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Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARRS-11-124, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE142011-07-28028 July 2011 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14 SVPLTR 09-0044, Day Response on Inadvertent Control Rod Withdrawal2009-09-21021 September 2009 Day Response on Inadvertent Control Rod Withdrawal SVPLTR 09-0027, Written Follow Up Report on Release of Radionuclide2009-07-0606 July 2009 Written Follow Up Report on Release of Radionuclide RS-08-073, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima22008-05-23023 May 2008 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima2 ML0216407762002-06-0707 June 2002 Offsite Dose Calculation Manual (OCDM) Required Action Not Met During Units 2/3 Main Chimney Particulate, Iodine, and Noble Gas Sampling System Inoperability ML17252A3201977-11-23023 November 1977 LER 77-047/03L-0 for Dresden Unit 3 Regarding During Normal Unit 3 Operation, Surveillance Program Review Revealed Violation of T.S.1.0.CC.b Maximum Combined Interval Time by 3.5 Days for HPCI Monthly Valve and Pump Operability ML17252A2881977-05-0303 May 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-8 ML17252A2911977-04-22022 April 1977 License Event Report - Rod Withdrawal at Approx. 44% Power, Discovered Rod Block Monitor Channels 7 and 8 Automatically Bypassed ML17252A2901977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-10 ML17252A2711977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-9 ML17252A2721977-04-20020 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-7 ML17252A2751977-03-23023 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2821977-03-0202 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2581977-01-20020 January 1977 Transmittal of Reportable Occurrence Report No. 50-249/1976-36 ML17252A2701976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 IR 05000249/20190761976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 ML17252A2461976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B ML17252A2451976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-25 in Accordance with Technical Specifications, Section 6.6.B ML17252A2391976-10-22022 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-20 in Accordance with Technical Specifications, Section 6.6.B ML17252A2411976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-18 in Accordance with Technical Specifications, Section 6.6.B ML17252A2401976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-19 in Accordance with Technical Specifications, Section 6.6.B ML17252A2231976-10-12012 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-15 in Accordance with Technical Specifications, Section 6.6.B ML17252A2261976-09-30030 September 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-17 in Accordance with Technical Specifications, Section 6.6.B ML17252A2361976-07-0101 July 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-1 ML17252A2101976-02-0505 February 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-3 in Accordance with Technical Specifications, Section 6.6.B IR 05000249/19750361975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1761975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1711975-08-15015 August 1975 Report of A.O. Per Section 6.6.A of the Technical Specifications Isolation Condenser High Flow Sensor Setpoint Drift IR 05000249/19750321975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A1741975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A4471975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings IR 05000249/19750311975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings ML17252A7861975-03-27027 March 1975 Report of Abnormal Occurrence Per Section 6.6.a of the Technical Specification - Exceeding Set-point on Main Stream Line Hi Hi Rad ML17252A8271975-02-14014 February 1975 Report of Abnormal Occurrence Per Section 6.6.A of the Technical Specification - Reactor Feed Pump 3C Pump Casting Vent Line Weld Leak ML17252A8361975-01-14014 January 1975 Report of 4 Inch Recirculation Bypass Line Inspection 2011-07-28
[Table view] |
Text
- ~r~!!:e~~~:*t~e~~~!~~8'.\
R.R. #1
Morris, Illinois 60450 *~
Telephone 815/942-2920 egufatqry*
........___R- -
.lf.V~. Cy.
BBS Ltr. 1177-50 Mr. James G. Keppler, Regional Dire:.~~--
D.irectora te .of Regulatory Operations - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen:Ellyn; Illinois 60137 ..-~
E~closed please find Reportable Occurrence report number This report is being submitted to your office in accordance .~wi-th ,the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B.
ffe~-c-
?' ,-:;.. ::;,
B. B. Stephenson v.*
St~tion.Superintendent Dresden Nuclear Power Station BBS :jo Enclosure cc: Director of Inspection & Enforcement DireGJo.r of Managem.ent Information & Program Control File/NRC J
.l.
888
'CONTROL BLOCK: ~--'L-....&--'-'--*.LI 1 .
---1 6
. e,LEASE PRINT AU REOlJiRED iN:FORMATION]
LICENSEE LICENSE EVEN.T NAME * . LICENSE NUMBER TYPE TYPE
@E] Lr I LI nlRls I 31 I oI o1-\1 oIo Io I o I o1-1 oI oI I 4 I 1 11 111 1 I I0I 31 7 8 9 14 15
- 25 26 30 31 . 32 REPORT . REPORT
, CATEGORY TYPE.' SOURCE DOCKET NUMBER . EVENT DATE REPORT DATE
@El CON}
7'*" 8*
I I I
- 57 . 58 w 59 LIJ 60 I61oI s I o 1-1 oI 21 AJ** 9s0**I
- 69.* t 1 J* 2**** I* _2* I ) I .1 I 674I I75o Lt P JQ..J.7* L100I EVENT DESCRIPTION
- *Jo'21 J. A routine surveillance aud:j_.t .conducted by sta_tion personnel ,:revealed that a number I 7 8 9 BO
@@] I of surveillance intervals had been inadvertently exceed.ed during the six-month.* I 7*'8 9~:--:--:--~~-~------....,..-----,,.....,..~~-.,..,...,~__,,.-......,_;,..:.....,.,,.,,.,..,..,.,,..,,__,___.,,..__..,.._.;.________. -.8-10 jbj41 *I *
- period following a Tech Spec revision '."hich Jiniited those intervals. Tech Spec I 7 8 .9 .. 80.
T lolsFB: 9!:.":.-----------------------------~-__;,,-_.___:_
I sectJon 1.0. c. C (a) and (b) .(which becam'e ef'fectTve in* May~ 1976) specified *that
_____,_~---....----8-10I (o]sl ~('-.'_(;;;..?_)-'.'-$._l.l_rv_.e_i'-.)-'_~'-a"'""'.n-'.~'-.,e_i_*n.....t_e_r_v_a_l_e_x_t_e_n_s_i_o_n_s~w;_e._r:.;....e......p._o_t_.,t_P....._e_x_c_e_e_d--'2-'-5_.%..;.,_;,.o"'"'J"""-t"""h-e--'i'-n'-t'-e,;,;;;:*12;:.:.;":?';.::.:**~;::.~;;.::;-!.~,.:.;;,_il:;.;,11_d;;;;;...*.;..*-:::..*..:JI 7* 8 9 PRIME 80 SYSTEM CAUSE COMPONENT ;coMPONENT. * (Continued)
. CODE *cooE .. COMPONENT CODE
- SUPPUEA MANUFACTURER VlOLAOON
[§Illzlzl L~J Iz I z I z I zI zI z117. ..
12 .
~* I z 19 19 I 9 I ~
7 8 9 10 . 11 43. 44 47 48 CAUSE* DESCRIPTION .
jo Isl ~I__s_t_a_t_i_o_n_s_u_rv_._e_i_ll_..a_n__c_e_s_a_r_e_s_c_h_e_d_u_l_e_d_*_a_n_d_._u_p_d_a_te_d_w_e_e_k_l_y_o_n_a__c_o_m_p_u_t_e_r_._*--F_r_o_m_t_h_e...;,..;....._--11 7 8 9. . 80 joj9j j t.ime surveillance s~heduling by compute:r;. began until December 6, 1976, surveillance . I ,
- 7. 8 9 80
~ ~I_ ....s_c_h_e_d_u_l_i_n.;:;.g_w_a_s_p:;...e_r_f_o_rm_e_d_o_n_a_*_f_r_e...:q;...u_e_n_c~y_b_a_s_is_._T_h_i_*s_m_e_a_n_t_t_h_a_t_*_a_m_o_n__t_h_l.;_y_*_i_t_e_m_ _.;....._JI 7 8 9 FACILITY *.METHOD OF (Continued) 80 EEJ ~
STATUS \Iii POWER I 0I9 I3 I OTHER STATUS
~-N_A_ _ __., ,I
~ NA.
DISCOVERY DESCRIPTION 7 8 ... 9. 10 12 13 .. 44 ,,45 *46 80 FORM 'OF ACTIVITY CONTENT
- RELEASED OF RELEASE AMOUNT OF ACTIVITY . . I* NA .. LOCATION OF RELEASE I fil~l 7 .. 8 ..
lzJ .. uJ 9
10 t NA 1~1-*_...;.;.;.;_ _ __....;;.;..._ _ _ _*~44 1 4~5-----...,...----------------""ao PERSONNEL ExP.OSURES ;,: " *,
/'
. NUMBER TYPE DESCRIPTION *
[ill] l OJ. 0.1 0 I L~J NA.:
7*. 8 9 .. 11 ..12 13 80 PERS'ONNEL- INJURIES
. NUMBER 'OESCRIPT.iON EEJ I 01 01 0111 12L-~N_A__~--------~--~~-------------------~-------~
- 7. 8 9 80 OFFSITE CONSEQUENCES EE
- 7. 8 9 NA.
80 LOSS OR DAMAGE TO . FACILITY TYPE DESCRIPTION
(!fil;.Uj . NA 7 0*s * .10 80 PUBLICITY'
.. filZ] NA.
80 7 8 9 ADDITIONAL FACTORS
~ NA*
7 8 9 80 NAME; _ _.;,;;,Ra=l*p.;;;;h;,_V~*~*....;N;,;.;i;;;..mm..;.....;e;,_r;___ _. , . . . - - - - - - - - -
- PHONE:_E_X~.T_._2_2_2_ __
- EVENT DESCRIPTION (Continued)
(b) that the total combined interval of any*3 consecutive interirals was not to exceed 3. 25 times the specified surveill~nce inte.rval.. Sur:ve:i,llance interval vioJ~t.iq_i).s wer:,¢. identified in both categories .dE!$C.r,ibed above* I t was .also noted during the audit that certain surveillanc.e items had not been* conducted.*.
(Seec*attached. list for titles of surveillance items,. involved-.) (50-249/1976'-36)
CAUSE DESCRIPTION (Continued) was scheduled for the same time period each month regardless of when it had been performed the previous month. Consequently, if a monthly item, for exa,mple, were performed.nine.days "early," by the time the.item ..appeared on the .schedule -to.be performed ag_ain, the interval plus 25% would have alreadY._* e_lapsed, resulting in a Teel( Sp*ec violation.
-~Y Ju.ne, 197.6, a course of action .had been c:l.ecided upon _whi.ch woµld ensure t.ha;.t.. surveilla.nce intervals did not exceed t:he_.*re:vis:ed .. limits. First, *the *con'fpU'ter
. w:as . .to b.e ;t';eprogrammed to schedule suryeil~aru::.es on a d,ate-:.cione :ra.theL..than .o.n .a ..'
frequency basis. A formal request for program *niodifications was initi_ated in* July, 1916. These modifications had been programmed, tested, and successfully implemented by December, 1976. Secondly, a base date (desirable surveillance date) was to be assigned to each regularly scheduled surveillance item to provide a stable reference po.int. This. phase has been substantj ally completed., and- final base. date ipfonn~.tion is expected to be entered into the computer no later than February 28~ 1977.
Successful implementation of the program described above will permit a prompt comparison to be made between a given surveillance item's scheduled date and its base date. In this manner it will be possible to determine readily whether a surveillance item has been performed within the required inte.rval. To ensure that any discrepancy is identified in a timely manner, all surveillance items will be re-viewed on a monthly basis.
The number of surveillance items involved in this event represented less than*
1% .of the t_otal nllinber of surveillances conducted duringrt:he period in-"-"ques'tion
- The safety impiications of this event, therefore, we+e c<;>,nsidered to be. minimal>.
Surveillance interval violations were identified concurrently for all three units at D.r.esden.
- ~****-- - .--.-.*--:;-,-**--.~ ... *{*--***- * - -~; *1-.?:--:---*-:, *** .-.-*- .. ;*":~-- *-*--- .--.c.--~ *-:-**-**** *** * *** * :"":~*: ...~- ...*--.-..---.::::*:-:.-;::-;-:":":"*:-':":~***t .* ,.,.>4 *. --";"~-
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~-- INSTRUMENTATION..
A,REA
. suRv. ~ *sURv .* *F . '*tECH.*
EREQ. ITEM.NO. Q.
- DES~RXPTIQN DATES OF EXCEEDED.LN-TERVA'
- APRM Upscale, In6perafive: & Downscale 4._2.1 8-17-76 To 9-28-76 -.:::*;
- . Scram 7-19-76 To 10-28-76 M. 007 3 APRM Upscale, -Inoperative & Downscale 4.2~1 :8-17-76 To 11-:29-76 4.1. 2 016: .. *1 .Sfilf:Upscal.e':Rod. Bfock 4.2.1 11 76. Tp H'-13::)Q___ .
-M*** .. 018 * ** 3 .RBM *upsGa*f:e -~nd Downs*cale: Rod. ;Block . 4.2.1 8-7-76 Jo l-l:-1.7-]~.. ---*
Block-M 019 l APRM Flow Bias Upscale & *nownscale *.Rod 8-17-76 To 9-:;-28-:7.6 ..
.... -~~ :
- M 0,19 *3 APRM Flow: Bias Upscale ..& Downscale Rod Block 4.2.1 6-18-76 To 9~28-76*1-19~1a To 10-28-76;8~17 To ll-29-<
M 02,3 1 Main Steam Line High Flow Isolation_ 4.2.1 6...:19-76.To 7-30..:. 7.6
.IiC2.J.a.e:J.01 ..
M 028 1
- Isolation Condenser Steam Line High Flm 4.2.1 9-15-76 To 10-24-76*. ',':;.'*
~
Isolatio1 '.
M 029 1 Isolation Condenser Condensate Line Flrn 4.2.1 9-15-76 To 10-24_:.76 M 042 1 Containnient Spray In~erio~k ECCS * (2) *' 4. 2 .1 8-17-76 *To 9-30--76 M 042 3 Containment Spray Interlocks ECCS (2) 4. 2.1 ... 8-:17-76 To 12-4-76 M 051 3 Rx Bu.ilding CCW .Radiation Monitor 4.8.C 6-:14...:76 To 9-29-76**
M 052 1 _Servic:e Water *R.aaiatfon *:Monitor 4.8.C ... *. 6-'-14.;_76 *to 7-23--76
.... **. *F.Q ... ~.-fype. *of F~eq~~.ncy* ViOJ..ation.: . . .... * - :.: .*. - * ..... *
. : . **1 . "'". 1 Frequency Interval Plus 25% Exceeded . . * .* .....
~.
- . * ' ** 3 *.,. 3. Tµne~ Nprmal Interval Plus Single* Interval 25% Exceeded. . *.*
'M c. ~sse_d Surveillance v*
,.. :*. 1.* .' *. - . : /,.
- .*. . j **. .: :,. . *:: :t..- ..
. <*~~l >./'. =>-- : >*. .. ' .....
. ! . . .. ~-
.~-
OP.ERATING A,REA SURV.
.'*'.rECH ** *
'LREQ. .ITEM NO . 0. *sPEC~
- DATES OF EXCEEDED.lN-TERVA:.
012 3 Core Spray Pump Operability 6-18-76 Io 9-27-76 M. 013 .3 Core Spray M.O. Valve Op~rability 4.5.A M ..... .9.!.:'L:.c.. )1 __ ..Jlj..gJ:i. ~~i=,J::-gy PJpirig Inspection* 4.11 Not Done* June :Thru -Sept ..
--i
- Pump Q.{)erab.i,li-~y * . . . , ... 4.5.A 6-18-76 To-9~27~76
.M .* 017 3 : -LPCI M. 0. Valve Operability 4.5.A 6-18.:..., 76 To_, sJ-:-)7.~76 .
M 022 M Torus/Drvwell *Vacuum Bre<itker Cvclirti? 4. 7.A 4 a Not Done Ma'l or June 022 1 Torus/Drywell Vacuum Breaker Cycling 4.7.A.4.a
8-8-76 To 9-30-76
,. i 02_3 i 1 MSIV Trip and Timing 4~7.D 5-3-76 T6 8-29-76
.:...,_- 6-ll-76:To 7-~1~76 M* 028 1 HPCI Pump Oi:ierabilitv 4 . .s:c;:***:-- ~ 7-2i-76 To 9~5-76' .
- , .... 6~11-76 To 7-21-l6*
... M 029 1 HPCI M.O. Valve Operability 4.5.C 7-21-76 To ~-5-76 *
. Q 030 1 HPCI Flow Test* 4.5.C * . 5-4-76 To 9~5~76
. :_g:
- 047 . M Abnormal Procedure Dd:lL Npt Done* Since. 5-4~ 7.6 ** .
. *~ .
. 1*
.~-: .*
. ~t
-*--.*.-. - **
" .. *F.Q *. ~.Type of Frequency" VicU.ation: .. ***- :: .*.: . ..*....
- * :1* * .. 1 Frequency Interval *Plus 25% Exceeded 3* .. 3 Times Normal. Interval Plus Single Interval 25% Exceeded .
,:... :._':: *. "M
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RAP-CHEMISTRY .. ;.
A.REA SURV. S.URV. * *F .
'*TECli;-
'EREQ. * . ITEM .NO. Q. ..SPEC~
- DATES OF: EXCEEDED .LN-TERVA
- . ~ ... Reac.tor Water: ~S.91:;_<?.Pi.~: ..4.'6.C.l.b 9-15-76 To_l0-28~16 *
.. ** *,,.. . . 'l._._ '.**. .. , ..... *..*. -. -~~ ..
i-------+-...-.--~~r--r--~--~~~~~~~~~~~~~~~~~-t-~~~~~-t~~~~~--~.;.;...~_,.;..--~----~
.. *... _* .. ..*\: .
=
. . *F.Q *.. .Type of Frequency* Vi~ation: .. : .*: - . --:-*.*** .....
- *_ ** * * *1 .... 1 *Frequency Inter~al Plus 25% Exceeded*
. ... 3 *~ 3 Times Normal Interval Plus Single. Interval 25% Exceeded
'M c. Miss.ed. Surveillance