Letter Sequence Approval |
|---|
|
Results
Other: AECM-83-0146, Forwards Response to Five of Six Items Contained in Re Util Work Addressing Containment Issues.Evaluation of Condensation Oscillation Loads Produced by Discharges from RHR HX Relief Valve Will Be Completed by Late Apr, AECM-84-0443, Forwards Approach to Chugging,Assessment of RHR Steam Discharge Condensation Oscillation in Mark III Containments, Per 830323 Commitment.Ae Evaluation Will Be Completed by mid-Dec 1984, AECM-85-0018, Forwards Evaluation of RHR Relief Valve Condensation Oscillation Loads on Structures & Piping.Info Demonstrates That All Loads Which Could Be Produced by Actuation of RHR HX Relief Valves Acceptable, AECM-85-0046, Provides Basis That Weir Wall Overflow Following Postulated Inadvertent Upper Containment Pool Dump Does Not Involve Significant Safety Problem.Evaluation Plans & Justification Provided, AECM-85-0233, Forwards Weir Wall Overflow Probability Analysis. Because of Very Low Probability of Occurrence & Leak of Safety Significance for Worst Case Postulated Overflow (Ref AECM-85/0046),corrective Actions Not Warranted, AECM-85-0376, Submits Info Re Wier Wall Overflow,Per 851021 Request.Topics Addressed Include Overflow Effect Upon Uninsulated Drywell Piping & Evaluation of Recirculation Piping Relative to Predicted Water Level.Ge Rept Re Containment Issue Encl, AECM-86-0143, Clarifies Planned Resolution of Possible Loads from Chugging Caused by Steam & Gas Venting Into Suppression Pool Through RHR Relief Valve Discharge Line.Rhr HX Vent Line Header Will Have Dedicated Discharge Line to Pool, ML20097F052, ML20137Q230, ML20204J145
|
MONTHYEARAECM-83-0146, Forwards Response to Five of Six Items Contained in Re Util Work Addressing Containment Issues.Evaluation of Condensation Oscillation Loads Produced by Discharges from RHR HX Relief Valve Will Be Completed by Late Apr1983-03-23023 March 1983
Forwards Response to Five of Six Items Contained in Re Util Work Addressing Containment Issues.Evaluation of Condensation Oscillation Loads Produced by Discharges from RHR HX Relief Valve Will Be Completed by Late Apr
Project stage: Other
ML20137Q2301983-07-31031 July 1983
Containment Issue Isolation Transient
Project stage: Other
ML20097F0521984-03-31031 March 1984
Approach to Chugging,Assessment of RHR Steam Discharge Condensation Oscillation in Mark III Containments
Project stage: Other
AECM-84-0443, Forwards Approach to Chugging,Assessment of RHR Steam Discharge Condensation Oscillation in Mark III Containments, Per 830323 Commitment.Ae Evaluation Will Be Completed by mid-Dec 19841984-09-0707 September 1984
Forwards Approach to Chugging,Assessment of RHR Steam Discharge Condensation Oscillation in Mark III Containments, Per 830323 Commitment.Ae Evaluation Will Be Completed by mid-Dec 1984
Project stage: Other
AECM-85-0018, Forwards Evaluation of RHR Relief Valve Condensation Oscillation Loads on Structures & Piping.Info Demonstrates That All Loads Which Could Be Produced by Actuation of RHR HX Relief Valves Acceptable1985-01-24024 January 1985
Forwards Evaluation of RHR Relief Valve Condensation Oscillation Loads on Structures & Piping.Info Demonstrates That All Loads Which Could Be Produced by Actuation of RHR HX Relief Valves Acceptable
Project stage: Other
AECM-85-0046, Provides Basis That Weir Wall Overflow Following Postulated Inadvertent Upper Containment Pool Dump Does Not Involve Significant Safety Problem.Evaluation Plans & Justification Provided1985-02-25025 February 1985
Provides Basis That Weir Wall Overflow Following Postulated Inadvertent Upper Containment Pool Dump Does Not Involve Significant Safety Problem.Evaluation Plans & Justification Provided
Project stage: Other
ML20126J2671985-06-11011 June 1985
Forwards Request for Addl Info Re Steam Condensing Mode of RHR Sys.Info Requested by 850715
Project stage: RAI
AECM-85-0287, Responds to NRC 850611 Request for Addl Info Re Steam Condensing Mode.Listed Methods for Predicting Chugging Will Be Evaluated.Evaluation Scheduled for Completion by 8512201985-09-13013 September 1985
Responds to NRC 850611 Request for Addl Info Re Steam Condensing Mode.Listed Methods for Predicting Chugging Will Be Evaluated.Evaluation Scheduled for Completion by 851220
Project stage: Request
AECM-85-0233, Forwards Weir Wall Overflow Probability Analysis. Because of Very Low Probability of Occurrence & Leak of Safety Significance for Worst Case Postulated Overflow (Ref AECM-85/0046),corrective Actions Not Warranted1985-10-0404 October 1985
Forwards Weir Wall Overflow Probability Analysis. Because of Very Low Probability of Occurrence & Leak of Safety Significance for Worst Case Postulated Overflow (Ref AECM-85/0046),corrective Actions Not Warranted
Project stage: Other
AECM-85-0376, Submits Info Re Wier Wall Overflow,Per 851021 Request.Topics Addressed Include Overflow Effect Upon Uninsulated Drywell Piping & Evaluation of Recirculation Piping Relative to Predicted Water Level.Ge Rept Re Containment Issue Encl1985-11-27027 November 1985
Submits Info Re Wier Wall Overflow,Per 851021 Request.Topics Addressed Include Overflow Effect Upon Uninsulated Drywell Piping & Evaluation of Recirculation Piping Relative to Predicted Water Level.Ge Rept Re Containment Issue Encl
Project stage: Other
AECM-86-0012, Discusses Status of Util Activities in Response to NRC 850611 Request for Addl Info Re Review of Possible Condensation Oscillation Loads from Chugging. Dedicated Lines from RHR HX Noncondensible Vents Preferred Resolution1986-01-28028 January 1986
Discusses Status of Util Activities in Response to NRC 850611 Request for Addl Info Re Review of Possible Condensation Oscillation Loads from Chugging. Dedicated Lines from RHR HX Noncondensible Vents Preferred Resolution
Project stage: Request
AECM-86-0143, Clarifies Planned Resolution of Possible Loads from Chugging Caused by Steam & Gas Venting Into Suppression Pool Through RHR Relief Valve Discharge Line.Rhr HX Vent Line Header Will Have Dedicated Discharge Line to Pool1986-05-16016 May 1986
Clarifies Planned Resolution of Possible Loads from Chugging Caused by Steam & Gas Venting Into Suppression Pool Through RHR Relief Valve Discharge Line.Rhr HX Vent Line Header Will Have Dedicated Discharge Line to Pool
Project stage: Other
AECM-86-0175, Corrected Response to 860326 Request for Addl Info Re Listed Humphrey Concerns,Including Addl Submerged Structure Loads & Containment Open Area,Correcting Omission of Page 2 from Attachment 31986-08-14014 August 1986
Corrected Response to 860326 Request for Addl Info Re Listed Humphrey Concerns,Including Addl Submerged Structure Loads & Containment Open Area,Correcting Omission of Page 2 from Attachment 3
Project stage: Request
ML20204J1451987-03-23023 March 1987
SER Supporting Licensee Responses to Humphrey Concerns on Safety of Mark III Containment Design
Project stage: Other
ML20204J1161987-03-23023 March 1987
Forwards SER Re Licensee Responses to Humphrey Concerns on Mark III Containment Design.Humphrey Concerns Satisfactorily Resolved.Licensee Will Continue to Prohibit Use of RHR Steam Condensing Mode Until Design Mods Implemented
Project stage: Approval
1985-11-27
[Table View] |
Text
-
March 23, 1987
- Docket No.: 50-416 DISTRIBUTION
+6% BGrimes Mr.' Oliver D. Kingsley, Jr.
NRC PDR JPartlow Vice President, Nuclear Operations LPDR NThompson System Energy Resources, Inc.
PD#4 Reading LKintner/BSiegel
. Post Office Box 23054 RBernero-JUnda Jackson, Mississippi 39205 Young,'0GC M0'Brien EJordan ACRS(10)
Dear Mr. Kingsley:
SUBJECT:
SER RELATING TO HUMPHREY CONCERNS RE: GRAND GULF NUCLEAR STATION, UNIT 1 By letter dated May 8,1982, Mr. John Humphrey, a former General Electric Company engineer, notified the licensee (Mississippi Power & Li now Systems Energy Resources, Inc.)ght Company of certain prior to December 20, 1986, safety concerns regarding the Grand Gulf Nuclear Station Mark III containment design (Humphrey Concerns). The licensee provided responses to the Humphrey Concerns which were evaluated by the staff in the Grand Gulf Nuclear Station Safety Evaluation Report (NUREG 0831) Supplement Nos. 2, 3 and 4.
In SSER 4 staff concluded based on its review to date that adequate safety margin in the GGNS Mark III containment existed to pennit full power operation, pending completion of the staff's confirmatory review of the issue. The licensee has provided additional submittals regarding the Humphrey Concerns in response to requests by the staff for additional information.
The NRC staff has reviewed the information submitted by the licensee as well as generic submittals re The staff's safety evaluation report (SER) garding Mark III containments.
is enclosed. The staff concludes that all the Humphrey Concerns regarding the Mark III containment design have been satisfactorily resolved for GGNS-1. As a part of this resolution, the licensee will continue to prohibit the use of the RHR steam condensing mode until design modifications are made to eliminate the routing of non-condensible gases from the condensing steam to the RHR discharge line.
(See Pages 8-11 of the enclosed SER).
- driginal syn,,g Lester L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing 4
i'
Enclosure:
As stated cc w/ enclosure:
See next page PD#4 PDf4/D LKintner:ca WButler W 3 /2f/87
}/g87 8703270177 870323 PDR ADOCK 05000416 p
PDR
3m=
- p neauq%[
' UNITED STATES
~
E NUCLEAR REGULATORY COMMISSION n
,h WASHINGTON, D. C. 20565 March 23, 1987 Docket No.: 50-416 Mr. Oliver D. Kingsley, Jr.
Vice President, Nuclear Operations System Energy Resources. Inc.
Post Office Box 23054 Jackson, Mississippi 39205
Dear Mr. Kingsley:
SUBJECT:
SER RELATING TO HUMPHREY CONCERNS RE: GRAND GULF NUCLEAR STATION, UNIT 1 By letter dated May 8,1982, Mr. John Humphrey, a former General Electric Company engineer, notified the licensee (Mississippi Power & Linow Systems Energy of certain
' prior to December 20, 1986, safety concerns regarding the Grand Gulf Nuclear Station Mark III containment design (HumphreyConcerns). The licensee provided responses to the Humphrey Concerns which were evaluated by the staff in the Grand Gulf Nuclear Station SafetyEvaluatiorReport(NUREG0831)SupplementNos.2,3and4 In'SSER 4 i
staff concluded based on its review to date that adequate safety margin in the GGNS Mark III containment existed to permit full power operation, pending completion of the staff's confirmatory review of the issue. The licensee has provided additional submittals regarding the Humphrey Concerns in response to requests by the staff for additional information.
The NRC staff has reviewed the information submitted by the licensee as well as generic submittals regarding Mark III containments. The staff's safety evaluation report (SER) is enclosed. The staff concludes that all the Humphrey Concerns regarding the Mark III containment design have been satisfactorily resolved for GGNS-1. As a part of this resolution, the licensee will continue to prohibit the use of the RHR steam condensing mode until design modifications are made to eliminate the routing of non-condensible gases from the condensing steam to the RHR discharge line.
(See Pages 8-11 of the enclosed SER),
Sincerely, Lester L.
intner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
~
l Mr. O!!ver D. Kingsley, Jr.
System Energy Resources. Inc.
Grand Gulf Nuclear Station (GGNS) cc:
Mr. Ted H. Cloninoer Mr. C. R. Hutchinson Vice President, Nuclear Enaineering GGNS General Manager and Support System Energy Resources, Inc.
i System Energy Resources, Inc.
Post Office Box 756 Post Office Box 23054 i
Port'Gibson, Mississippi 39150 Jackson, Mississippi 39205 j
Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 l
State of Louisiana Nicholas S. Reynolds, Esquire 70804 Baton Rouce Louisiana Bishop.Liberman, Cook,Purcell;i Office of the Governor and Reynolds l
State of Mississippi 1200 17th Street, N.W.
Jackson, Mississippi 39201 Washington, D. C.
20036 j
Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance i
Jackson, Mississippi 39205 Middle South Utilities System i
Services Inc.
P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management j
Mississippi Department of Natural Mr. John G. Cesare Resources i
Director, Nuclear Licensing and' Safety Bureau of Pollution Control System Energy Resources Inc.
Post Office Box 10385 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 Alton B. Cobb, M.D.
Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1A54 Jackson, Mississippi 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 2. Box 399 Port Gibson, Mississippi 39150 Regional Administrator, Region II U.S. Nuclear Regulatory Connission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. James E. Cross GGNS Site Director System Energy Resources, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150
