|
|
Line 14: |
Line 14: |
| | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT | | | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT |
| | page count = 2 | | | page count = 2 |
| | | project = TAC:61578 |
| | | stage = Approval |
| }} | | }} |
|
| |
|
Line 25: |
Line 27: |
| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
|
| |
|
| The licensee plans to build a new Record Storage Center adjacent to the existing record storage office. By letter dated April 25, 1986, the licensee requested approval of ten deviations to the codes and standards that ensure adequate protection of the documents to be contained in this new Record Storage Center. The specific codes and standards for which a the licensee requested deviations are National Fire Protection Association (NFPA) Standard No. 232 (which pertains to fire protection for record storage facilities) and ANSI N45.2.9-1974 (which pertains to | | The licensee plans to build a new Record Storage Center adjacent to the existing record storage office. By {{letter dated|date=April 25, 1986|text=letter dated April 25, 1986}}, the licensee requested approval of ten deviations to the codes and standards that ensure adequate protection of the documents to be contained in this new Record Storage Center. The specific codes and standards for which a the licensee requested deviations are National Fire Protection Association (NFPA) Standard No. 232 (which pertains to fire protection for record storage facilities) and ANSI N45.2.9-1974 (which pertains to |
| , collection, storage, and maintenance of Quality Assurance records). Both of these standards are referenced in NRC Standard Review Plan a (NUREG-0800) Section 17.1.17.4. | | , collection, storage, and maintenance of Quality Assurance records). Both of these standards are referenced in NRC Standard Review Plan a (NUREG-0800) Section 17.1.17.4. |
| 2.0 EVALUATION 2.1 Fire Protection y After reviewing the licensee's deviation requests related to fire protection, the staff expressed concern regarding the fire resistance of the exterior walls and ceiling / roof assembly, as well as the design for the automatic and manual fire protection systems. The licensee responded to these concerns by letter dated August 15,1986(P-86516). The exterior walls will be fire rated at two hours. In order to achieve this rating, the doors and dampers will be rated for three hours. The staff concludes that this level of fire resistance is sufficient to provide protection from any potential external exposure fire. | | 2.0 EVALUATION 2.1 Fire Protection y After reviewing the licensee's deviation requests related to fire protection, the staff expressed concern regarding the fire resistance of the exterior walls and ceiling / roof assembly, as well as the design for the automatic and manual fire protection systems. The licensee responded to these concerns by {{letter dated|date=August 15, 1986|text=letter dated August 15,1986}}(P-86516). The exterior walls will be fire rated at two hours. In order to achieve this rating, the doors and dampers will be rated for three hours. The staff concludes that this level of fire resistance is sufficient to provide protection from any potential external exposure fire. |
| The ceiling / roof assembly will be supported by unprotected steel. The licensee responded to the staff's concern about the structural integrity of this steel during a fire exposure by describing the design of the proposed halon fire suppression system, fire detection and alarm system, and manual fire fighting equipment. The fire detection and alarm system will be designed in accordance with NFPA Standards Nos. 72D and 72E. The halon system will be designed in accordance with NFPA Standard No. 12A. | | The ceiling / roof assembly will be supported by unprotected steel. The licensee responded to the staff's concern about the structural integrity of this steel during a fire exposure by describing the design of the proposed halon fire suppression system, fire detection and alarm system, and manual fire fighting equipment. The fire detection and alarm system will be designed in accordance with NFPA Standards Nos. 72D and 72E. The halon system will be designed in accordance with NFPA Standard No. 12A. |
| It will be capable of providing a sufficient concentration of halon gas to control any potential fire within the storage area, and is designed to 8609240164 860915 PDR ADOCK 05000267 F PDR l | | It will be capable of providing a sufficient concentration of halon gas to control any potential fire within the storage area, and is designed to 8609240164 860915 PDR ADOCK 05000267 F PDR l |
Line 43: |
Line 45: |
| S The level of fire protection proposed by the licensee will achieve an equivalent level to that which would be achieved by complete compliance with NFPA Standard No. 232. Therefore, the licensee's request for deviations from this standard is acceptable. | | S The level of fire protection proposed by the licensee will achieve an equivalent level to that which would be achieved by complete compliance with NFPA Standard No. 232. Therefore, the licensee's request for deviations from this standard is acceptable. |
| Similarly, the licensee's request for a deviation from ANSI N45.2.9-1974 is acceptable because any missiles resulting from the failure of the new Record Storage Center will not damage any Category I structure or safety-related equipment. | | Similarly, the licensee's request for a deviation from ANSI N45.2.9-1974 is acceptable because any missiles resulting from the failure of the new Record Storage Center will not damage any Category I structure or safety-related equipment. |
| Based on the above findings, the staff approves the ten deviation requests contained in the licensee's April 25, 1986 letter (P-86069) from D. Warembourg (PSC) to H. Berkow (NRC). With the exception of these ten deviations, the design of the new Record Storage Center will be in accordance with the NRC Standard Review Plan (NUREG-0800) Section 17.1.17.4 concerning the design of suitable facilities for the storage of Quality Assurance records. | | Based on the above findings, the staff approves the ten deviation requests contained in the licensee's {{letter dated|date=April 25, 1986|text=April 25, 1986 letter}} (P-86069) from D. Warembourg (PSC) to H. Berkow (NRC). With the exception of these ten deviations, the design of the new Record Storage Center will be in accordance with the NRC Standard Review Plan (NUREG-0800) Section 17.1.17.4 concerning the design of suitable facilities for the storage of Quality Assurance records. |
| Principal Contributors: D. Kubicki R. Lipinski Dated: September 18, 1986 | | Principal Contributors: D. Kubicki R. Lipinski Dated: September 18, 1986 |
| _ _ _. -.__.__ . _ _ _}} | | _ _ _. -.__.__ . _ _ _}} |
Latest revision as of 13:56, 4 May 2021
Letter Sequence Approval |
---|
|
|
MONTHYEARML20266D8291986-02-11011 February 1986 Record Storage Bldg Addition Roof Details Project stage: Other ML20266D8251986-02-11011 February 1986 Record Storage Addition Elevations & Details. Sheet 1 of 1 Project stage: Other ML20266D8391986-02-12012 February 1986 Record Storage Addition - Plot Plan. Sheet 1 of 1 Project stage: Other ML20266D8341986-02-12012 February 1986 Record Storage Bldg Addition Floor,Wall & Door Details. Sheet 1 of 1 Project stage: Other ML20266D8211986-02-12012 February 1986 Record Storage Addition - Elevations. Sheet 1 of 1 Project stage: Other ML20266D8161986-02-12012 February 1986 Record Storage Addition - Plan View. Sheet 1 of 1 Project stage: Other ML20198A1431986-04-25025 April 1986 Discusses Codes & Stds That Will Provide Design Basis for New Record Storage Ctr.Requested Exemptions to Reg Guide 1.88 & NUREG-0800 Re Facilities for Storage of QA Records Encl.Six Oversize Drawings Also Encl Project stage: Other ML20206M1161986-08-14014 August 1986 Forwards Request for Addl Info Re Proposed Record Storage Ctr,Including Design Details Concerning Location & Spacing of Fire Smoke Detectors.Response Requested within 45 Days of Ltr Date Project stage: RAI ML20214K7671986-08-15015 August 1986 Responds to Kubicki 860708 Request for Clarification of Info Re Roof Steel Unprotected from Fire,Halon Fire Suppression Sys,Halon Concentration,Reserve Capacity of Halon Tanks, Discharge Tests & Test Points & Door & Damper Ratings Project stage: Request ML20214Q0701986-09-18018 September 1986 Safety Evaluation Supporting Proposed Records Storage Ctr & Deviations from NFPA Std 232 & ANSI N45.2-1974 Project stage: Approval ML20214Q0641986-09-18018 September 1986 Forwards Safety Evaluation Supporting Proposed Records Storage Ctr.Deviations from NFPA Std 232 & ANSI N45.2-1974 Acceptable Project stage: Approval ML20151X6031988-08-18018 August 1988 Requests Concurrence W/Util Proposal to Revise FSAR Section B.5.19.9 to Explicitly Exempt Records Ctr from Recommended 4 H Min Rating & Class a Designation,In Order to Resolve Deviation Noted in Insp Rept 50-267/85-16 Project stage: Other ML20154A6771988-09-0202 September 1988 Concurs W/Util That Requirements for 4-h Rating Unnecessary & Potentially Difficult to Implement.Util Commitment to 3-h Fire Rating for Structure,Doors,Frames & Hardware Acceptable Project stage: Other 1986-08-14
[Table View] |
|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20246J3261989-08-30030 August 1989 Safety Evaluation Supporting Amend 72 to License DPR-34 ML20245J3781989-08-14014 August 1989 Safety Evaluation Supporting Amend 71 to License DPR-34 ML20245J4511989-08-0808 August 1989 Safety Evaluation Responding to Issues Re Tech Spec Upgrade & Plant Defueling.Stated Tech Spec Sections Should Be Upgraded ML20246J3131989-07-0707 July 1989 Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable ML20247R2261989-05-26026 May 1989 Final Safety Evaluation Re LER 87-20 Concerning Interactions Between Steamline Rupture Detection/Isolation Sys,Plant Protective Sys & Control Sys at Facility ML20245C5031989-04-18018 April 1989 Safety Evaluation Supporting Amend 70 to License DPR-34 ML20248D6501989-03-31031 March 1989 Safety Evaluation Supporting Amend 69 to License DPR-34 ML20236A1401989-02-27027 February 1989 Safety Evaluation Supporting Amend 68 to License DPR-34 ML20235T4511989-02-24024 February 1989 Safety Evaluation Re Facility Core Support Flow Vent Sys. Continued Operation of Facility W/Current Core Support Flow Sys Configuration Acceptable ML20235J3421989-02-16016 February 1989 Safety Evaluation Supporting Util Action in Response to Generic Ltr 83-28,item 2.1 (Part 2) Confirming Establishment of Interface W/Either NSSS Vendor or Vendors of Each Component in Reactor Trip Sys ML20235J3841989-02-13013 February 1989 Safety Evaluation Concluding That Continued Operation of Facility Not Affected by Steam Generator Tube Failures Experienced by Advanced gas-cooled Reactors ML20195D3911988-10-27027 October 1988 Safety Evaluation Supporting Corrective Actions of LER 86-017 ML20205G0021988-10-24024 October 1988 Safety Evaluation Supporting Amend 65 to License DPR-34 ML20154J8021988-09-15015 September 1988 Safety Evaluation Supporting Amend 64 to License DPR-34 ML20154J4621988-09-15015 September 1988 Safety Evaluation Supporting Amend 63 to License DPR-34 ML20207F0571988-08-10010 August 1988 Safety Evaluation Supporting Util 870206 Submittal Re Safe Shutdowns During Postulated Accident Conditions ML20207F0431988-08-0505 August 1988 Safety Evaluation Supporting Amend 61 to License DPR-34 ML20207F2411988-08-0505 August 1988 Safety Evaluation Supporting Amend 62 to License DPR-34 ML20151M1601988-07-21021 July 1988 Safety Evaluating Supporting Requirements for Redundancy in Responding to Rapid Depressurization Accident ML20151A9961988-06-20020 June 1988 Safety Evaluation Supporting Amend 60 to License DPR-34 ML20195K0651988-06-15015 June 1988 SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Rept of Helium Circulator S/N 2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities ML20195F9661988-06-15015 June 1988 Safety Evaluation Re Destructive Exam Rept for Fuel Test Assembly-2.Fuel Represented by Fuel Test Assembly-2 Predicted to Be Safe for Operation in Facility for 1,800 EFPDs ML20154F8891988-05-10010 May 1988 Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R.Licensee Request for Exemptions in Listed Areas Should Be Granted.Concept for Providing post-fire Shutdown Acceptable ML20148S6031988-04-0707 April 1988 Safety Evaluation Supporting Amend 59 to License DPR-34 ML20151B6651988-04-0101 April 1988 Supplemental Safety Evaluation Supporting Util Compliance w/10CFR50.App R Re Safe Shutdown DHR Capacity ML20150C4541988-03-10010 March 1988 Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg ML20147C8181988-02-25025 February 1988 Safety Evaluation Supporting Changes to Interim Tech Specs 3/4.1.7, Reactivity Change W/Temp NUREG-1220, Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures1988-01-13013 January 1988 Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures ML20237D7631987-12-18018 December 1987 Safety Evaluation Updating 861118 Fire Protection Sys Safety Evaluation.Util Alternate Fire Protection Configuration Acceptable ML20149E1621987-12-18018 December 1987 Marked-up Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R ML20236U6961987-11-23023 November 1987 Safety Evaluation Supporting Amend 57 to License DPR-34. Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise,Limiting Condition for Operation..., Technical Evaluation Rept Encl ML20236U5761987-11-20020 November 1987 Safety Evaluation Re Helium Circulator S/N C-2101 Damage. Util Corrective Action Program Initiated ML20236R3001987-11-13013 November 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20238C7621987-09-0202 September 1987 Safety Evaluation Concurring W/Util 870702 & 27 Ltrs & 870818 Telcon Re Elimination or Reduction of Maint Requirements on Certain Fire Seals ML20235N6491987-07-13013 July 1987 Safety Evaluation Supporting Amend 56 to License DPR-34 ML20235F5281987-07-0202 July 1987 Safety Evaluation Re Safe Shutdown of Steam Generator Matls. Under Severe Transient Conditions,Fuel Temp Can Be Maintained Under Accepted Temp Limits & Plant Can Be Safely Shutdown ML20235F5151987-07-0202 July 1987 Safety Evaluation Re Safe Emergency Shutdown of Reactor Sys. Operation at 82% Acceptable ML20235F5441987-07-0202 July 1987 Safety Evaluation Re Effect of Firewater Cooldown on Steam Generator Structural Integrity.All Tests Acceptable ML20235E5281987-06-29029 June 1987 Safety Evaluation Supporting Amend 55 to License DPR-34 ML20216G9511987-06-24024 June 1987 Revised Safety Evaluation Re Steam Line Rupture Detection & Isolation Sys (Slrdis).Slrdis Meets Requirements of 10CFR50, App A,Gdc 20 & GDC 4 ML20216G9911987-06-24024 June 1987 Supplemental Safety Evaluation Supporting Application for Amend to License DPR-34 Re Tech Specs for Steam Line Rupture Detection & Isolation Sys ML20215J5401987-06-22022 June 1987 Draft Safety Evaluation Re Safe Emergency Shutdowns.Facility Operation at 82% Power Acceptable ML20216J1921987-06-17017 June 1987 Safety Evaluation Re Mods to Reduce Moisture Ingress Into Reactor Vessel.Periodic Insps & Preventive Maint Should Be Performed on Pertinent Components.Operational Performance Should Be Continuously Upgraded ML20214M4681987-05-20020 May 1987 Safety Evaluation Supporting Amend 54 to License DPR-34 ML20215J8271987-05-0505 May 1987 Safety Evaluation Supporting Amend 53 to License DPR-34 ML20209D7561987-04-22022 April 1987 Safety Evaluation Supporting Util 870211 Submittal Re Performance Enhancement Program,Finding 4-10 ML20206J9331987-04-0606 April 1987 Safety Evaluation Supporting Amend 52 to License DPR-34 ML20205S1141987-03-31031 March 1987 Safety Evaluation Accepting Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing. Facility Designed to Permit on-line Functional Testing,Including Testing of Reactor Trip Contactors 1997-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
Text
, J .n..
jt !og UNITED STATES
- g NUCLEAR REGULATORY COMMISSION 5 ij WASHINGTON, D. C. 20555
...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO PROPOSED RECORD STORAGE CENTER PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267
1.0 INTRODUCTION
The licensee plans to build a new Record Storage Center adjacent to the existing record storage office. By letter dated April 25, 1986, the licensee requested approval of ten deviations to the codes and standards that ensure adequate protection of the documents to be contained in this new Record Storage Center. The specific codes and standards for which a the licensee requested deviations are National Fire Protection Association (NFPA) Standard No. 232 (which pertains to fire protection for record storage facilities) and ANSI N45.2.9-1974 (which pertains to
, collection, storage, and maintenance of Quality Assurance records). Both of these standards are referenced in NRC Standard Review Plan a (NUREG-0800) Section 17.1.17.4.
2.0 EVALUATION 2.1 Fire Protection y After reviewing the licensee's deviation requests related to fire protection, the staff expressed concern regarding the fire resistance of the exterior walls and ceiling / roof assembly, as well as the design for the automatic and manual fire protection systems. The licensee responded to these concerns by letter dated August 15,1986(P-86516). The exterior walls will be fire rated at two hours. In order to achieve this rating, the doors and dampers will be rated for three hours. The staff concludes that this level of fire resistance is sufficient to provide protection from any potential external exposure fire.
The ceiling / roof assembly will be supported by unprotected steel. The licensee responded to the staff's concern about the structural integrity of this steel during a fire exposure by describing the design of the proposed halon fire suppression system, fire detection and alarm system, and manual fire fighting equipment. The fire detection and alarm system will be designed in accordance with NFPA Standards Nos. 72D and 72E. The halon system will be designed in accordance with NFPA Standard No. 12A.
It will be capable of providing a sufficient concentration of halon gas to control any potential fire within the storage area, and is designed to 8609240164 860915 PDR ADOCK 05000267 F PDR l
l
d y ,
, have a 100% reserve supply of halon gas. Portable fire extinguishers will be provided in accordance with NFPA Standard No. 10. On this basis, the. staff concludes that an adequate level of fire protection will be provided to protect against a potential internal exposure fire.
2.2 Missile Generation ANSI N45.2.9-1974 states that permanent record storage facilities be so constructed as to protect their contents from possible destruction by causes such as fire, flooding, and tornados. The licensee requested a deviation from ANSI N45.2.9-1974 to build the new Record Storage Center to withstand winds with speeds up to 100 mph instead of tornado-force winds (windspeeds up to 300 mph). In view of the fact that the plant is designed to be capable of safe shutdown following a maximum tornado with a 300 mph total horizontal wind velocity, the staff requested that the licensee demonstrate that any missiles resulting from the failure of the
. Record Storage Center will not damage any Category I structure or safety 4
related equipment. In response to the staff's request, the licensee evaluated the potential tornado generated missiles and reported that
_ neither the weight nor shape of the potential missiles would exceed the FSV design missile (fir plank, 4" X 12" x 12 ft. long, weighing 105 lbs).
This missile was used as the design missile in determining the thickness requirement of the Prestressed Concrete Reactor Vessel shield deck structure. Since the existing non-Category I structures at the FSV plant are similar to the proposed storage facility, it can be concluded that no new credible potential missiles can be generated by a tornado and that the existing Category I structures will be adequately protected.
3.0 CONCLUSION
S The level of fire protection proposed by the licensee will achieve an equivalent level to that which would be achieved by complete compliance with NFPA Standard No. 232. Therefore, the licensee's request for deviations from this standard is acceptable.
Similarly, the licensee's request for a deviation from ANSI N45.2.9-1974 is acceptable because any missiles resulting from the failure of the new Record Storage Center will not damage any Category I structure or safety-related equipment.
Based on the above findings, the staff approves the ten deviation requests contained in the licensee's April 25, 1986 letter (P-86069) from D. Warembourg (PSC) to H. Berkow (NRC). With the exception of these ten deviations, the design of the new Record Storage Center will be in accordance with the NRC Standard Review Plan (NUREG-0800) Section 17.1.17.4 concerning the design of suitable facilities for the storage of Quality Assurance records.
Principal Contributors: D. Kubicki R. Lipinski Dated: September 18, 1986
_ _ _. -.__.__ . _ _ _