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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20058K1391993-12-0606 December 1993 Safety Evaluation Supporting Amend 193 to License NPF-1 ML20057D9951993-09-30030 September 1993 Safety Evaluation Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Plant ML20057D0791993-09-22022 September 1993 Safety Evaluation Supporting Amend 192 to License NPF-1 ML20127P5801993-01-26026 January 1993 Safety Evaluation Supporting Amend 189 to License NPF-1 ML20125B8071992-12-0404 December 1992 Safety Evaluation Supporting Amend 188 to License NPF-1 ML20127L4221992-11-19019 November 1992 SE Accepting IST Program Requests for Relief for Pumps & Valves ML20059D1031990-08-30030 August 1990 SER Accepting Util 880311,0401 & 1223 & 900319 & 0622 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20059C7981990-08-27027 August 1990 Safety Evaluation Supporting Amend 162 to License NPF-1 ML20058L5641990-08-0202 August 1990 Safety Evaluation Concluding That Operable Instrumented Ammonia Detection Capability Unncessary for Protection of Control Room Personnel in Event of Spill of Anhydrous Ammonia in Vicinity of Plant ML20055C7531990-06-18018 June 1990 Safety Evaluation Supporting Amend 161 to License NPF-1 ML20245H4141989-08-10010 August 1989 Safety Evaluation Approving on-line Functional Testing of Reactor Trip Sys,Per Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20245E8091989-06-20020 June 1989 Safety Evaluation Supporting Amend 154 to License NPF-1 ML20247M9331989-05-24024 May 1989 Safety Evaluation Supporting Amend 153 to License NPF-1 ML20247H9571989-05-15015 May 1989 Safety Evaluation Supporting Amend 152 to License NPF-1 ML20247F1911989-03-17017 March 1989 Safety Evaluation Supporting Amend 151 to License NPF-1 ML20235T5351989-02-28028 February 1989 Safety Evaluation Supporting Amend 150 to License NPF-1 ML20151T4191988-08-0505 August 1988 Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures as Design Basis for Facility ML20151X8581988-08-0303 August 1988 Safety Evaluation Supporting Amend 149 to License NPF-1 ML20151H3041988-07-14014 July 1988 Safety Evaluation Supporting Amend 148 to License NPF-1 ML20151L4391988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20151E4551988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20196G0421988-06-23023 June 1988 Safety Evaluation Supporting Amend 145 to License NPF-1 ML20196C1571988-06-22022 June 1988 Safety Evaluation Supporting Amend 144 to License NPF-1 ML20196F9471988-06-16016 June 1988 Safety Evaluation Supporting Amend 143 to License NPF-1 ML20154D4931988-05-11011 May 1988 Safety Evaluation Supporting Amend 142 to License NPF-1 ML20154A1151988-05-0303 May 1988 Safety Evaluation Supporting Amend 141 to License NPF-1 ML20148S6491988-04-11011 April 1988 Safety Evaluation Supporting Amend 140 to License NPF-1 ML20151B3821988-03-31031 March 1988 Safety Evaluation Supporting Amend 139 to License NPF-1 ML20236X5311987-12-0101 December 1987 Safety Evaluation Supporting Amend 137 to License NPF-1 ML20236S4021987-11-12012 November 1987 Safety Evaluation Supporting Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Fire Protection of Safe Shutdown Capability Requirements ML20236M8711987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Accumulator Fill Line Failures ML20236M8551987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Main Feedwater Line Restraint Failure ML20236M9931987-11-0909 November 1987 Safety Evaluation Supporting Amend 136 to License NPF-1 ML20236A9151987-10-13013 October 1987 Safety Evaluation Concluding That Corrective Actions for Design Deficiencies in Main Steam Line Pipe Supports Adequate & Acceptable & That Commencement of Heatup & Return to Power Safe ML20235V6121987-10-0202 October 1987 Safety Evaluation Supporting Amend 135 to License NPF-1 ML20238B0181987-09-0101 September 1987 Safety Evaluation Supporting Amend 134 to License NPF-1 ML20237G8351987-08-25025 August 1987 Safety Evaluation Re Util 870723 Request for Relief from 4 H Test Pressure Hold Time Requirement of Section XI of ASME Code,1974 Edition Through Summer 1975 Addenda ML20237G8421987-08-24024 August 1987 Safety Evaluation Re Ultrasonic Insp of RCS hot-leg Elbow (Loop B).Ultrasonic Exam Performed Acceptable W/Exception of Ultrasonic Beam Spread Correction Procedures Used to Estimate Indication Size.Continued Operation Permissible ML20236P6731987-08-0707 August 1987 Safety Evaluation Supporting Amend 133 to License NPF-1 ML20236H5581987-07-30030 July 1987 Safety Evaluation Supporting Amend 132 to License NPF-1 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210F8701999-07-22022 July 1999 Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar ML20209C6531999-07-0606 July 1999 Rev 8 to Defueled SAR, for Trojan Nuclear Plant ML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20207G9881999-03-0303 March 1999 Rev 6 to Trojan Nuclear Plant Decommissioning Plan ML20207J0781999-02-28028 February 1999 Update to Trojan ISFSI Sar ML20202G4511999-02-0202 February 1999 Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar ML20207C6981998-12-31031 December 1998 1998 Annual Rept for Trojan Nuclear Plant. with ML20195J2501998-11-17017 November 1998 Rev 7 to Trojan Nuclear Plant Defueled Sar ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20155E0411998-10-27027 October 1998 Amend 7 to Quality-Related List Classification Criteria for Tnp ML20154R4121998-10-0202 October 1998 Requests Commission Approval,By Negative Consent,For Staff to Grant Two Specific Exemptions from Package Test Requirement Specified in 10CFR71 for Trojan Reactor Vessel Package & to Authorize one-time Transport for Disposal ML20237B6121998-08-13013 August 1998 Revised Trojan Reactor Vessel Package Sar ML20151W5471998-08-13013 August 1998 Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant ML20236Y2691998-08-0808 August 1998 Revised Trojan Rv Package Sar ML20249B4081998-06-17017 June 1998 Rev 6 to Trojan Nuclear Plant Defueled Sar ML20203E6291998-02-28028 February 1998 Trojan Nuclear Plant Decommissioning Plan ML20198T1741998-01-0404 January 1998 Rev 5 to Trojan Nuclear Plant Decommissioning Plan ML20248K6891997-12-31031 December 1997 Enron 1997 Annual Rept ML20203J3821997-12-31031 December 1997 Annual Rept of Trojan Nuclear Plant for 1997 ML20248K6931997-12-31031 December 1997 Pacificorp 1997 Annual Rept. Financial Statements & Suppl Data for Years Ended Dec 1996 & 97 Also Encl ML20203B0341997-11-26026 November 1997 Rev 5 to Trojan Nuclear Plant Defueled Sar ML20199F8141997-10-21021 October 1997 Requests Approval of Staff Approach for Resolving Issues Re Waste Classification of Plant Rv ML20216F4291997-07-25025 July 1997 Requests Commission Approval of Staff Approach for Reviewing Request from Poge for one-time Shipment of Decommissioned Rv,Including Irradiated Internals to Disposal Site at Hanford Nuclear Reservation in Richland,Wa ML20141F2311997-06-24024 June 1997 Rev 3 to PGE-1061, Tnp Decommissioning Plan ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148E8631997-05-31031 May 1997 Amend 6 to PGE-1052, Quality-Related List Classification Criteria for Trojan Nuclear Plant ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20140D9451997-03-31031 March 1997 Tnp First Quarter 1997 Decommissioning Status Rept ML20137K5811997-03-31031 March 1997 SAR for Rv Package ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134B6231997-01-15015 January 1997 Draft Rev 3 of Proposed Change to Trojan Decommissioning Plan ML20217M2381996-12-31031 December 1996 Portland General Corp 1996 Annual Rept ML20217M2471996-12-31031 December 1996 Pacific Power & Light Co (Pacifcorp) 1996 Annual Rept ML20217M2551996-12-31031 December 1996 1996 Enron Annual Rept ML20135C3521996-12-31031 December 1996 Annual Rept of Trojan Nuclear Plant for 1996 ML20132G2831996-12-19019 December 1996 Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan ML20132H0011996-12-12012 December 1996 Rev 20 to PGE-8010, Portland General Electric Nuclear QA Program for Trojan Nuclear Plant ML20132B8491996-12-12012 December 1996 Rev 20 to PGE-8010, Trojan Nuclear Plant Nuclear QA Program ML20135B5241996-11-27027 November 1996 Rev 4 to Trojan Nuclear Plant Defueled Sar ML20135B5341996-11-25025 November 1996 Trojan ISFSI Safety Analysis Rept ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134K6621996-11-11011 November 1996 Decommissioning Plan,Tnp ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20134F4661996-10-30030 October 1996 Final Survey Rept for ISFSI Site for Trojan Nuclear Plant ML20134P4321996-09-30030 September 1996 Tnp Quarter Decommisioning Status Rept,Third Quarter 1996 ML20137K5321996-09-0505 September 1996 Rev 0 to H Analysis of Residue Protocol ML20137K5091996-06-28028 June 1996 Summary Rept Poge Tnp SFP Project 1999-07-06
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/ UNITED STATES
- j. ,g. NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
.e SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.154 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY l l'
THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT j DOCKET NO. 50-344 l l
1.0 INTRODUCTION
{
By letter dated September 2, 1988, Portland General Electric Company (PGE, the licensee) proposed a modification at Trojan Nuclear Plant that would result in an increase of up to 3 percent in lateral shear force for the Control Building walls. By a licensee change application (LCA 174) ;
dated February 10, 1989, PGE proposed a net 3 sercent increase in the t allowed lateral shear forces on any story of t1e Control-Auxiliary-Fuel Building Complex (the Complex). The staff reviewed the PGE proposal and raised some technical concerns. These were discussed during a telephone conference of February 8, 1989, and were addressed in a licensee submittal dated February 15, 1989.
2.0 EVALUATION t Section 5.7.2.2 of the Trojan Technical Specifications states the require-ments controlling modification to Category I structures for Trojan.
Specifically, Item (a) of Section 5.7.2.2 states one of the conditions barring structural modification to Categnry I structure as, "1 percent increase in lateral shear forces on any story of the Compicx". PGE proposed a modification to the ventilation system in the Control Building that would result in an increase of lateral shear fortes in excess of one percent for the walls supporting the roof of the building. Also, Section 5.7.2.2 allows an increase in equipment weight not to exceed 10 percent on a per story, per building basis. However, PGE cannot utilize this provision to accommodate the needed increase in equipment weight because there was originally minimal equipment weight contributing to the Control Building roof loads.
PGE has determined that current and future modifications would require consideration for a 3 percent increase in lateral shear forces for the walls in the Control Building, and that the value of increase in lateral shear force is directly proportional to the increase in weight.
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1 The licensee originally analyzed the structure utilizing the STARDYNE finite element computer code as documented in their report PGE-1020,
" Report on the Design Modification for Trojan Control Building, July 14, 1978." For the reevaluation, the licensee has increased all of the weights used in the original STARDYNE Code by 3 percent and has evaluated ,
the effects of these weight increases on the shear wall capacity-to-force i ratios, floor response spectra, and interstructure displacements. The ,
results of the reevaluation based on an effective increase by 3 percent of l all shear forces indicate that all of the structural components remain well within their allowable stresses and their load capacities are greater than their load demands.
The licensee has justified tne above assumed linear relationship between the weight increase and the equival.ent increase in lateral shear forces 1
based on an argument that the story shear forces are essentially a l function of the spectral acceleration and weight of the structure. The i licensee further states that the spectral acceleration depends on the period j (frequency) of the modes of vibration, and the first and second modes of ;
vibration control the overall structural responses in the north-south and j east-west directions. A 3 percent increase in weight will result in a 1.5 !
percent increase in the value of the fundamental period of the structure.
A check on the change in ground response spectra based on the 1.5 percent change in fundamental period of the structure (FSAR Figure 3.7-1) resulted j in nondetectable differences. Therefore, the licensee concluded that a direct relationship between the weight and the lateral shear forces is justifiable. The staff finds the above justification reasonable and convincing.
The licensee has determined that the controlling locations for the old !
and new evaluations of shear wall capacity-to-force ratios, when consider-ing the Operating Basis Earthquake (0BE) load combination, include the following wall components:
- a. Walls No. 6 and 8 between Elevation 45 and 61.
- b. Wall R at Elevation 93 along column line 46.
- c. Wall N between Elevations 61 and 93 and along column line 46.
Items (c) and (d) to Section 5.7.2.2 of the Trojan Technical Specifications identify limitations in displacements between the Control and Turbine Buildings. The licensee reported that the above limits are not exceeded by the pertinent relative displacements determined, based on the assumed increase in allowable lateral shear fcrces.
During its review, the staff requested the licensee to address three issues: (a) The effects of selecting a larger change in weight than currently identified and its effects on the fundamental frequency of the j structure, (b) the identification of the specific structural components
l that would be structurally modified to provide the ventilation requirements, and (c) an explanation of why the results were based on the OBE load combina- l tions rather then the SSE load combinations. PGE addressed these issues in !
their submittal of February 15, 1989, to the satisfaction of the staff. The licensee's identification of (from 1 percent to 3 percent) and planned current the very low and effectfuture of theload changes 3 percent weight change on the period of the structure and spectral accelerations i resolved the first issue. Also, the licensee has stated that no alteration :
of major structural members will take place and that planned attachments to !
structural members will follow the structural design requirements stated '
in Trojan's FSAR Section 3.8, " Design of Seismic Category I Structures." l This licensee commitment will be properly documented in a future FSAR. '
Finally, in responding to the last staff concern, the licensee stated ;
that the technical specifications original requirements limiting the lateral shear force increase to one percent resulted from an evaluation utilizing the OBE load combinations. The evaluation that considered the Safe Shutdown Earthquake (SSE) load combinations satisfied the capacity requirements stated in the Trojan FSAR. Since the licensee has demonstrated that the margins for the SSE are larger than those for the OBE, the staff considers the third concern resolved. '
Based on the foregoing considerations, the staff concludes that the effect of a 3 percent increase in weight to the Control Building roof could be reasonably accounted for by addition of 3 percent weight at all mass points in the STARDYNE Computer Code model. The results of the ,
evaluation of the proposed niodification have indicated that: (a) there is minimal effect on the seismic response characteristics of the structure, (b) there is essentially no change on the overall structural load demand for each structural component, and (c) the interstructural relative dis-la p(c) and cements (d) ofremain small Section to comply 5.7.2.2 of the with the related Trojan's T>chnicalrequirements of items Specifications.
Based on the evaluation of the licensee submittals, the supplementary information provided by the licensee and telephone discussions with the licensee which served to clarify some issues associated with this proposed activity, the staff concludes that the licensee's structural analyses of the applicable components are in compliance with the acceptance criteria set forth in the FSAR and consistent with current licensing practice.
Therefore, the licensee's proposed modification to the Control Building is acceptable, and the proposed technical specification change is acceptable.
3.0 CONTACT WITH STATE OFFICIAL The NRC staff has notified the Oregon Department of Energy of the proposed issuance of this amendment along with the proposed determination of no significant hazards consideration. No comments were received.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR Part 51.21,(51.31 and 51.35, an environmental 54 FR 24432) in assessment has been published
, June 7, 1989. Accordingly, based upon the environmental assessment, the Commission has determined that the issuance of the amendments will not have a significant effect on the quality of the human environment.
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations,and(3)theissuanceoftheamendmentwillnotbeinimical to the common defense and security or to the health and safety of the public.
PRINCIPAL CONTRIBUTORS: Frank Rinald' Roby Bevan Dated: June 20, 1989 i
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