Letter Sequence Request |
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Results
Other: 05000270/LER-1982-002, Forwards LER 82-002/01T-0.Detailed Event Analysis Encl, 05000270/LER-1982-002-01, /01T-0:on 820122,three Core Support Assembly Thermal Shield Bolts Found W/Heads Broken Off & Shock Pad Y-2 Attachment Bolts Discovered Broken.Caused by Intergranular Stress Corrosion Cracking.Pad Removed, ML17318A294, ML19240C002, ML19256A166, ML19256A171, ML19274D226, ML19274E547, ML19309G772, ML19317F583, ML19323D082, ML19323D085, ML19326A405, ML19326A415, ML19329A858, ML19329A909, ML19329A920, ML19329B774, ML19340E122, ML19345F245, ML19345F247, ML19345G512, ML20011B254, ML20023A486, ML20024E088, ML20028D207, ML20040H182, ML20040H185, ML20041C218, ML20041G421, ML20052F377, ML20052F389, ML20054C645, ML20054C957, ML20065B814, ML20073S274, ML20236J661
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MONTHYEARML19326A4051977-04-22022 April 1977 Grants Relief from ASME Requirements for Proposed Inservice Testing Program for Pumps & Valves for Defined Period of Time.Addl Info Needed for Request for Relief from ASME Code Requirements Under Section 4.0.5b of Tech Specs Project stage: Other ML19326A4091977-04-22022 April 1977 NRC Guidance for Complying W/Certain Provisions of 10CFR50. 55a(g), Inservice Insp Requirements. List of Info Required for NRC Review of Inservice Insp Review & Testing Program Encl Project stage: Approval ML19326A4151977-04-22022 April 1977 NRC Guidelines for Excluding Exercising (Cycling) Tests of Certain Valves During Plant Operation Project stage: Other ML19329A8581977-06-27027 June 1977 Responds to NRC 770422 Request.Forwards Pump & Valve Test Program, for Compliance w/10CFR50.55a(g).Additions & Changes to Program,Which Meet Code Testing Requirements Will Be Implemented.W/O Encl Project stage: Other ML19329A9091977-11-22022 November 1977 Responds to NRC 770422 Request Re Facility Inservice Insp Program Compliance w/10CFR50.55a(g).Forwards Program for ASME Class 2 & 3 Components.W/O Encl Project stage: Other ML19329A9201977-11-22022 November 1977 ASME Section 11 Weld Examination Program for Facility: Inservice Insp Program Project stage: Other ML19329A8551978-01-0505 January 1978 Responds to NRC 770104 Request.Forwards Second Transmittal of 770627 Rept, Pump & Valve Test Program, for Docketing. W/O Encl Project stage: Request ML19317F5831978-01-0505 January 1978 ASME Section 11 Pump & Valve Test Program for Facility Project stage: Other ML19329B7741978-01-0606 January 1978 Notifies of Receipt of Util Request for Relief from Requirements of ASME Code Section 11,1974 Edition W/Addenda Through Summer 1975.Forwards Info Re Proposed Testing Program.W/O Encl Project stage: Other ML20236J6611978-03-29029 March 1978 Advises That Submittal of Second 40 Month Insp Period Plan Rescheduled to 780801.Submittal Date Changed from 780601 Due to Unanticipated Demand on Available Engineering Manpower Project stage: Other ML20112H3841978-08-0303 August 1978 Forwards Description of Planned Inservice Insp & Testing Program for Next 40-month Period & Three Sets of Modified Piping & Instrumentation Drawings,Including Applicable Components,Per Project stage: Request ML20147B6621978-10-0303 October 1978 Forwards Proposed Amend to Tech Specs Which Will Upgrade the Insvc Inspec Requirements Per 10CFR55a(g)(4)(ii).Proposed Changes Rely on Standard Tech Specs Project stage: Request ML19256A1711978-10-19019 October 1978 Notice of Granting of Relief from ASME Section XI Inservice Insp (Testing) Requirements Project stage: Other ML19256A1661978-10-19019 October 1978 Responds to Requesting Relief from Certain Requirements of Section XI of ASME Boiler & Pressure Vessel Code.Preliminary Review by NRC Finds Compliance W/Codes Would Cause Unusual Hardship & Are Waived Project stage: Other ML20062F4091978-12-12012 December 1978 Responds to 781201 Request for List of Plant Mod Being Made to Implement the Fire Hazard Analysis Rept.Fire Extinguishers Being Added to 13 Rooms & Wet Sprinkler or Spray Sys Being Added or Upgraded Project stage: Request ML19274D2261979-01-0303 January 1979 Grants Relief from Certain Inservice Insp & Testing Requirements of the ASME Boiler & Pressure Vessel Code, Section 11,pending Review Completion.Determines That Environ Statement Re This Action Is Not Necessary Project stage: Other ML19274E5471979-03-0909 March 1979 Requests Confirmation That Meb Will Not Review Inservice Testing Program in the Same Way They Review Inservice Insp Program.Asks for Name of Lead Reviewer of Testing Program Project stage: Other ML20244A5731979-03-28028 March 1979 Forwards Summary of 790222 Meeting Re Inservice Insp & Test Program.Summary Identifies Addl Info Required to Complete Review of Requested Relief from Certain ASME Code Requirements Project stage: Meeting ML20244A5791979-03-28028 March 1979 Summary of 790221 Meeting W/Util at Site Re Inservice Insp & Testing Program Project stage: Meeting ML19308A4531979-08-0808 August 1979 Discusses Review Re ASME Code,Section XI Exemption of ECCS Components from Inservice Insp Based on Water Chemistry Control.Water Chemistry Control to Minimize Stress Corrosion Is Unacceptable Basis for Exemption from Insp Project stage: Approval ML17318A2941979-09-14014 September 1979 Proposes Mods to Inservice Insp & Inservice Testing Program Review Responsibilities to Minimize Duplication of Effort at NRC & Maximize Contractor Review Activities.Sister Nuclear Facilities Should Be Managed by Same NRC Ofc Project stage: Other ML19309G7721980-05-0101 May 1980 Submits Addl Info Re Inservice Insp & Testing,In Response to NUREG-0411 Requirements.All Inservice Examinations Will Be Performed Per 1974 ASME Code XI W/Addenda Through 1975. Requests Relief from Hydrostatic Test Temp & Test Duration Project stage: Other ML19323D0821980-05-15015 May 1980 Forwards Updated Inservice Insp Program for Pumps,Valves, Welds(Including Supports,Components & Bolting) & Sys Pressure Tests Project stage: Other ML19323D0851980-05-15015 May 1980 Updated Inservice Insp Program for Pumps,Valves,Welds (Including Supports,Components & Bolting) & Sys Pressure tests.Twenty-three Oversize Drawings Encl Project stage: Other ML19345B2191980-11-14014 November 1980 Forwards Branch Questions & Comments & Request for Addl Info Re Util 800515 Revised Inservice Insp Program.Comments Will Form Basis for 801119-21 Working Session at Site Project stage: RAI ML19340E1221980-11-30030 November 1980 To Inservice Insp Program Project stage: Other ML19340E1191980-12-15015 December 1980 Forwards Revision to 800515 Inservice Insp Program.Changes Reflect Results of 801119 & 20 Meetings W/Nrc Onsite Re Lower Head Weld Insp & Requirements in 1977 Edition Through Summer 1978 Addenda of Boiler & Pressure Vessel Code Project stage: Meeting ML19345F2471981-01-27027 January 1981 Amend 2 to Inservice Insp Program Project stage: Other ML19345F2451981-01-27027 January 1981 Forwards Amend 2 to Facility Inservice Insp Program, Replacing 790606 Amend 1 Submittal.Requested Relief Does Not Affect Public Health & Safety.Requests Approval Project stage: Other ML19345G5121981-03-31031 March 1981 Forwards Editorial Revisions to Inservice Insp Program Project stage: Other ML19240C0021981-03-31031 March 1981 Inservice Testing Program for Pumps & Valves at Davis-Besse Nuclear Power Station - Unit 1 (Docket 50-346) for Period Nov 1977 Through Nov 1987, Safety Evaluation Project stage: Other ML20011B2541981-11-24024 November 1981 Forwards Info Re Class I Inservice Exam Areas Not Receiving Full Code Exam During 1981 Maint Refueling Outage.Areas Include Lugs,Reactor Recirculation Sys Vessel Nozzles,Piping Butt Welds & Recirculation Pump Studs Project stage: Other 05000270/LER-1982-002-01, /01T-0:on 820122,three Core Support Assembly Thermal Shield Bolts Found W/Heads Broken Off & Shock Pad Y-2 Attachment Bolts Discovered Broken.Caused by Intergranular Stress Corrosion Cracking.Pad Removed1982-02-0505 February 1982 /01T-0:on 820122,three Core Support Assembly Thermal Shield Bolts Found W/Heads Broken Off & Shock Pad Y-2 Attachment Bolts Discovered Broken.Caused by Intergranular Stress Corrosion Cracking.Pad Removed Project stage: Other 05000270/LER-1982-002, Forwards LER 82-002/01T-0.Detailed Event Analysis Encl1982-02-0505 February 1982 Forwards LER 82-002/01T-0.Detailed Event Analysis Encl Project stage: Other ML20041C2181982-02-0808 February 1982 Notice of Granting Relief from ASME Section XI Inservice Testing Requirements Project stage: Other ML20041C2151982-02-0808 February 1982 Safety Evaluation Re Inservice Test Program & Granting of Relief from ASME Code Section XI Inservice Testing Requirements Project stage: Approval ML20041C2071982-02-0808 February 1982 Forwards SER & Fr Notice Re Inservice Test Program & Granting of Relief from ASME Code Section XI Inservice Testing Requirements.Approval of Relief Expires on 850508 for Unit 1 & on 870401 for Unit 2 Project stage: Approval ML20040H1821982-02-16016 February 1982 Submits Editorial Revisions,Revision 3,to Inservice Insp Program Project stage: Other ML20040H1851982-02-28028 February 1982 Inservice Insp Weld & Support Insp Program,Revision 3, Editorial Changes Project stage: Other ML20041G4211982-03-12012 March 1982 Requests Addl Info Re Inservice Insp Program Relief.Info Should Be Forwarded to Science Applications,Inc,Within 30 Days of Ltr Project stage: Other ML20054D3051982-04-0606 April 1982 Requests Addl Info Required for Review of Inservice Insp Program.Response by 820611 Requested Project stage: Approval ML20054C6451982-04-0707 April 1982 Approves Util 800501 & 820311 Requests for Relief from 1974 Edition of ASME Section XI Code Re Required Inservice Insp Hydrostatic Min Test Temp of 100 F & Hold Times Project stage: Other ML20054C9571982-04-0808 April 1982 Notice of Violation from Insp on 820101-0228 Project stage: Other ML20052F3861982-05-0505 May 1982 Safety Evaluation Re ASME Code Section Xi,Inservice Insp Requirements.Granting of Relief Does Not Authorize Change in Effluent Types or Total Amounts Nor Increase in Power Level & Will Not Result in Significant Environ Impact Project stage: Approval ML20052F3891982-05-0505 May 1982 Notice of Granting Relief from ASME Code Requirements Project stage: Other ML20052F3771982-05-0505 May 1982 Advises That Sections 3 & 4 of 800515 Revised Inservice Insp & Testing Program Per ASME Boiler & Pressure Vessel Code Section XI of 1977 Edition Through Summer 1978 Addenda Acceptable for Remainder of 120-month Insp Interval Project stage: Other ML20023A4861982-09-0202 September 1982 Ei Hatch Nuclear Plant Units 1 & 2 Inservice Insp Program, Technical Evaluation Rept Project stage: Other ML20065B8141982-09-15015 September 1982 Advises of Exam Areas Not Receiving Full Code Exam During Inservice Insp Activities Conducted During Maint/Refueling Outage & Forwards Lists of Exam Limitations.Welds Receiving Limited Coverage Listed Project stage: Other ML20028D2071983-01-0707 January 1983 Comments on Upgrading Inservice Insp/Inservice Testing Program.Upgrade Requires Extensive Rewrite Due to Significant Changes in 1980 Edition of ASME Section XI Code from That Currently Used.Submittal Delayed Until 830801 Project stage: Other ML20028G1681983-02-0202 February 1983 Forwards Addl Info on Modified 821214 Code Relief Request 1 Revising Inservice Testing Program.Basis for Request Listed. Request Per ASME Section XI Iwv Re MSIVs MS-100 & MS-101 Project stage: Request 1980-12-15
[Table View] |
Text
Docket No. 50-346 TOLEDO
- License No. NPF-3 Rwn P cm Serial No. 908 Vce Presnjent Nuclear
'"*"8' February 2, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz United States Nuclear Regulatory Commission Operating Reactors Branch No. 4 Division of Operating Reactors Washington, D. C.
20555
Dear Mr. Stolz:
This letter is to transmit additional information on modified Code Relief Request No. 1, dated December 14,1982 (Serial No. 882), revising the Toledo Edison Inservice Testing Program, which was submitted by letter on May 15, 1982 (Serial No. 616).
Please find attached five (5) copies of additional information to Code Relief Request No. 1 for the Davis-Besse Nuclear Power Station, Unit No.
1, Inservice Testing Program. The subject of this relief request is the Class 2 valve testing requirements of ASME Section XI IWV, Main Steam Isolation Valves MS-100 and MS-101.
By this submittal, Toledo Edison Company requests relief from the perform-ance testing by partial stroking of Main Steam Isolation Valves (MSIV's)
MS-100 and MS-101.
The basis for this relief request is as follows:
a.
Partial stroking the valve during normal operation produces the potential for the valve to fully close. This would put the plant in an unsafe c:ndition, with no added safety benefit in performing the partial stroke test.
b.
Relief from partial stroking MSlV's have been issued to Light Water Reactors (LWR's) in the past.
c.
The cost for power replacement, if the valve would fully close during the partial stroking testing, would be approximately
$380,000, and an additional two days lost in operating time.
9302070478 830202 DR ADOCK 05000346 PDR THE TOLEDO EOISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43652 b
Docket No. 50-346 License No. NPF-3 Serial No. 908 February 2, 1983 Page 2 We request permission.to perform an "in lieu-of" full stroke test at hot shutdown. This package has been developed in accordance with the require-ments of the ASME-Boiler and Pressure Vessel Code,Section XI, 1977 Edition through Summer 1978 Addenda, and consists of the following document.
Additional information to modified Code Relief Request No. 1-Description _of and justification for the deviation from the requirments of ASME Section XI IWV-3412(a), Exercising Procedure.
This relief request is being re-submitted in accordance with 10CFR50.55a(g) (5)(iii). Any additions that become necessary due to modifications and changes to this program during the course of the 120 month interval, which do not meet the code testing requirements, will be implemented as needed. A fully documented notification to the NRC will be placed on the docket subsequent to implementation of approv-d changes.
Very truly yours,
$f RPC:ECC:nif encl.
j cc: DB-1 NRC Resident Inspector' Kevin Ward, NRC Region III George Johnson, NRC Bethesda, Maryland A. DeAgazio NRR Branch 4, Project Manager l
I, rr
Docket No. 50-346 License No. NPF-3 ATTACHMENT 1 Serial No. 908 February 2, 1983 MODIFIED CODE RELIEF REQUEST NO. 1 Components:
Main Steam Isolation Valves MS-100 and MS-101 Function:
Valves are required to close within 5 seconds on a safety actuation signal thereby isolating the main steam lines from the Steam Generators.
ASME Class:
2 Testing Requirements:
Partial stroke valve every three months during normal operation and full af coke valves during cold shutdown.
Basis for Relief Request:
1.
Code Test Requirements for exercising valves (Ref: ASME Code Section II, 1977 Edition through Summer 1978 Addenda):
"IWV-3412 Exercising Procedure"
"(a) Valves shall be exercised to the position required to fulfill their function unless such operation is not practi-cal during plant operation.
If only limited operation is practical during plant operation, the valve shall be part-stroked exercised during plant operation and full-stroke exercised during cold shutdown."
2.
Ramifications of Partial Stroke Code Test for Valves MS-100 and MS-101 When performing the partial stroke test specified in the code, the following additional safety action items would have to be implemented if the valve would inadvertently close past 90% open during the test.
If the MSIV continues to shut past approximately 90% open, attempt will be made to seat the " Slow Close" valve by pushing and releasing " Slow Close" button.
If this fails, the area must be evacuated. The reactor operator would be required to take the following action:
a)
Trip the reactor and carry out EP 1202.04 - Reactor Trip.
b)
Ensure that either a main foed pump is operating on the side where the MSIV is open og; start the startup feed pump.
c)
If MS-101 has closed, shif t auxiliary steam to the auxiliary boiler.
d)
If MS-100 has closed, shift gland steam to auxi:.iary steam.
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a.
m
- - Docket No. 50-346 License No. NPF-3 Ser'ial No. 908 February 2, 1983 l
e)
S'aift turbine bypass valve on affected side to Hand and I
shut them.
f)
Open bypass valve (MS-101A or MS-100A) on affected side.
g)
Attempt to reopen MSIV when once thru steam generator (OTSG) and turbine header pressure are equalized within 100 poid.
h)
The " Slow Close" valve would also have to be repaired in order to reopen the MSIV (MS-100/MS-101).
1)
The cost involved if the above occurs would be approximately
$380,000 with two days lost operating time.
3.
Background Information on the Inservice Testing Program for the Davis-Besse Unit 1 Nuclear Power, Station 2
a) on May 15, 1980 Serial No. 616 a revised Inservice Inspection Testing Program was submitted to the NRC, requesting exception from the partial stroke testing during normal operation on valves MS-100 and MS-101 Page II-59.
The alternate testing stated in this submittal was to full stroke the valves during cold shutdown with a justification stated in the submittal.
3 b)
On November 14, 1980 Docket No. 50-346 Toledo Edison Company received from the NRC questions and comments on the submitted Inservice Testing Program. The NRC requested a meeting at the Davis-Besse 1 site on November 19-21, 1980 to discuss their review on the submitted Inservice Testing Program.
It should be'noted that there were no comments from the NRC relating to the code exception for.not partial stroking during normal operation valves MS-100 and MS-101.
0 c)
On December 15, 1980 Serial No. 671 revisions were made to the Inservice Testing Program based upon the results of the combined meeting NRC/ Toledo at the Davis-Besse site November 19-21, 1980. During the site meeting each relief request was discussed in detail, and we explained to the NRC personnel why we should not partial stroke valves MS-100 and MS-101.
It was agreed during that meeting that a 10% stroke on the valves in question would not increase any safety margin and the possible safety consequences if the valve should go full close during the test could cause a safety issue.
It should be noted on page II-59, the exception to partial stroking of the valves was not one of the questions that evolved from of the NRC review of the Inservice Testing Program.
5 d)
On March 31, 1981 Serial No. 702 based upon the resul,ts of several telephone conversations with the NRC and EG&G, Inc.. several editorial changes were made to the Inservice 2
1
--ev-
Docket No. 50-346 License No. NPF-3 Serial No. 908^
February 2, 1983 Testing ~ Program.
It also should be noted that on page 11-59, the only change requested by the NRC on not partial stroking during normal operation Valves MS-100 and MS-101, was to change code exception to Basis for Relief Request.
4.
. Alternative Valve Testing Proposed a)
The above technical and safety-related consid-erations, and potential for additional downtime, when partial stroking valves MS-100 and MS-101, result in no added safety benefits.
Toledo Edison requests permission to perform, in lieu of the partial stroke test during normal operation, a full stroke test at hot shutdown, as defined in Davis-Be'sse Technical Specification (Table 1-1, page 1-7).
Since ASME Section XI 1977 Edition through Summer 1978 Addenda, Article IWV-3412 only provides a definition for two (2) plant conditions, the full stroke testing will be performed when the plant is in hot shutdown condition (defined in the Davis-Besse Technical Specifications) at least once per 12 months or at a frequency not exceeding one test every three months.
5.
Other Verification on Valves MS-100 and MS-101 a)
TED proposes to introduce valve trends analysis on valves MS-100 and MS-101, which will allow monitoring of the valve's characteristic cach time the valve is full stroked.
By utilizing trends analysis during the full stroke testing, any abnormal behavior of the valves could be identified and appropriate action taken to correct any abnormalities.
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