Letter Sequence Other |
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Results
Other: ML19209A420, ML19246C410, ML19256G252, ML19257C541, ML19290B734, ML19320D502, ML19320D511, ML19320D518, ML19320D523, ML19320D526, ML20041G423, ML20052C092, ML20054K847, ML20054K849, ML20062G684, ML20062G693, ML20064L899, ML20082A625, ML20150F162
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MONTHYEARML19270G8051979-05-15015 May 1979
Summary of 790511 Meeting W/Util in Bethesda,Md Re Auxiliary Feedwater Sys.List of Attendees & Matl Discussed Encl
Project stage: Meeting
ML20150F1621979-05-22022 May 1979
Submits Formal Responses to 790510 Questionnaire Re Pressurizer Heater,Loss of Feedwater Event & Steam Generator
Project stage: Other
ML19225C9181979-06-0404 June 1979
Requests Status of Lll Electrical Staff Overpressure & Flooding Reviews
Project stage: Request
ML19246C4101979-06-11011 June 1979
Forwards NRC to Westinghouse Requesting Addl Info Re Small Break LOCA Analyses & Analysis Methods.Nrc Will Eventually Require Documentation Re Applicability of Westinghouse Results to Analyses at Facility
Project stage: Other
ML19209A4201979-09-21021 September 1979
Forwards NRC Requirements for Auxiliary Feedwater Sys & Requests That Plant Designs & Procedures Be Evaluated Against Applicable Requirements to Determine Degree of Conformity
Project stage: Other
ML19259D6551979-10-20020 October 1979
Forwards Response to NRC Requesting Commitments to Implement NUREG-0578 Recommendations.Design Differences Decrease Chance of TMI-type Accident
Project stage: Request
ML19290B7341979-10-29029 October 1979
Submits Partial Response to Re short-term & long-term Requirements for Auxiliary Feedwater Sys.Requests Extension Until 800131 for Remaining Requirements
Project stage: Other
ML19320D5181979-12-0707 December 1979
Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump
Project stage: Other
ML19256G1021979-12-17017 December 1979
Responds to NRC 791210 Request for Addl Info on TMI Lessons Learned Task Force Recommendations Re Auxiliary Feedwater Sys.Oversize Drawings Available in Central Files
Project stage: Request
ML19256G2521979-12-17017 December 1979
Forwards Modified Response to Previous Commitment to Implement NUREG-0578.Util Will Provide Alarms in Addition to Existing Position Indication for Power Operated Relief Valves for Both Units
Project stage: Other
ML19320D5261979-12-23023 December 1979
Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pumps
Project stage: Other
ML19320D5231979-12-26026 December 1979
Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pump
Project stage: Other
ML19320D5111979-12-28028 December 1979
Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump
Project stage: Other
ML19257C5411980-01-22022 January 1980
Forwards Small Break LOCA Operator Guidelines.Min RCS Subcooling Margin Set at 36 F Prior to Terminating Safety Injection
Project stage: Other
ML19260D8281980-02-0404 February 1980
Responds to NRC 790921 Request for Evaluation of Requirements for Auxiliary Feedwater Sys & Associated Schedule & Commitment for Implementation of Required Changes & Actions
Project stage: Request
ML19316A7831980-05-16016 May 1980
Forwards Request for Addl Responses to NRC Long & short-term Recommendations Re Auxiliary Feedwater Sys.Open Items Must Be Resolved Acceptably Before Safety Evaluation Can Be Issued.Responses Needed within 45 Days
Project stage: Approval
ML19320D5021980-07-0808 July 1980
Revised Tech Spec 15.3.4 for Steam & Power Conversion Sys
Project stage: Other
ML19320D4771980-07-0808 July 1980
Forwards Revised Tech Spec 15.3.4 for Steam & Power Conversion Sys & Four 72-h Test Repts for Auxiliary Feed Pump in Response to NRC 800516 Request for Addl Info Re Auxiliary Feedwater Sys
Project stage: Request
ML19350D3491981-04-0909 April 1981
Responds to 810127 Request for Response to Unresolved Items Identified in Safety Evaluation for Auxiliary Feedwater Sys, Including short-term Recommendation GS-1 Re Tech Specs & Recommendation Re Redundant Level Indications
Project stage: Request
ML20041G4231982-03-16016 March 1982
Submits Synopsis of Items Discussed During 820302 Telcon Re Automatic Initiation Features of Auxiliary Feedwater Sys
Project stage: Other
ML20052C0921982-04-27027 April 1982
Tech Spec Change Request 76 Consisting of Tech Spec Pages 15.3.4-1,-2 & -2.a Re Auxiliary Feedwater Pump
Project stage: Other
ML20052C0861982-04-27027 April 1982
Application for Amend to Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 76.Amend Would Incorporate NRC Changes to Limit Unavailability of Auxiliary Feedwater Pumps
Project stage: Request
ML20054K8491982-06-30030 June 1982
Proposed Tech Spec Changes Re Periodic Testing of Auxiliary Feedwater Sys Automatic Actuation Logic
Project stage: Other
ML20054K8471982-06-30030 June 1982
Forwards Revision to Tech Spec Table 15.4.1-1 Re Periodic Testing of Auxiliary Feedwater Sys Automatic Actuation Logic.Nrc Review of Tech Spec Change Request 76 Should Include Addl Change
Project stage: Other
ML20062G6931982-07-27027 July 1982
Notice of Issuance & Availability of Amends 62 & 67 to Licenses DPR-24 & DPR-27,respectively
Project stage: Other
ML20062G6841982-07-27027 July 1982
Amends 62 & 67 to Licenses DPR-24 & DPR-27,respectively, Changing Tech Specs to Modify Limiting Conditions for Operation Re Auxiliary Feedwater Pump Operation
Project stage: Other
ML20064L8991983-02-11011 February 1983
Advises That Installation of Addl Supports for Auxiliary Feedwater Sys Piping & Components Rescheduled to June 1983, Due to Conflicts W/Other Plant Mods
Project stage: Other
ML20082A6251983-11-11011 November 1983
Advises That Auxiliary Feedwater Sys Operability Mods Completed Per Tech Spec Revs Proposed in 820427,0505 & 0630 Ltrs
Project stage: Other
1979-09-21
[Table View] |
Text
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]5.3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies to the operating status of steam and power conversion system.
Objective To define conditions of the steam and power conversion system steam-relieving capacity. Auxiliary Feedwater System and Service Water System operation is necessary to ensure the capability to remove decay heat from the core.
Specification A.
When the reactor coolant is heated above 350*F the ' reactor shall not be taken critical unless the following conditions are met:
1.
A minimum steam-relieving capability of eight (8). main steam safety valves available, except for low power physics testing.
2.
Auxiliary Feedwater System a.
Two Unit Operation
- All four auxiliary feedwater pumps together with their associated flow paths and essential instrumentation shall be operable.
b.
Single Unit Operation - Both motor driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pump associated with that unit together with their associated flow paths and essential instrumenta-tion shall be operable.
8205040 355 15.3.4-1
3.
A minimum of 10,000 gallons of water per operating unit in the condensate storage tanks and an unlbnited water supply from the lake via either leg of the plant Service W ter System.
a 4.
Systen piping and valves required to function during accident conditions directly associated with the above components operable.
B.
The iodine-131 activity on the secondary side of the steam generator shall not exceed 1.2 pCi/cc.
C.
During power operation the requirements of 15.3.4.A.2.a and b may be modified to allow the following components to be inoperable for a specified time. If the system is not restored to meet the requirements of 15.3.4.A.2.a and b within the time period specified, the specified action must be taken. If the requirements of 15.3.4.A.2.a and b are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the appropriate reacter(s) shall be cooled down to less than 350'F.
1.
Two Unit operation - One of the four operable auxiliary feedwater pumps may be out-of-service for the below specified times. A turbine driven auxiliary feedwater pump may out of.
service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the turbine driven auxiliary feedwater pump cannot be restored to service within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period the as'sociated reactor shall be shutdown and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. A motor driven auxiliary feedwater pump may be out of service for up to 7 l
days. If the inoperable motor driven auxiliary feedwater pump cannot be restored to service within the 7 day time perioc both of the reactors shall be shutdown and in hot shut-down within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
15.3.4-2
o 2.
Single Unit Operation - The turbine driven auxiliary feedwater pump may be out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the turbine drives auxiliary feedwater punp cannot be restored to service within that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period, the reactor shall be shutdown and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Either one of the two motor driven auxiliary feedwater pumps may be out-of-service for up to 7 days. If the motor driven auxiliary feedwater pump cannot be restored to service within that 7 day period the operating unit shall be shutdown and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
15.3.4-2.a
