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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20128G1661996-10-0303 October 1996 Summarizes 960924 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Preliminary Responses to Staff RAI Concerning Request to Change EALs for TMI-1.List of Participants & Copy of Preliminary Response to RAI Encl 1999-09-29
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20203E0321999-02-11011 February 1999 Staff Requirements Memo Re 990211 Affirmation Session in Rockville,Md (Open to Public Attendance) Re Secys 99-044 & 99-045 ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20248H7001998-05-20020 May 1998 Staff Requirements Memo Re SECY-98-071,exemption to 10CFR72.102(f)(1) Seismic Design Requirement for TMI-2 ISFSI ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months 1999-09-29
[Table view] |
Text
m. -
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- g& Q'o,, UNITED STATES 8
o NUCLEAR REGULATORY COMMISSION h ;E WASHINGTON. D. C. 20555
.....+ W L 1 1 1984 MEMORANDUM FOR: Gus C. Lainas, Assistant Director for Operating Reactors Division of Licensing FROM: William V. Johnston, Assistant Director Materials, Chemical & Environmental Technology Division of Engineering
SUBJECT:
EVALUATION OF RECENT INCREASE IN OTSG PRIMARY TO SECONDARY LEAKAGE RATE AT TMI-1 In NUREG-1019 cnd Supplement No. 1 to NUREG-1019, we found the licensee's OTSG's acceptable for continued operation. By letters dated June 27, July 3, and July 6,1984, the licensee provided additional information.
This information does not affect the evaluation, conclusions or proposed license conditions in NUREG-1019 or Supplement No. 1 to NUREG-1019.
Enclosed is our evaluation.
William V. Johnston, Assistant Director Materials, Chemical & Environmental Technology Division of Engineering
Enclosure:
As stated cc: R. Vollmer D. Eisenhut J. Knight R. Rawson M. Wagner V. Benaroya C. McCracken J. Stolz R. Bosnak (H.%5 fiver 2 J. Van Vliet S. Pawlicki T. Sullivan P. Wu S. Kirslis L. Frank D. Sellers J. Rajan W7/7p/7/ g
,- J My-
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W' &
._ Safety Evaluation by The Office of Nuclear Reactor Regulation Related to Operation of Three Mile Island Unit No. 1 General Public Utilities Nuclear Corporation Docket No. 50-289
Background
In NUREG-1019 and Supplement No. 1 to NUREG-1019, we determined the once-through-steam generator (OTSG's)-had been repaired to their original licensing basis, that the applicable GOCs were met and, therefore, the OTSG's were acceptable for continued operation. By letters dated June 27 end July 3, 1984, the licensee provided additional information on i primary-to-secondary leakage rate. By letter dated July 6, 1984, the licensee provided updated information on the long' term corrosion test program.
Evaluation j
While in a cold shutdown condition, the licensee detected an increase in the background primary-to-secondary leakage rate of the B OTSG. During the
- September 1983 hot functional test, the background primary-to-secondary leakage rate had been established at 1.0 gph as discussed in Supplement No. 1
. to NUREG-1019 at pg. 22. Although the increase in leakage was less than that
[
' which would require inspection, the licensee opened the primary side of l - both OTSG's and conducted bubble, drip and eddy-current test (ECT) examinations.
' ECT examinations of approximately 150 tubes demonstrated that corrosion was not progressing or initiating. A total of approximately 15 tubes and/or plugs showed indications of minor leakage. Minor leakage of this magnitude is typical from plugs and anticipated from the repaired tubes. The unplugged tubes which were leaking were confirmed to be leaking between the tube and tubesheet, above the kinetic expansion repair joint. It was determined that one tube was leaking past the 6-inch repair joint sufficiently so that background leakage would have increased to an estimated 4 gph at operating I conditions. To maintain background leakage low, in addition to the leaking l
i
2-tube, two additional tubes were plugged for added precaution. Leakage of this type is anticipated as discussed in various sections of NUREG-1019 and ,
- Supplement No. 1 to NUREG-1019. The total amount of primary-to-secondary leakage is limited by the plant Technical _ Specifications and the proposed License Condition No. 4 on pg. 27 of NUREG-1019, Supplement No. 1.
By letter dated July 6, 1984, the licensee updated the long term corrosion test program. Tests which simulate actual plant ' conditions with water chemistry maintained at maximum anticipated impurity concentrations continue to show no evidence of crack propagation or initiation. The absence of crack propagation or initiation in these tests continue to support the conclusion of NUREG-1019 and Supplement No. 1 to NUREG-1019.
- Test Loop No. 1 simulated conditions which assumed that peroxide cleaning would not be conducted and that a continued source of thiosulfate contamination ,
would exist. Under these conditions, one pre-existing crack in a tube specimen taken from the TMI-1 OTSG showed crack propagation. No evidence of corrosion initiation of uncracked tube specimens was detected. These test results verify the applicability of the long term corrosion test program by demonstrating that corrosion continues to propagate in water chemistry conditions where it would -
be predicted to propagate.
Conclusions l' Based on the above evaluetion, we find that the information provided by
( letters dated June 27, July 3 and July 6, 1984 does not affect the l evaluation, conclusions, or proposed license conditions in NUREG-1019 L
or Supplement No. 1 to NUREG-1019.
i 1.
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i w-- --7--W't P'---T -- - '- -------+we** +-we-w-1*-a------- --ie--t ww-' + - *- - -* _--w- erw-e--e--m---m-tw--w-- m - -- - - -- - - ----- -w
1s-
.,wg Mile Island Unit t 7/16 SRI Fcx/Firo ct Inf rmation Throc mot:rcyclo riders startcd a small fire et the fcnce along 0-289 Centar the road in front of the TMI Information Center. 11.2 f i r . saas - <
quickly extinguished with no signi fi cant -dar.iage done.'
- jgllh,',tr hroo Mile Island Unit t 9-289 7/16 SRI Fax ( On 7/16/84, the licensee notified the resident inspector i. h i t . +
five (5) steam generator (SG) plugs (3 in SG-A and 2 i n Sc. -It ) g
- I were missing from the lower (outlet) head area. Thi2 pluq loca-t i tion-verification has been performed following the cepa.r..L'uovo-J' / ment of a plug from tube 148-35 to tube 65-38 in the c ip. 4 . (in-
/ let) head area of SG-A.
The licensee's review of the tube pluqqing records indicate that-
) these plugs were in SG tubes 10-62, 133-77 and 13i-15 ( sG - /- ) . and 4
12-51 and 42-16 (SG-B) since April, 1983. Of the 1207 LG tiehc a .
plugged in the two SGs, approximately 490 have been plu:.4 al uuing i
s the Westinghouse rolled plugs.
!hrosMileIslandUnitt 7/16 SRI Fax / Seismic Qualifi- Between 9:30 a.m. and 10:00 a.m., 7/16/84, licensen repscuenta-tives determined that differential current relays fur (1.o Emar-10-289 cation of Diesel Generator Relays gency Diesel Generators (EDG's) were no t soi smically qu..l i fi ed
,' (Category I). The relays lockout the EDG's (output t.: e..L ar trip and diesel mechanical trip) on a current imbalance i s, the LI4 l
- windings. The relays are manufactured by General Electsic for uso in Westinghouse switchgoar. Apparently, licenseo repre ms.lativos i
di scussions wi th these vendors confirmed that the rel.: f t. i i.n t a '. l e d
]i at THI-l were not designed for Seismic Category I usu.
- j The licensee made this dotermination subsequent to t i .. s uuu..nco earlier this year of an IHP0 (Instituto of Nuclear 1:1..nt opera-4 d tions) Sincificant Event Report for a similar problo.i ideati fied at Palisades. A 10 CFR 50.72 was made at 12:43 p.o.. 1/ 1../ C i .
i
$ crmant Yankee 7/16 SRI fax The licensee disclosed on 7/16/84 that RitR system in Id ;32-6
'N 50-271 was found to have an axial flaw in excess of 10% of 4.ho t hre. ugh j
wall dimensions. RHR Line 032 is part of the 20 inch ai..s *Lv.r i' suction line to the RHR pumps for shutdown coolinq apar.aticnu.
i' Weld 032-4 is located inside the drywell. The liccn.oo i.. utill ,
lj evaluating the type of repair that will be used to d i t. LI.a f l ate
' necessary. Two addi tional RHR system walds were ad.h is la tho
.ll sample of welds selected for examination.
6 i, Indian Point Unit 2 7/16 RI fax On 7/23, at 2:45 p.m., with the reactor defueled. i..am me t . ..t ipH 50-247 7/13 EMS call actuation of train A ESF occurred due to a spuriou.. c;: ; . . e . .1
~
signal to the safety injection manual actuation ro l-/.
Safeguards equipment loads did not sequence onto i t .. i r.0 Volt l
busses. Operators manually reset the nocessary eqose.a s.t.. Iho
.. licensee is investigating the cause of the spuriou.. . . :.ia l .
i MORNING REPORT - REGION I i
1 DATE 7/17/84 l
j Page 3 ll.icensse/ Facility Notification / Subject Description of Items or Events
!.imtrick Information Item Mr. Chilk, Mr. Bates, and Mr. Mazuzan, will go on zin i n f.>rnat i on tour of the Limerick site with the Senior Resident i n .g..:.. t o r on i
'IS 50-352/353 !
Tuesday, July 17, 1984.
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9 MORNING REPORT - REGION V ~. p
, DATE: JULY 17, 1984
- REGIONAL ACTION HOTIFICATION ITEM OR EVENT LCILITY
' FDLLOWUP PER MC 2515 -
)UTHERN CALIFORHIA TELEPHONE CALL / STEAM GEHERATOR TUBE LEAKS FROM RESIDENT A TUBE LEAK IN STEAM GENERATOR E-089 WAS MEASURED EDISON COMPANY INSPECTOR ON i
AT 33 GALLONS PER DAY OH JULY 16, 1984 AND AT 68 3 HGS 3 GALLONS PER DAY (0.05 GALLOHS PER MINUTE) OH' 1 50-362 7/16/84 JULY 17,1984. -THE REACTOR COOLANT GROSC ACTIVITY' IS 14 UCI/ GRAM WITH A DOSE EQUIVALAtlT 10DIHE ACTIVITY OF 0.35 UCI/ GRAM. TifE TEClit(ICAL
/ SPECIFICATION LIMIT FOR STEAM GENERATOR TUBE LEAKAGE N IS 720 GPD FOR ONE S/G OR 1 GPM TOTAL. A f.GPM TUBE I LEAK WOULD RESULT IN A DOSE RATE AT Tile SITE BoullDARY
/ OF ABOUT 0.005 MREN/HR. THE LICENSEE IS CLOSELY
/ MONITORIHG THE SITUATION AHD PLANS TO SilUT Tile UNIT
/ DOWH WELL BEFORE Tile TECH SPEC LIMIT IS REACllED.
\ Tile RESIDENT INSPECTOR IS ALSO ACTIVELY IllVOLVED
\ Ill FOLLOWING THIS NATTER.
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