Letter Sequence Other |
|---|
|
Results
Other: A01658, Submits Addl Info Re Independence of Four Channels of Reactor Protection & Engineered Safeguards Actuation Sys Measurement Logic,In Response to NRC, ML17212B541, ML18047A273, ML20009C700, ML20009D105, ML20050Q900, ML20054C030, ML20054C820, ML20054C988, ML20054C994
|
MONTHYEARML18046B4081977-06-28028 June 1977 Safety Evaluation Supporting Amend 15 to License DPR-67. Calvert Cliffs Sample Tech Specs Re Reactor Protection Sys & Engineered Safety Features Actuation Sys Encl Project stage: Approval ML20003G0471978-09-12012 September 1978 Summary of 780802 Meeting W/Utils & C-E Re Length of Time Single Failed Reactor Protection Sys Channel Should Be Bypassed Before Requiring Tripping Project stage: Meeting ML20238E6041978-09-15015 September 1978 Forwards Ltrs to Utils Documenting NRC Position Presented at 780802 Meeting & Requesting That STS Allowing Limited Reactor Protection Sys Channel Bypass Be Proposed Project stage: Meeting ML20238E6971978-09-30030 September 1978 Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls Project stage: Meeting ML20238E6521978-09-30030 September 1978 Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls Project stage: Meeting ML20238E6441978-09-30030 September 1978 Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls Project stage: Meeting ML20238E7021978-09-30030 September 1978 Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls Project stage: Meeting ML18046A5781981-04-16016 April 1981 Requests Results within 90 Days Re Review of Reactor Protection & Engineered Safety Features Actuation Sys Channel Operability.Application for License Amend Re Tech Specs Change May Be Substituted for Review Project stage: Approval ML20003G6471981-04-16016 April 1981 Requests Results within 90 Days Re Review of Reactor Protection & Engineered Safety Features Actuation Sys Channel Operability.Application for License Amend Re Tech Specs Change May Be Substituted for Review Project stage: Approval ML20009C7001981-07-15015 July 1981 Advises That Verification Results Re Adequacy of Physical & Electrical Separation & Independence of Reactor Protection Sys Instrument Channels & Engineered Safety Features Actuation Sys Subsystems Expected by End of 1982 Outage Project stage: Other ML20009D1021981-07-21021 July 1981 Application for Amend to License DPR-40 to Upgrade Provisions Re Operation W/Tripped or Bypassed Reactor Protection or Emergency Safeguards Feature Channel Project stage: Request ML20009D0991981-07-22022 July 1981 Forwards Application for Amend to License DPR-40 & Proposed Tech Specs.Amend Upgrades Provisions Re Operation W/Tripped or Bypassed Reactor Protection or Emergency Safeguards Feature Channel.Certificate of Svc Encl Project stage: Request ML20009D1051981-07-22022 July 1981 Proposed Tech Specs Upgrading Provisions Re Operation W/ Tripped or Bypassed Reactor Protection or Emergency Safeguards Feature Channel Project stage: Other ML18046A8251981-07-27027 July 1981 Informs That Applicant Will Submit Application for Tech Spec Changes by 810915 Re Reactor Protection Sys Inoperable Channel Condition.Documentation of Design Similarities to St Lucie & Calvert Cliffs Complete Project stage: Request A01658, Submits Addl Info Re Independence of Four Channels of Reactor Protection & Engineered Safeguards Actuation Sys Measurement Logic,In Response to NRC1981-10-23023 October 1981 Submits Addl Info Re Independence of Four Channels of Reactor Protection & Engineered Safeguards Actuation Sys Measurement Logic,In Response to NRC Project stage: Other ML20050Q9001982-03-31031 March 1982 Informs of Modified Staff Position on Length of Time Reactor Protection Sys or ESF Actuation Sys Channel May Be Bypassed. San Onofre Unit 2 Tech Spec & Design Criteria Encl Project stage: Other ML20054C8201982-03-31031 March 1982 Provides Options for Licensees Which Would Allow Flexibility in Performing Maint & Testing of Inoperable Channels,Per .San Onofre Proof & Review Tech Specs Encl Project stage: Other ML20054C9941982-03-31031 March 1982 Informs of Modified Position on Length of Time Reactor Protection Sys or ESF Actuation Sys Channel May Be Bypassed. Proposed Tech Specs Encl Project stage: Other ML18047A2731982-03-31031 March 1982 Forwards Proof & Review Copy of Tech Specs,Incorporating Changes to Permit 48-h Bypass of Reactor Protection Sys & ESF Actuation Sys Inoperable Channel.Design Criteria Permitting Bypass for Indefinite Period Encl Project stage: Other ML20054C0301982-03-31031 March 1982 Forwards Proof & Review Copy of Tech Specs,Incorporating Changes to Permit 48-hr Bypass of Reactor Protection Sys & ESF Actuation Sys Inoperable Channel.Design Criteria Permitting Bypass for Indefinite Period Encl Project stage: Other ML20054C9881982-03-31031 March 1982 Advises That NRC Position Modified Re Reactor Protection Sys & ESF Actuation Sys.Proposed Tech Specs Encl Project stage: Other ML17212B5411982-03-31031 March 1982 Informs of Modified Position on Length of Time Reactor Protection Sys or ESF Actuation Sys Channel May Be Bypassed. Proposed Tech Specs Encl Project stage: Other 1981-04-16
[Table View] |
Text
~
c ~
(
MAR S1 19N n1S-ale g
RQQIIr]yp@
APR8 tNggy~
7 nag Enclosure 2 delineates the criteria which must be satisfied to ensure that three channels are sufficient for plant protection.
- However, we believe that ft fs prudent that an inoperable channel be repaired and returned to service.as quickly as practicable.
Action Statement 2 of Enclosure 1 would allow the flexibilityof continued plant operation with an inoperable channel fn bypass where ft is not feasible to repair the charm'el (for example, ff the failure fs inside the containment fn a location inaccessible during plant operation)..
The model TS, however, do place responsibility on the licensee to repair the channel as quickly as possible and fn any event during the first cold shutdown after the failure has occurred.
If you have any questions on this sub)ect, please contact your assigned NRC prospect manager.
Sincerely, 6rlginaI signed bg Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch 83 Division of Licensing
Enclosures:
As stated DISTRIBUTION:
~ocket File NRC PDR L PDR CO Docket No. 50-335 NSIC
~
C ORBP3 Rdg DEisenhut Dr. Robert E. Uhrfg JHeltemes Vice President OELD Advanced Systems 8 Technology ACRS-10 Florida Power 8 Light Company P. 0. Box 529100 Gray File Mfamf, Florida 33152 PMKreutzer-3 RAClark CO
Dear Dr. Uhrig:
EConner CNelson This fs to inform you of a modified staff position on the length of time a reactor protection system (RPS) or an engineered safety features actuation system (ESFAS) channel may be bypassed.
Your Technical Specifications (TS) currently limit the inoperable channel bypass time to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Ifft can be verified that three protection system channels fn two-out-of-three logic are sufficient to satisfy all protection system criteria, then one channel of a four channel system may be bypassed for a lengthy period of time with no degradatfon to safety.
Action Statement 2 of the Enclosure 1 TS page (San Onofre - Unit 2 type) may be proposed fn place of the appropriate present action requirements.
OFFICEI SURNAME/
DATE Q cc:
See ext page p4~:-
C l&rt 3/27/82 3~82 OHM3.'Pl,.......
AC 3/g) /82 NRC FORM 318 {10-80) NRCM 0240 OFFICIAL R ECOR D COPY USOPO.'981~960
4 I
1 4
a '$
- 4 Cl II $4 t
'5 A
4 V
IP
)
Florida Power
& Light Company CC:
Harold F. Reis, Esquire Lowenstein,
- Newman, Reis
& Alexrad 1025 Connecticut Avenue, N.W.
Washington, D. C.
20036 Norman A. Coll, Esquire McCarthy, Steel, Hector
& Davis 14th Floor, First National Bank Building Miami Florida 33131 Indian River Junior College Library 3209 Virginia Avenue Fort Pierce, Florida 33450 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator
. St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 U.S. Environmental Protection Agency Region IY Office
~ ATTN:
Regional Radiation Representative 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
4853 Cordell Avenue, Suite A-1
- Bethesda, Maryland 20014 Regional Administrator Nuclear Regulatory Commission, Region II Office of Executive Director for Operations 101 Marietta Street; Suite 3100 Atlanta, Georgia 30303 Mr. Jack Schreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector/St.
Lucie Nuclear Power Station c/o U.S.N.R.C.
P. 0.
Box 400 Jensen Beach, Florida 33457 Bureau of Intergovernmental Relations 660 Apalachee Parkway'allahassee, Florida 32304