Generic Ltr 86-04 Concerning Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii).Facility Does Not Require Recombiner Capability ML20236Y3711986-04-0101 April 1986 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components,Respectively. SALP Input Also Encl ML20137V7621986-02-12012 February 1986 SER Supporting Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping ML20135E5211985-09-11011 September 1985 Safety Evaluation Supporting post-trip Review Program & Procedures ML20134H3571985-08-13013 August 1985 Safety Evaluation Granting 821203,0804,831201,840628 & 850212 Relief Requests from ASME Code Requirements of Inservice Insp Program,Except for Items B9.10-B9.40 & C5.10-C5.32 Re Pressure Retaining Welds ML20140G1431985-07-0505 July 1985 Interim Safety Evaluation Supporting Util Response to Generic Ltr 83-36 Re NUREG-0737 Tech Specs ML20129C6901985-05-16016 May 1985 Safety Evaluation Re Dcrdr.Supplemental Rept Addressing Concerns Identified Necessary to Meet Requirements of NUREG-0737,Suppl 1 ML20206K6161985-03-13013 March 1985 SER Supporting Proposed Tech Spec Change to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Testing of Hydrogen Addition Water Chemistry.Related Documentation Encl 1999-09-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
[Table view] |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO FIRE DOOR-TO-FRAME FRAME-TO-WALL AND ANCHOR BOLT IRREGULARITIES BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated February 3,1988 (BECo 88-018), the Licensee provided technical evaluations and acceptance criteria to address fire door-to-frame, frame-to-wall and anchor bolting irregularities. The Licensee provided this information as a result of staff concerns expressed at a meeting with BECo on November 24, 1987, 2.0 EVALUATION The Licensee submitted a detailed and fomal Fire Protection Engineering Evaluation (FPEE) for each class of irregularity noted above. The object of each FPEE was to address fire door installation and establish acceptance criteria that ensure the doors provide the required fire protection.
The staff reviewed and evaluated each FPEE separately. The results of this review and evaluation are presented below:
A. Fire Door Clearance (FPEE 88, Rev. 1 dated 1/27/88)
1. Background
Licensee inspections conducted during the current outage (refuel outage I number seven) revealed a number of existing fire door units that had l clearance between the door and frame in excess of the 1/8 inch allowed by either Underwriters Laboratories (UL) reference 108-1979, "Fire Tests of Door Assemblies," or National Fire Protection Association (NFPA) reference 80-1986 3 "Standard for Fire Doors and Windows." Adjustments to red' ice the door-to-frame clearance were made where possible, yet some could not be reduced to the required maximum.
The Licensee reviewed the consequences of a fire within the plate on either side of a fire door with excessive clearances and datemined that if the gaps do not exceed the following criteria, there would be no change in the degree of protection provided by the door, ii. Acceptance Criteria:
Clearance between the door and frame, and between the meeting edges of doors swinging in pairs, shall meet the following conditions:
- a. The averaae gap along the jambs head and between the leaves of double doors shall not exceed 3/16 inch. The total allowable area of the gap is 3/16 inch times the total length of the gap.
8805270170 880517 PDR ADOCK 05000293 F PDP
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- b. Provided item a. is met, the maximum gap is to be less than or eoual to 1/4 inch at any location.
iii. Technical Evaluation In 1985 UL conducted a fire test (Project 84NAC489, File NC603) with two door / frame assemblies to evaluate the effect of a gap between the frame of a door and a masonry-type wall. The installed cor4 figuration resulted in door to frame clearances greater than the 1/8 inch clearance allowed by UL in their own test standard. Two of the three jambs on each of the doors were noted as having an average clearance of 3/16 inch.
Both of the door assemblies in this UL fire test withstood the fire endurance and hose stream portions of the test without developing any openings.
A second set of tests conducted by Warnock Hersey, independent of the UL test, was specifically designed to evaluate the effects of excessive clearance between the door and frame in both single and double leaf assemblies. These tests were conducted in accordance with UL 10B (and other compatible fire door test standards) !
requirements, with the exception of the following clearance changes:
All door-to-frame gaps were increased to 1/4 inch.
Gaps at the bottom of the doors were increased to 1 inch.
Strike plates were shimed to obtain a clearance of 1/8 inch between door and strike plate to ensure adequate engagement of i the 1/2 inch latch bolt.
As in the UL test, the results of the Warnock Hersey test showed that the modified door assemblies with excess clearances were still capable of passing a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire endurance and hose stream test.
The slightly larger door-to-frame gap has no effect on the !
conduction and radiation methods of heat transfer or fire spread !
because: '
- 1. The wider gap is still totally obstructed by the frame's stop, thus blocking the "line of sight" for radiant energy transfer between the fire and any exposed combustible material on the non-fire side of l the door. Therefore, it is ui.likely that fire can be spread by radiant energy.
- 2. The gap has no effect on conduction because there is no solid material, or mass, even in a properly spaced gap for this heat transfer method to take place.
I i
To further enhance the fire endurance of these door assemblies, the Licensee has developed administrative controls to prevent the accumulation of transient combustibles in areas adjacent to fire doors. These administrative controls include a crocedure that addresses prcper storage of flammable and combustible materials 4 well as a procedure requiring periodic inspections. The periodic inspections are intended to ensure that excessive amounts of transient combuttible materials are not brought into the plant and that no combustibles are stored in uracceptable locations, especially in the immediate area of fire doors. With these administrative controls in place, it is unlikely that any flame extension beyond the door surface would be sufficient to reach combustible materials an the non-fire side of the door, is Conclusion Based upon the technical eval 9ation presented above, the staff concludes tnat Pilgrim fire doors meeting the acceptance criteria of 2.A.ii will be capable of providing the required fire resistance.
B. Fran,e-to-Wall Clearance (FPEE 89, Re". O dated 12/21/87) i, Background Licersee insoections conducted caring the current outage (refuel outsge number seven) revealed a number of existing fire door units for which clearance betw?en the door frame and wall opening exceeded the original assembly requirement of ore cuarter inch. Because no current references were fcund that specifically address this issue for fire i
dcors, the Licensee contacted Underwriters Laboratories for guidance. Underwriters Laboratories established that t9e existing frame to wall gaps were not in strict compliance with "normal" installation criteria and provided the following two methods to resolve the deviation: fill the 96p with fire retardant material, or install metal shims behina each door frame anchor to improve fit, ii. Technical Fvaluation Filling the gap between the fire door frame and wall tith a fire resistant cementatious material will retard the spalling of existing grout under the door frame backbend. This justification is bar.ed on the results of a penetration seal test conducted by Promatech (Three Hour Fire Qualification Test, CTP 1001A, dated 7/25/80), in which a 3/4 inch bead of silicone caulk provided a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire seal for a 1/2 inch sngular space around a 2-1/2 inch pipe penetration.
1
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4 The installation of metal shims behind each fire door frame anchor has been tested and proven acceptable. Undemriters Laboratories conducted their test 108-1977, "Fire Tests of Door Assemblies" on a fire door asscnbly having a maximum 1/4 inch gap between the frure and wall. The tested assembly used metal shims behind each frame anchor to eliminate the gap at door anchor locations and is therefore accepted only when the frame-to-wall gap is 1/4 inch or less.
iii. Conclusion Based on the technical evaluatian presented above, the staff concludes that Pilgrirr fire doors that are caulked or metal shimed as described in 2.B.ii, will be capable of n.aintainir.g their fire resistance rating.
C. Fire Door Anchor 9olting (FPEE 90, Rev. O dated 12/18/8/)
1., Background Licensee inspections conducted during the current outage (refuel outage number seven) revealed a number of existing # ire door units that had fewer, and sometimes smaller, anchor bolts than required by Underwriters Laboratories standard 63-1976, "Fire Door Frames."
The Licensee contacted Underwriters Laboratories and proposed installation of additional 3/4 inch diameter anchor bolts to reach the required number in each fire docr frame. Unde mriters Laboratories replied that thic solution was not necessary, as long as the total anchorage system provided the same pullout resistance as UL standard 63-1976, "Fire Door Frames "
ii. Technical Evaluation The Licensee performed a calculatior. (No. C15.0.2220, Rev. 0 "3 F i .*e Door Anchorage") to determine the number and type of additional l bolts required to equal the pull out resistance of four, l 3/4 inch expansion shell anchor type bolts. Because of the location of existing bolts and the amount of labor required to remove a frame, the licensee elected to use a botting system that would eliminate the need to pull the frame from the opening. This boltieg systen can be installed by u 111ng a hole through the frame and into the wall to the required depth. The belts can then be inserted through the frame, into the wall and set to establish the requirod anchorage.
The calculation demonstrated that an additional three. 3/8 inch "Kwik" or "hol-hugger" type bults are required on each side jamb, no matter what the size of the existing bolts.
While grout placed within and behind the frame may help existing frame anchor bolts resist rotacion ard/or pull-out, the Licensee could net quantify the additional value of the grout. Tnerefore, for conservstism, an additional three anchor bolts will be installed in each #fre door jamo that is grouted.
1
_ _ . _ _= s
4 As for the use of reinforcements required on the inside of the frame soffit behind new anchor bolts, the Licensee has determined that one of the following options is an acceptable alternative:
- 1. If the frame is not grouted, a reinforcement shim shall be installed to prevent frame daformation or bolt pull-through during tightening, or
- 2. Grouted trames will not require the inclusion of a reinforcement shim since the grout will prevent frame deformation and resist bolt pull-through, iii. Conclusion Based or4 the technical evaluation presented above, fire door frames that are reanchored and/or reinforced with shims as described will be capable of maintaining their fire resistance rating.
3.0
SUMMARY
CONCLUSION Based nn the three technical evaluations presented herein, the staff finds thr.'. Pilgrim fire door a',semblies that meet the installation or acceptance criteria described above. will be capable of maintaining their fire resistance rating.
ACKNOWLEDGEMENT Principal Contributor- E. H. Trottier Dated:
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