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Results
Other: 05000369/LER-1984-029, :on 841029,concentration of Nitrogen in Upper Head Injection Accumulator Exceeded Tech Spec Limits.Caused by Repetitive Continuous Makeup to Accumulator from Upper Head Injection Surge Tank, 05000369/LER-1984-030, Suppl to LER 84-030:review Revealed Installation Error That Would Result in Failure of Upper Head Injection Accumulator Discharge Valves to Isolate on Low Level.Analysis of Safety Significance & Encl, 05000370/LER-1984-019-01, :on 840820,while Filling & Venting Upper Head Injection Sys,Reactor Vessel Head Sight Glass Failed, Releasing RCS Water Into Containment Bldg.Caused by Design Deficiency.Sight Glass Replaced, 05000370/LER-1984-028, :on 841113,upper Head Injection Hydraulic Sys Alarm Received in Control Room for Train B While Train a Instruments Calibr.Caused by Crossover Connection Between Trains Allowing Pressure Surges, ML19306G616, ML20112G107, ML20126M295, ML20140A539, ML20202E874, NRC-86-3112, Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl
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MONTHYEAR05000370/LER-1984-019-01, :on 840820,while Filling & Venting Upper Head Injection Sys,Reactor Vessel Head Sight Glass Failed, Releasing RCS Water Into Containment Bldg.Caused by Design Deficiency.Sight Glass Replaced1984-09-19019 September 1984
- on 840820,while Filling & Venting Upper Head Injection Sys,Reactor Vessel Head Sight Glass Failed, Releasing RCS Water Into Containment Bldg.Caused by Design Deficiency.Sight Glass Replaced
Project stage: Other ML19306G6161984-11-28028 November 1984 Discusses Region II 841102 Problem W/Upper Head Injection Sys at Facility.Memo Prepared Prior to Event Expressed Concern That NRC Does Not Appreciate Safety Significance of Event.Appropriate Action Requested Project stage: Other 05000369/LER-1984-029, :on 841029,concentration of Nitrogen in Upper Head Injection Accumulator Exceeded Tech Spec Limits.Caused by Repetitive Continuous Makeup to Accumulator from Upper Head Injection Surge Tank1984-11-29029 November 1984
- on 841029,concentration of Nitrogen in Upper Head Injection Accumulator Exceeded Tech Spec Limits.Caused by Repetitive Continuous Makeup to Accumulator from Upper Head Injection Surge Tank
Project stage: Other 05000370/LER-1984-028, :on 841113,upper Head Injection Hydraulic Sys Alarm Received in Control Room for Train B While Train a Instruments Calibr.Caused by Crossover Connection Between Trains Allowing Pressure Surges1984-12-13013 December 1984
- on 841113,upper Head Injection Hydraulic Sys Alarm Received in Control Room for Train B While Train a Instruments Calibr.Caused by Crossover Connection Between Trains Allowing Pressure Surges
Project stage: Other 05000369/LER-1984-030, Suppl to LER 84-030:review Revealed Installation Error That Would Result in Failure of Upper Head Injection Accumulator Discharge Valves to Isolate on Low Level.Analysis of Safety Significance & Encl1984-12-19019 December 1984 Suppl to LER 84-030:review Revealed Installation Error That Would Result in Failure of Upper Head Injection Accumulator Discharge Valves to Isolate on Low Level.Analysis of Safety Significance & Encl Project stage: Other ML20112G1071984-12-20020 December 1984 Forwards Evaluations of Complete Draindown of Upper Head Injection Sys Water Accumulator & Poor Performance of Kerotest Valves for Compliance W/Tech Spec 4.5.1.2c.Channel Calibr Overlapping Surveillance Satisfies Tech Specs Project stage: Other ML20126M2951985-07-24024 July 1985 Advises That Addl Info Needed for Plants W/Upper Head Injection (Uhi) Sys to Assess Likelihood of Loss of Uhi auto-isolation Capability.Info Re Demand & Failure Frequencies of Isolation Function Requested within 30 Days Project stage: Other ML20136D3301985-12-23023 December 1985 Forwards Response to NRC 851104 Request for Addl Info Re Radiological Aspects of upper-head Injection Removal & Radiological Impacts on Plant Operations.Final Decision Re Disposal Method Expected by Late Jan 1986 Project stage: Request ML20140A5391986-03-17017 March 1986 Provides Addl Info Re License Amend Request Concerning upper-head Injection Sys.Bash Large Break LOCA Analyses Replaced w/NRC-approved Bart Analyses.Info from Listed Submittals Still Valid Unless Noted Project stage: Other NRC-86-3112, Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl1986-03-18018 March 1986 Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl Project stage: Other ML20202E8741986-04-0808 April 1986 Forwards Addl Info Re Radwaste Expected to Be Generated During upper-head Injection Removal,Per NRC 860407 Telcon Project stage: Other ML20203C6371986-04-17017 April 1986 Responds to 860416 Request for Addl Info Re Planned Elimination of Upper Head Injection Sys.Containment Penetration Capping Will Be Performed Per Applicable Codes & Stds & Design Requirements Project stage: Request 1984-09-19
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.. o Duxu POWER Goxem 18.0. ISOX 31180 CitAltLOTTI' N.C. 28242 HALH.TUCKEN retse,mu
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(704) at:t-4n:38 wousas reawcwn April 17, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commissica Washington, D.C.
20555 Attention:lt.'fJ' _ Youndlood',I Director PWR Project Directorate #4
Subject:
McGuire Nuclear Station Docket Nos. 50-369, -370
Dear Mr. Youngblood:
In a telephone call on April 16, 1986, the NRC requested additional information relative to the planned elimination of the Upper Head Injection System from the McGuire Nuclear Station.
This sJdltional information is attached.
Very truly yours, s hl-
/d g
Hal B. Tucker, ice President Nuclear Production Department WDR/gbh Attachment cc:
Mr. Darl Hood, Project Manager Division of Licensing Office of Nuclear Regulatory Commission Washington, D.C.
20555 W. T. Orders NRC Resident Inspector McGuire Nuclear Station Dr. J. Nelson Crace U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, CA 30323 lh 9604210205 860417 PDR ADOCK 05000369 P
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Duke Power Company McGuire Nuclear Station Additional Information Related to UHI Removal The planned operation of the McGuire Nuclear Station without the Upper Head Injection System operable may be divided into two phases. The first phase involves operation with the UHI System in place hut functionally disabled by closure of the existing UHI isolation valves. The plant modifications required for this mode of operation were described in Duke's December 17, 1985 transmittal.
The second phase involves the physical removal of UHI piping and components, cutting and capping the penetrations to the vessel upper head, capping containment penetrations, and capping miscellaneous piping interfaces with other plant systems.
The vessel upper head penetration cap has been designed and manufactured in accordance with ASME Section III (Class 1) (latest Edition and Addenda) requirements.
Installation of the cap will be performed in occordance with ASME Section IX and XI requirements, approved plant procedures, and other i
applicable codes and standards. The capped vessel upper head penetrations will undergo NDE and hydrostatic testing in accordance with the require-ments of ASME Section XI, approved plant procedures, and other applicable codes and standards.
Two of the three UHI related containment penetrations are currently planned l
to be capped when the system is physically removed. The containment pene-tration capping will be performed in accordance with applicable codes and standards (including ASME Section III (Class 2)) and design requirements.
The third penetration will be used as the post nccident liquid sampling return line penetration. Testing of containmen' penetrations will be per-formed in accordance with applicable codes, standards, and approved plant procedures in order to ensure the required containment integrity.
UH1 interfaces with other systems consist of various grades of piping, Capping of the interface piping will be performed in accordance with i
applicable codes, standards, and prudent design practices.
Parts of the UHI System located in the Auxiliary Building may remain in place indefinitely. Any component which is not physically removed will be evaluated from mechanical and civil engineering perspectives to ensure l
the component does not introduce risk to or interfere with other plant systems. The evaluations include seismic and structural analyses and will l
ensure McGuire Nuclear Station continues to satisfy applicabic codes, standards, regulatory requirements, and design criteria, l
The safety analyses performed are applicable for either mode of operation, i
UHI isolated or UHI physically removed.
The isolation of UHI has been discussed in previous Duke transmittals to the NRC. The physical removal i
of UHI includes design, execution of modifications, and subsequent testing in accordance with applicable codes and standards, approved plant pro-cedures, regulatory requirements, and good engineering practice.
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