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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20078S4721995-02-15015 February 1995 Provides Update to Status of WNP-3 Project ML20069D0021994-05-17017 May 1994 Informs Board & Parties of Recent Developments Re WNP-3 Project ML20235B3621987-08-25025 August 1987 FOIA Request for Listed Documents for Specified Dockets ML20141D3441986-03-31031 March 1986 Concludes That Financial Info Submitted in Util Satisfies Requirements of 10CFR140.21 Re Licensee Maint of Approved Guarantee of Payment of Deferred Premiums ML20010H3481981-08-14014 August 1981 Responds to IE Bulletin 80-20, Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches. No Subj Switches Have Been Identified at Facilities.Util Awaits Info from GE for Final Resolution.Next Response by 811030 ML19260E0371980-01-28028 January 1980 Forwards Util 800123 News Releases.Utils Have Decided to Terminate Const Plans for Units.Reduced Load Growth Projections,Financial Constraints & Overregulation Cited as Contributing Factors ML19260E0101980-01-23023 January 1980 Forwards Util 800123 Press Release Re Termination of Plans to Build Four Addl Nuclear Units Presently in Design Stage. Const Will Continue on Two Units Near North Perry,Oh & One Near Shippingport,Pa ML20125D5911980-01-0808 January 1980 Discusses Recent Util Reorganization.Cw Frederickson Is Authorized Officer Responsible for Receipt & Transmittal of NRC Official Correspondence Re Facility.Bm Miller Authorized to Review & Approve Documents Re Licensing Application ML19253C9121979-12-0505 December 1979 Forwards 10-yr Forecast Rept to Be Used in Updating Plants Final Environ Statement.W/O Encl ML19254E1981979-10-24024 October 1979 Responds to 791010 Ltr Re Threatened & Endangered Species in Vicinity of Proposed Facility.Federal Law Requires Biological Assessment.Lists Info for Inclusion in Assessment ML19254D6791979-10-23023 October 1979 Responds to 791010 Ltr Re Followup Actions Resulting from NRC Reviews Re Tmi.Study of Scheduled Inservice Dates Continues.Licensing Manpower Reduced.Dates Cannot Now Be Amended to Include Six Items Noted in Ltr ML19289F5281979-06-0505 June 1979 Forwards PSAR Amend 22 Re Qa,In Response to NRC 790430 Ltr.Affidavit Encl ML19273B3991979-03-0707 March 1979 Applicants Request ASLB Attention to Recent & Subsequent Order of Aslab Which Bears Directly on Issue Presented in Order.Certificate of Svc Encl ML19276F5341979-03-0505 March 1979 Requests Convening of Radiological Health & Safety Phase of Const Permit Hearing.Related SER Suppl Was Issued in Jan. Certificate of Svc Encl ML19283B5751979-02-16016 February 1979 Ack Receipt of NRC 790131 Ltr.Util Feels Any Design & Initial Const Scheduled to Occur Between Now & 791101 Can Proceed W/O Precluding Possible Addition of ATWS Mitigating Equipment ML19256B1761979-01-0808 January 1979 Responds to NRC Request for Addl Info Re Tornado Missile Protection of Main Steam Lines.Info Deals W/Analysis of Automobile Impact on Main Steam Line Piping & Calculation of Restraint Barrier Stiffness ML19263A8921978-12-21021 December 1978 Discusses Schedule Changes in Const & Planning Studies.After Review,Util Concluded That Licensing Activities Re Pending Const Permit Application Should Continue Concurrently W/The Planning Studies ML20147H3541978-12-15015 December 1978 Responds to 781027 NRC Ltr by Forwarding Oec Commitment to Conform W/Nrc Cold Shutdown Design Requirements for Subj Facils. W/Encl Affidavit ML20148T4521978-12-0101 December 1978 Manager,Quality Assurance Dept Has Assumed the Duties of Previous Chief Nuc Qual Assurance Engineer & Responsibility for All non-nuc Quality Assurance.Forwards Clarification of Main Steam Valve Leak Rate Analysis ML20197C5201978-11-0707 November 1978 Forwards 780928 NRC Memo Discussing Results of Recent Underwriters Lab Fire Protec Res Test.W/Encl ANO:7811050359, 7811160004,7811060106,7811050373 ML20150C1721978-11-0606 November 1978 Proposes Steps Util Will Take to Resolve Areas of Discord Re 2nd Analysis of Probability of Unacceptable Conditions Occurring in Control Room as Result of Toxic Chem Spill Near Facil,Including Facil Design & Hazard Analysis ML20148H0621978-11-0303 November 1978 Responds to Expressing Concern Re Proposed Location of Subj Facil.Describes Lic Process ML20058A1431978-10-27027 October 1978 Forwards Util Responses to NRC Questions Re Financial Qualifications.Affidavit Requesting Withholding of Info Per 10CFR2.790 Also Encl ML20150B7411978-10-27027 October 1978 Forwards Requirements for Subj Facil Cold Shutdown.Req Comment Prior to Issuance of SER ML20197B6401978-10-18018 October 1978 Requests Viable Geographic Alternatives to Subj Facil & Any Info Re Evaluation Studies of Proposed Pwr Plant Sites ML20148H0691978-10-18018 October 1978 Believes There Must Be Viable Alternatives to Proposed Plant Location in Northern Oh ML20148A7631978-10-18018 October 1978 Advises That Const Schedules Currently Undergoing Review. Review Expected to Be Completed in Approx 30 Days. Certificate of Svc Encl ML20147E0791978-10-0909 October 1978 Forwards Addl Info for Sser Re Major Reorganization of Util. Senior Vice-President for Engineering & Const Responsible Fr All Engineering & Const Activities.Organizational Chart Encl ML20147C8781978-10-0606 October 1978 Forwards Info Which Is 780828 Suppl Testimony of L.Firestone Describing the Rev Capco Load Forecast as Submitted to Oh Pwr Siting Comm During State Cert Hearings for Subj Facil. Matl Was Previously Submitted Informally to Singh Bajwa,Nrc ML20204C7661978-08-17017 August 1978 Reports on 220th ACRS Meeting Held on 780803-05.Items Considered Incl:Review of Facils Requests for Constr Permit RESAR-414,CRAC Code Use ML19329C4541977-12-0808 December 1977 Requests Final Rept Re Davis Besse Shutdown Resulting from Release Valve Failure & NUREG 0337,DES for Erie Units 1 & 2 ML19329C6801974-11-0404 November 1974 Responds to AEC Notice Calling for Comment Re Anticompetitive Effects of CP on Behalf of City of Cleveland 1995-02-15
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20078S4721995-02-15015 February 1995 Provides Update to Status of WNP-3 Project ML20069D0021994-05-17017 May 1994 Informs Board & Parties of Recent Developments Re WNP-3 Project ML20235B3621987-08-25025 August 1987 FOIA Request for Listed Documents for Specified Dockets ML20010H3481981-08-14014 August 1981 Responds to IE Bulletin 80-20, Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches. No Subj Switches Have Been Identified at Facilities.Util Awaits Info from GE for Final Resolution.Next Response by 811030 ML19260E0371980-01-28028 January 1980 Forwards Util 800123 News Releases.Utils Have Decided to Terminate Const Plans for Units.Reduced Load Growth Projections,Financial Constraints & Overregulation Cited as Contributing Factors ML19260E0101980-01-23023 January 1980 Forwards Util 800123 Press Release Re Termination of Plans to Build Four Addl Nuclear Units Presently in Design Stage. Const Will Continue on Two Units Near North Perry,Oh & One Near Shippingport,Pa ML20125D5911980-01-0808 January 1980 Discusses Recent Util Reorganization.Cw Frederickson Is Authorized Officer Responsible for Receipt & Transmittal of NRC Official Correspondence Re Facility.Bm Miller Authorized to Review & Approve Documents Re Licensing Application ML19253C9121979-12-0505 December 1979 Forwards 10-yr Forecast Rept to Be Used in Updating Plants Final Environ Statement.W/O Encl ML19254E1981979-10-24024 October 1979 Responds to 791010 Ltr Re Threatened & Endangered Species in Vicinity of Proposed Facility.Federal Law Requires Biological Assessment.Lists Info for Inclusion in Assessment ML19254D6791979-10-23023 October 1979 Responds to 791010 Ltr Re Followup Actions Resulting from NRC Reviews Re Tmi.Study of Scheduled Inservice Dates Continues.Licensing Manpower Reduced.Dates Cannot Now Be Amended to Include Six Items Noted in Ltr ML19289F5281979-06-0505 June 1979 Forwards PSAR Amend 22 Re Qa,In Response to NRC 790430 Ltr.Affidavit Encl ML19273B3991979-03-0707 March 1979 Applicants Request ASLB Attention to Recent & Subsequent Order of Aslab Which Bears Directly on Issue Presented in Order.Certificate of Svc Encl ML19276F5341979-03-0505 March 1979 Requests Convening of Radiological Health & Safety Phase of Const Permit Hearing.Related SER Suppl Was Issued in Jan. Certificate of Svc Encl ML19283B5751979-02-16016 February 1979 Ack Receipt of NRC 790131 Ltr.Util Feels Any Design & Initial Const Scheduled to Occur Between Now & 791101 Can Proceed W/O Precluding Possible Addition of ATWS Mitigating Equipment ML19256B1761979-01-0808 January 1979 Responds to NRC Request for Addl Info Re Tornado Missile Protection of Main Steam Lines.Info Deals W/Analysis of Automobile Impact on Main Steam Line Piping & Calculation of Restraint Barrier Stiffness ML19263A8921978-12-21021 December 1978 Discusses Schedule Changes in Const & Planning Studies.After Review,Util Concluded That Licensing Activities Re Pending Const Permit Application Should Continue Concurrently W/The Planning Studies ML20147H3541978-12-15015 December 1978 Responds to 781027 NRC Ltr by Forwarding Oec Commitment to Conform W/Nrc Cold Shutdown Design Requirements for Subj Facils. W/Encl Affidavit ML20148T4521978-12-0101 December 1978 Manager,Quality Assurance Dept Has Assumed the Duties of Previous Chief Nuc Qual Assurance Engineer & Responsibility for All non-nuc Quality Assurance.Forwards Clarification of Main Steam Valve Leak Rate Analysis ML20150C1721978-11-0606 November 1978 Proposes Steps Util Will Take to Resolve Areas of Discord Re 2nd Analysis of Probability of Unacceptable Conditions Occurring in Control Room as Result of Toxic Chem Spill Near Facil,Including Facil Design & Hazard Analysis ML20058A1431978-10-27027 October 1978 Forwards Util Responses to NRC Questions Re Financial Qualifications.Affidavit Requesting Withholding of Info Per 10CFR2.790 Also Encl ML20148H0691978-10-18018 October 1978 Believes There Must Be Viable Alternatives to Proposed Plant Location in Northern Oh ML20197B6401978-10-18018 October 1978 Requests Viable Geographic Alternatives to Subj Facil & Any Info Re Evaluation Studies of Proposed Pwr Plant Sites ML20148A7631978-10-18018 October 1978 Advises That Const Schedules Currently Undergoing Review. Review Expected to Be Completed in Approx 30 Days. Certificate of Svc Encl ML20147E0791978-10-0909 October 1978 Forwards Addl Info for Sser Re Major Reorganization of Util. Senior Vice-President for Engineering & Const Responsible Fr All Engineering & Const Activities.Organizational Chart Encl ML20147C8781978-10-0606 October 1978 Forwards Info Which Is 780828 Suppl Testimony of L.Firestone Describing the Rev Capco Load Forecast as Submitted to Oh Pwr Siting Comm During State Cert Hearings for Subj Facil. Matl Was Previously Submitted Informally to Singh Bajwa,Nrc ML19329C4541977-12-0808 December 1977 Requests Final Rept Re Davis Besse Shutdown Resulting from Release Valve Failure & NUREG 0337,DES for Erie Units 1 & 2 ML19329C6801974-11-0404 November 1974 Responds to AEC Notice Calling for Comment Re Anticompetitive Effects of CP on Behalf of City of Cleveland 1995-02-15
[Table view] Category:UTILITY TO NRC
MONTHYEARML20235B3621987-08-25025 August 1987 FOIA Request for Listed Documents for Specified Dockets ML20010H3481981-08-14014 August 1981 Responds to IE Bulletin 80-20, Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches. No Subj Switches Have Been Identified at Facilities.Util Awaits Info from GE for Final Resolution.Next Response by 811030 ML20125D5911980-01-0808 January 1980 Discusses Recent Util Reorganization.Cw Frederickson Is Authorized Officer Responsible for Receipt & Transmittal of NRC Official Correspondence Re Facility.Bm Miller Authorized to Review & Approve Documents Re Licensing Application ML19253C9121979-12-0505 December 1979 Forwards 10-yr Forecast Rept to Be Used in Updating Plants Final Environ Statement.W/O Encl ML19254D6791979-10-23023 October 1979 Responds to 791010 Ltr Re Followup Actions Resulting from NRC Reviews Re Tmi.Study of Scheduled Inservice Dates Continues.Licensing Manpower Reduced.Dates Cannot Now Be Amended to Include Six Items Noted in Ltr ML19289F5281979-06-0505 June 1979 Forwards PSAR Amend 22 Re Qa,In Response to NRC 790430 Ltr.Affidavit Encl ML19283B5751979-02-16016 February 1979 Ack Receipt of NRC 790131 Ltr.Util Feels Any Design & Initial Const Scheduled to Occur Between Now & 791101 Can Proceed W/O Precluding Possible Addition of ATWS Mitigating Equipment ML19256B1761979-01-0808 January 1979 Responds to NRC Request for Addl Info Re Tornado Missile Protection of Main Steam Lines.Info Deals W/Analysis of Automobile Impact on Main Steam Line Piping & Calculation of Restraint Barrier Stiffness ML19263A8921978-12-21021 December 1978 Discusses Schedule Changes in Const & Planning Studies.After Review,Util Concluded That Licensing Activities Re Pending Const Permit Application Should Continue Concurrently W/The Planning Studies ML20147H3541978-12-15015 December 1978 Responds to 781027 NRC Ltr by Forwarding Oec Commitment to Conform W/Nrc Cold Shutdown Design Requirements for Subj Facils. W/Encl Affidavit ML20148T4521978-12-0101 December 1978 Manager,Quality Assurance Dept Has Assumed the Duties of Previous Chief Nuc Qual Assurance Engineer & Responsibility for All non-nuc Quality Assurance.Forwards Clarification of Main Steam Valve Leak Rate Analysis ML20150C1721978-11-0606 November 1978 Proposes Steps Util Will Take to Resolve Areas of Discord Re 2nd Analysis of Probability of Unacceptable Conditions Occurring in Control Room as Result of Toxic Chem Spill Near Facil,Including Facil Design & Hazard Analysis ML20147E0791978-10-0909 October 1978 Forwards Addl Info for Sser Re Major Reorganization of Util. Senior Vice-President for Engineering & Const Responsible Fr All Engineering & Const Activities.Organizational Chart Encl ML20147C8781978-10-0606 October 1978 Forwards Info Which Is 780828 Suppl Testimony of L.Firestone Describing the Rev Capco Load Forecast as Submitted to Oh Pwr Siting Comm During State Cert Hearings for Subj Facil. Matl Was Previously Submitted Informally to Singh Bajwa,Nrc 1987-08-25
[Table view] |
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a
- s s O OHIO EDISON COMPANY 76 SOUTH MAIN STREET, AKRON, OHIO 44308 216-384-5918
""'"[/;,",l1",""" January 8, 1979 Mr. Roger S. Boyd, Director Division of Project Management U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Erie Nuclear Plant, Units 1 & 2 USNRC Docket Nos. STN50-580 and STN50-581 Additional Information for SER Supplement
Dear Mr. Boyd:
In a letter from Lynn Firestone to you dated September 14, 1978, information was submitted to address SER Outstanding Issue 2 concerning tornado missile protection of the main steam lines. After reviewing the above information, the NRC staff requested further clarification in order to complete their review.
The requested information is enclosed and deals with two topics. The first topic is an analysis of the automobile impact on the main steam line piping. The second topic is a calculation of the restraint barrier stiffness. Details are provided to substantiate the stiffness values transmitted previously.
It is our understanding that the submittal of the enclosed information resolves all outstanding issues which have delayed iscuance of the Safety Evaluation Report. If this 4 3 incorrect, please advise.
Very truly yours,
/c//c , hW lWvtW RJM/ROR:jmm Enclosure cc: See Attached Distribution List
6
A, [ [ I, p, A.,,11 T, STATE OF OHIO )
SS.
SUMMIT COUNTY On January 8, 1979, before me, a Notary Public in and for the State and County aforesaid, personally appeared Robert J. McWhorter, who after being sworn according to law, deposed and said that he is Vice President and an Officer of Ohio Edison Company, an Ohio corporation, that in such capacities he is authorized to make this Affidavit; and that the foregoing is true and correct to the best of his knowledge, informa-tion, and belief.
/Pr/r # h 31 T (( S M Robert J. McWhorter Sworn to and subscribed before me the day and year aforesaid.
f Notary Public JOSEPHINE M. ftELROY I'OTAiY PU3LIC - STATE OF CH!O RES! DENT OF SUI.!TAl! COUtiTY fly Commisdon Expires Au217,1932
Distribution List ec: DWHayes (USNRC OIE:III)
RThoma (Oak Ridge National Lab)
HKohn (OPSC)
JAckerman (Ohio Dept. of Health)
PGasteier (Erie County Commissioner)
RLMuctard (USEPA, Chicago)
Librarian /ThermalReactorsGroup (Brookhaven National Lab)
Atomic Industrial Forum GCharnoff (SPPT)
EStebbins RTufts
Overall Structural Response of Pioing Due to Automobile Impact The automobile is the largest tornado missile and contains the most kinetic energy. However since much of the energy is lost in the de-formation of the automobile upon impact with the piping, the overall structural damage is less severe thar. that of the 12" pipe, in fact the elastic limits of the pipe material are not even exceeded. A time history dynamic analysis is presented here to show this.
The applied force time history for the automobile crash is taken from a topical report " Design of Structures for 14issile Impact", BC-TOP-9A, Rev. 2, Sept. ,1974. Subsection 5.1 of that report gives a force time history as follows (with Erie Nuclear values for the automobile inserted):
F(t) = 485.0 sin 20t (Kips) O s t s 0.0785 sec.
F(t) = 0 - 0.0785 sec < t where: F(t) is the force on the target and t is the time from the instant of initial contact.
The automobile impacts directly upon the main steam line piping which in turn transmits the load through the adjacent pipe restraint barrier to the Auxiliary Building. The main steam line piping and adjacent barrier are considered as a single degree of freedom system with stiffness, K, and effective mass, M . The system is the same as that used in the energy balance method
- however only the elastic portion of the system is needed since the yield point of the pipe material is not exceeded.
1
The equation of motion for the main steam line piping is ME + Kx = F(t) where: M is the combined mass of the automobile, main steam line piping and restraint barrier, K is the stiffness of the main steam line piping and restraint barrier, and F(t) is the force as defined above.
Boundary conditions are x = x = 0 at t=0 The solution to this equation for t 10.0785 sec. is, x= 485.0 1 E
" 2 (sin 20 t
The solution to the equation for t >0.0785 sec. is, x = A sin (wt + B) where A = 485.0 M 2 1
3 _ m40 sin 40E + 400 g- 400 2 w
~
mu '20 B = arccos sin 40 - w 40 nw 400 1-o sin 40 + g 2
The maximum deflection of the system is 6
max
A Consider the case of the automobile impacting the main steam line in the middle of a 6.5 foot span. The stiffness of the pipe is 456,000 Kip /ft and the stiffness of the barrier is 110,000 Kip /ft giving a combined Kip /ft. The effective mass of the pipe and barrier stiffnessof89,00g/ft are20.0960 Kip sec and the mass of the automobile is 0.125 Kip sec /ft. The natural frequency of the combined system is e = VK/M
634.60 rad /sec. The maximum deflection is:
6 max
= 0.005528 ft.
2
This deflection produces a stress which is within the yield limit of the material and shows that the impact of the automobile do,1 not stress the main steam line piping and restraint barrier beyond the elastic region.
This is because most of the initial kinetic energy of the automobile is lost in its own crushing on impact. Therefore the automobile missile is much less severe than the 12" pipe, the worst non-deformable missile.
As discussed.in the September 14, 1978 letter, additional conservative effects not considered in this analysis include: (1) the reduction in the missile velocity when the missile perforates the protective enclosures for the pipe, (2) the 1.5 inch gap between the pipe and the barrier which allows the pipe to absorb energy over long spans, (3) the 30 percent reduction in missile velocity for missiles striking from the vertical direction, and (4) the initial stress in the pipe due to internal steam pressure. The consideration of these effects will tend to reduce the damage to the main steam lines.
Calculation of Barrier Stiffness The information requested on barrier stiffness is of such detail that it would not normally be supplied in an SAR. The following is a summary of the analysis necessary to calculate stiffness. Drawings of the barrier have not been finalized at this date and therefore are not transmitted.
In addition, standard techniques to calculate beam stiffness and cc.nbined stiffness are not given in detail.
- 1. Vertical segment of pipe The stiffest segment of barrier adjacent to the vertical pipe is near the header at the bottom of the vertical run. In this region the pipe runs parallel to a vertical beam which is supported at 15 feet intervals.
Shims are placed over this beam at 8 foot intervals at the location of the horizontal crcss beams. When the pipe impacts the barrier these shims are the points of contact. The pipe and barrier are sketched below.
Barrier bean - W24X162 2'
Shim
( N 8' r ss beans 4-1 Pipe
~
o 5'
Points assumed rigid 3
Stiffness of the beam at the upper cross beam is 600,000 Kip /ft.
Stiffness of the beam at the lower cross beam is 85,000 Kip /ft.
The stiffness of a point midway between the two cross beams is approximately 300,000 Kip /ft.
Therefore if the pipe is loaded midway between cross beams the net stiffness is the stiffness of the pipe, 245,000 Kips /ft, combined with the stiffness of the barrier, 300,000 Kip /ft. The net stiffness is 135,000 Kips /f t.
- 2. Horizontal segment of pipe Over the Auxiliary Building roof the main steam lines are perpendicular to cross beams spaced at 7.0 foot or 6.5 foot intervals. When the pipe contacts and loads the barrier these cross beams are loaded at a point either 5 feet or 10.5 feet from an end depending on which pipe is hit.
10.5'
- 6. 5 '__ _ 5 '__
Pipe Barrier beam L!24X162 Points assumed rigid The stiffness of the beam under the pipe 5' from the end is 55,000 Kip /ft which is the stiffer of the two locations.
The net stiffness of the barrier is the sum of two cross beams acting together which is 110,000 Cip/ft. When the pipe is loaded midway between cross beams the stiffness of the system is the combination of the pipe stiffness, 456,000 Kip /ft and the barrier stiffness, 110,000 Kip /ft.
This net stiffness is 89,000 Kip /ft.
4