SER Supporting Integrated Plant Safety Assessment Rept NUREG-0824 Sections,Including Flooding Elevation & Roofs, Provided Fire Pump House Blockwalls Adequate to Resist Flood LoadsML20138A784 |
Person / Time |
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Site: |
Millstone ![Dominion icon.png](/w/images/b/b0/Dominion_icon.png) |
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Issue date: |
10/07/1985 |
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From: |
NRC |
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To: |
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Shared Package |
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ML20138A777 |
List: |
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References |
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RTR-NUREG-0824, RTR-NUREG-824 NUDOCS 8510110086 |
Download: ML20138A784 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 ML20204H7131999-03-17017 March 1999 Safety Evaluation Concluding That NNECO Provided Adequate Justification for Deviations from RG 1.97,Rev 2, Recommendations,For Instrumentation Monitoring CST Level & Containment Area Radiation at Mnps Unit 2 ML20204C9441999-03-10010 March 1999 Safety Evaluation Denying Licensee Request for License Amend to Revise Frequency of Certain SRs for Electrical Power Sys ML20207L2631999-03-0505 March 1999 Safety Evaluation Supporting Amend 104 to License DPR-21 ML20207L5961999-02-22022 February 1999 Safety Evaluation Concluding That Code Requirements,Which Require 100 Percent Volumetric Exam of RPV flange-to-shell, Impractical to Perform to Extent Required & That Alternative Provide Reasonable Assurance of Structural Integrity ML20203D7601999-02-11011 February 1999 Safety Evaluation Supporting Millstone 1 Certified Fuel Handler Training & Retraining Program ML20196B0501998-11-24024 November 1998 Safety Evaluation Re Licensee 960213 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Unit 2 ML20155K1981998-11-0909 November 1998 Safety Evaluation Re Application of leak-before-break Status to Portions of Safety Injection & Shutdown Cooling Sys ML20195B8711998-11-0909 November 1998 Safety Evaluation Approving Revised Evaluation of Primary Cold Leg Piping leak-before-break Analysis for Plant ML20155C3781998-10-30030 October 1998 SER Denying Amend to Allow Changes to Fsar.Nrc Found That NNECO Had Not Considered Diversity Provided by Switch in Control Room That Removes Power to 1 of 2 MOV in SDC Sys Flow Path in Evaluation of High Low Pressure Design ML20155C8441998-10-29029 October 1998 Safety Evaluation Accepting Licensee Proposal to Withdraw ATWS Test Commitment ML20238F2781998-08-27027 August 1998 SER Related to Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept for Millstone Nuclear Power Station,Units 1,2 & 3 ML20237D5001998-08-20020 August 1998 SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements,Or Mods,Section Xi,Div 1 ML20236U7051998-07-22022 July 1998 Safety Evaluation Granting All Requests for Relief W/Exception of Requests RR-89-17 (Authorized for Class 1 Sys Only) & RR-89-21.Requests RR-13 & RR-14 Will Be Addressed in Separate Evaluation ML20236K6971998-07-0101 July 1998 SER Accepting Third 10-year Interval Inservice Insp Program Plan,Rev 2 & Associated Request for Relief & Proposed Alternatives for Plant,Unit 2 ML20236K3531998-07-0101 July 1998 Safety Evaluation Supporting Amend 218 to License DPR-65 ML20249C2541998-06-24024 June 1998 Safety Evaluation Accepting Proposed Rev 19 to NNECO QAP Topical Rept & Amended Through 980609.Informs That NNECO Exception to Provisions in Paragraph 10.3.5 of Constitutes Temporary & Acceptable Alternative ML20248J0031998-06-0404 June 1998 Safety Evaluation Accepting Millstone Nuclear Power Station Emergency Plan ML20248M2991998-06-0202 June 1998 Safety Evaluation Approving Application Re Restructuring of Central Maine Power Co by Establishment of Holding Company ML20248C4131998-05-26026 May 1998 SER of Individual Plant Exam of External Events Submittal on Millstone Nuclear Power Station,Unit 3 ML20217M4181998-04-30030 April 1998 Suppl Safety Evaluation Accepting Licensee RCS Pressure & Heat Removal by Containment Heat Removal Sys post-accident Monitoring Instrumentation ML20216G7921998-03-13013 March 1998 Safety Evaluation Authorizing Proposed Alternative to Check Valve Obturator Movement Requirements of OM-10 for SIL Accumulator Outlet for Listed Check Valves ML20203E8521998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(f) for Performing Required Inservice Testing of Certain Class 2 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E9341998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E2441998-02-0909 February 1998 Safety Evaluation Accepting Re Approval of Realistic,Median Centered Spectra Generated for Resolution of USI-A-46 ML20198R9941998-01-13013 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Millstone Nuclear Power Station,Unit 3 ML20202H7461997-12-10010 December 1997 Safety Evaluation Accepting Licensee Position That Correction of AC-11 Single Failure Vulnerability Unncessary ML20202J0911997-12-0202 December 1997 Safety Evaluation Accepting Proposed Exemption,Which Meets Special Circumstance Given in 10CFR50.12(a)(2)(ii) ML20198S2411997-10-31031 October 1997 SE Accepting Licensee Request for Deviations from Recommendations in Reg Guide 1.97,Rev 2 for Temp & Flow Monitoring Instrumentation for Cooling Water to ESF Sys Components & Containment Isolation Valve Position ML20212G5991997-10-27027 October 1997 Safety Evaluation Supporting Amend 103 to License DPR-21 ML20217K8801997-10-27027 October 1997 Correction to Safety Evaluation Supporting Amend 103 to License DPR-21.Phrase or Rod Block Protection Has Been Deleted from Listed Sentence in Staff Associated SE ML20212F1381997-10-22022 October 1997 Safety Evaluation Supporting Amend 102 to License DPR-21 ML20217M9301997-08-19019 August 1997 Safety Evaluation Accepting Continued Operation W/O High Startup Rate Trip by Nene for Millstone,Unit 2 ML20149J2661997-07-23023 July 1997 Safety Evaluation Accepting Changes & Reanalyses in ECCS Evaluation Models & Application of Models for Plant,Unit 2 ML20141L8821997-05-28028 May 1997 Safety Evaluation Supporting Amend 101 to License DPR-21 ML20138A0111997-04-23023 April 1997 Safety Evaluation Accepting Licensee Proposal,Not to Perform Type C Leakage Rate Testing on 14 Subject CIVs ML20137V5931997-04-15015 April 1997 Safety Evaluation Supporting Amend 100 to License DPR-21 ML20137U3121997-04-10010 April 1997 Safety Evaluation Supporting Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20134A0331997-01-23023 January 1997 Safety Evaluation Accepting Util Proposed Alternatives to ASME Code Requirements ML20133N3401997-01-14014 January 1997 Safety Evaluation Supporting Amend 98 to License DPR-21 ML20135C4221996-12-0202 December 1996 Safety Evaluation Accepting Proposed Alternative Described in Relief Request R-1 Re Valve Inservice Testing Program at Facility ML20128P4381996-10-0909 October 1996 Safety Evaluation Accepting Review of Cracked Weld Operability Calculations & Staff Response to NRC Task Interference Agreement ML20128L7541996-10-0404 October 1996 Safety Evaluation Supporting Amend 97 to License DPR-21 ML20248C5451995-05-0202 May 1995 SER on Millstone Unit 3 Individual Plant Exam of External Events to Identify plant-specific Vulnerabilities,If Any,To Severe Accidents & Rept Results Together W/Any licensee-determined Improvements & C/A to Commission ML20248C5731994-07-19019 July 1994 SER Step 1 Review of Individual Plant Exam of External Fire Events for Millstone Unit 3 ML20059H4991994-01-24024 January 1994 Safety Evaluation Accepting Revised Responses to IEB-80-04 Re MSLB Reanalysis 1999-08-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
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SAFETY EVALUATION REPORT IPSAR SECTIONS 4.1.1, FLOODING ELEVATION; 4.1.7, ROOFS 4.5.1, FLOOD ELEVATION; 4.5.2, GROUNDWATER; 4.6.1, DEFICIENCIES NOTED DURING SITE VISIT MILLSTONE UNIT I I
] 1. INTRODUCTION The Integrated Plant Safety Assessment Report (IPSAR) for Millstone 1 (NUPEG-0824) identified areas related to new design basis flood levels, gra water and probable maximum precipitation where Millstone 1 did not c .rm to present requirements. As described in the referenced
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cions of NUREG-0824, the licensee agreed to review the issues
( icentified and determine the appropriate corrective actions, if any.
_3 The licensee addressed each of the issues in submittals dated February 2, 1984 and March 16, 1984.
The issues identified in the IPSAR are as follows:
L Section 4.1.1,. Flooding Elevation - Probable Maximum Hurricane (PMH) g flood levels including wave effects resulted in a water level of .
3 22.3 ft ms1 (18.11 ft msl stillwater level plus wave action). Safety-related structures are protected to elevation 19.0 msl by concrete floodwalls. The licensee agreed to address the effects of water inleakage from waves overtopping the flood walls in this section and to address structural effects in Section 4.5.1.
Section 4.1.7, Roofs - The IPSAR concluded that roofs with parapets may be overstressed as a result of a local probable maximum precipitation (PMP).
Section 4.5.1, Flood Elevation - The issue identified in this section is identical to that identified in Section 4.1.1; however, the licensee has addressed the structural effects of the increased water level in this section and the inleakage from wave action overtopping
. the floodwalls in Section 4.1.1.
Section 4.5.2, Groundwater - The licensee has stated that plant structures were designed to resist hydrostatic and uplift forces resulting from groundwater rising to grade. The IPSAR requested the licensee to determine whether these loads were considered in the proper load combination.
Section 4.6.1, Deficiencies Noted During Site Visit - During a site visit, the staff noted that two of four roof drains on the turbine building were inoperable. The licensee addressed this issue as part of the roof analysis conducted for Section 4.1.7.
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II. EVALUATION Section 4.1.1, Flooding Elevation; 4.5.1, Flood Elevation The licensee has addressed both water inleakage from vave overtopping and structural effects from increased flood levels by relying on the isolation condenser as the primary method to achieve safe shutdown for flooding events. This method is described in detail in the licensee's letter dated December 2, 1983.
The isolation condenser is located in the upper levels of the reactor butidirg and can be operated independent of AC power. The licensee has proposed to use water from the firewater system to provide make-up
, to the shell side of the isolation condenser. Either one of two motor driven fire pumps or one diesel driven fire pump located in the fire pump house will be used to pump the water to the isolation condenser. One of the rotor driven pumps receives emergency AC power from Millstone 1 and the other from Hillstone 2. To protect s these pumps, the licensee has proposed to extend the east flood gate on the cump house to elevation 21.75 msl and seal it at the top of the door opening.
.An alternate source of make up would be available as part of the nodifications proposed to satisfy tornado missile concerns. The
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licensee has proposed to tie into the city water system and supply a portable enoine driven pump to be stored in the reactor building along with necessary hoses. This pump would be used to punp make-up water
~, from a connection in the city water system to the isolation condenser.
The staff concludes that in the event of a PMH, sufficient netbeds exist to safely shutdown Hillstone I with the modifications proposed by the licensee. Even if emergency AC power is lost, either one of twe diesel driven pumps would still be available to provide make-up from different sources to the isolation condenser. As noted in Section 4.1.5 of the IPSAP, the oil storage capacity for the diesel-driven firewater pump a11nws pump operation for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> before oil makeup from other sources would be necessary.
The staff finds this approach acceptable; however, the ifcensee should assure that the blockwalls of the fire pump house can resist the floodwater, including wave effects. In addition, as part of the ifcensee's implenentation of the plant modifications described above, the staff will require that the licensee make any necessary changes to the clant's energency procedures to reflect the safe shutdown capability for flooding events.
a Section 4.1.7, Roofs; 4.6.1, Deficiencies Noted During Site Visit The licensee analyzed the roofs of safety-related structures, where the roof was surrounded by a parapet, in order to determine whether the roof was capable of withstanding the load imparted by a water level equal to the parapet height. The evaluation was done by calculating the water level that would impart a load equal to the original design live load and then comparf ag this water level to the parapet height.
The analysis took no credit for roof drains.
The licensee concluded that the radwaste disposal building, the intake structure, the radwaste/ control building, the southwest corner of the reactor building and the gas turbine building roofs can support the loads imparted by a local Probable Maximum Precipitation (PMP) resulting in water to the top of the parapet. However, the licensee ccncluded that the turbine building, the reactor building, warehouse, and HVAC area roofs cannot withstand the PMP loads. For t'hese buildings, the ,
licensee proposes to install scuppers at a height which will limit the maximum water depth to a level which maintains the load below the original design live load.
The staff concludes that properly installed scuppers will adequately limit roof ponding loads and, therefore, finds the licensee's proposal acceptable.
Section 4.5.2, Groundwater To address this issue, the licensee analyzed the reactor building for uplift forces and horizontal forces from soil, groundwater and earthquake loadings. The load combinations chosen were nomal dead and live loads including lateral earth pressure with the associated load factors and the extreme environmental loading which includes earthquake forces.
The structure was found to be adequate for uplift as well as for horizontal forces.
After reviewing the analysis, the staff notes that only inertial forces from the buoyant weight of the soil were included and that inertial forces from the groundwater were not. These forces would tend to increase the load on the wall where the factor of safety in the vertical direction has been calculated to be 1.04. Additionally, while selecting the reactor building for investigation because of its large embedment was prudent, it is also the most substantial structure on the site. Demonstrating adequacy for the reactor building does not necessarily demonstrate adequacy for all structures.
The reference 9 (ASCE-Manuals and Reports on Engineering Practice -
No. 58, " Structural Analysis and Design of Nuclear Power Plant Facilities) cited in the licensee's analysis report (02-0240-1141) concludes that the solution of soil-structure interaction problems to obtain dynamic earth pressure is warranted for Category 1 structures.
For less important structures and for a preliminary estimate of the
- , . , - _ . , . , - . , - ,--_.n. -, ,
dynamic earth pressure on Category I structures, the Mononobe-Okabe method and methods based on elastic theory can be 'ased. Thus, the simplified methods in Reference 9 should demonstrate ample margins to cover possible uncertainties introduced by using a simplified method; if ample margins do not exist, a more refined method should be used.
In view of the minimal margin of safety calculated for the reactor building and the lack of groundwater inertial forces, the staff believes that a more refined analysis should be performed to confirm an adequate margin of safety with respect to the ability of the reactor building to resist groundwater loads. In addition, the staff believes that additional simplified analyses should similarly be conducted to demonstrate the adequacy of other Category I structures.
The issue of groundwater loads in combination with other loads (e.g.,
seismic) will be addressed in the staff's evaluation of the licensee's Integrated Structural Assessment Program under ISAP Topic 1.19 and IPSAR Section 4.12. For that evaluation, assuming the groundwater level at grade would be ultimately conservative; a more appropriate level can be established from site measurements.
III. CONCLUSIONS The staff finds the licensee's comitment to modify the fire pump house to assure a source of make-up water to the isolation condenser acceptable as a method of shutting down the facility in the event of flooding conditions. However, to assure that the fire pump house will remain water tight, the licensee should analyze the blockwalls of the fire pump house for floodwater, including wave effects. In addition, the licensee should modify the emergency procedures, as necessary, to reflect these shutdown provisions.
The staff finds the proposal to instal,1 scuppers on the roofs of the turbine building, reactor building, warehouse, and HVAC area to be an acceptable way of limiting roof loads, imposed by standing water from the PMP.
The staff recomends that the licensee perform additional analyses to confirm a margin of safety for groundwater loads in Category I structures.
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