|
---|
Category:Letter
MONTHYEARIR 05000255/20244022024-09-0606 September 2024 Public: Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2024402 PNP 2024-029, Notice of Payroll Transition at Palisades Nuclear Plant2024-08-15015 August 2024 Notice of Payroll Transition at Palisades Nuclear Plant PNP 2024-032, Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-07-31031 July 2024 Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations ML24206A0572024-07-25025 July 2024 PRM-50-125 - Letter to Alan Blind; Docketing of Petition for Rulemaking and Sufficiency Review Status (10 CFR Part 50) PNP 2024-033, Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-07-24024 July 2024 Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations PNP 2024-031, Response to RIS 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-07-18018 July 2024 Response to RIS 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000255/20240112024-07-15015 July 2024 Nuclear Plant - Restart Inspection Report 05000255/2024011 PNP 2024-027, Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2024-07-0909 July 2024 Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24183A1382024-07-0202 July 2024 Tribal Letter - Lac Du Flambeau Band of Lake Superior Chippewa Indians ML24137A0142024-07-0202 July 2024 OEDO-24-00011 - 2.206 Petition for Misuse of Palisades Decommissioning Trust Fund (EPID L-2023-CRS-0008) - Letter ML24183A1392024-07-0101 July 2024 Tribal Letter-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24155A0032024-07-0101 July 2024 Kathy Kowal, Us EPA Region 5-Palisades-NOI to Cibdyct Scoping Process and Prepare an EA EPID L-2024-LNE-0003 ML24183A1502024-07-0101 July 2024 Tribal Letter - Prarie Band Potawatomi Nation ML24183A1442024-07-0101 July 2024 Tribal Letter - Menominee Indian Tribe of Wisconsin ML24183A1312024-07-0101 July 2024 Tribal Letter-Citizen Potawatomi Nation ML24183A1302024-07-0101 July 2024 Tribal Letter-Chippewa Cree Indians of the Rocky Boys Reservation ML24183A1452024-07-0101 July 2024 Tribal Letter - Miami Tribe of Oklahoma ML24163A2602024-07-0101 July 2024 Randy Claramunt, Michigan DNR-Palisades-NOI to Conduct Scoping Process and Prepare an EA EPID L-2024-LNE-0003, Docket No.50-0255 ML24183A1592024-07-0101 July 2024 Tribal letter-Sokaogon Chippewa Community ML24152A1952024-07-0101 July 2024 Carin Speidel, Acting Division Director, Environmental Health - Palisades - Noi to Conduct Scoping Process and Prepare an EA EPID No. L-2024-LNE-0003, Docket No. 50-0255 ML24152A1992024-07-0101 July 2024 Richie Garcia, Water Filtration Supervisor-Palisades-NOI to Conduct Scoping Process and Prepare an EA EPID No. L-2024-LNE-0003 Docket No. 50-0255 ML24183A1602024-07-0101 July 2024 Tribal Letter - Turtle Mountain Band of Chippewa Indians ML24183A1322024-07-0101 July 2024 Tribal Letter-Fond Du Lac Band of Lake Superior Chippewa ML24156A0222024-07-0101 July 2024 Initiation of Scoping Process to Prepare an Environmental Assessment for the Environmental Review of Holtec Decommissioning International, Llc’S Licensing and Regulatory Requests for Reauthorization of Power Operations at Palisades EPID L-2 ML24155A0102024-07-0101 July 2024 Quentin L. Messer Jr., Michigan Econ-Palisades-NOI to Conduct Scoping Process and Prep an EA-EPID No. L-2024-LNE-0003 Docket No.50-0255P ML24163A2392024-07-0101 July 2024 Sara Thompson, Michigan DNR-Palisades-NOI to Conduct Scoping Process and Prepare an EPID No. L-2024-LNE-0003-Docket No. 50-0255 ML24163A0832024-07-0101 July 2024 Ltr to R Schumaker Shpo Re Initiation of Scoping Process, Section 106 Consult for Env Rev of HDI, LLC Request for Reauth of Power Operations at Palisades Nuclear Plant ML24183A1572024-07-0101 July 2024 Tribal Letter - Saint Croix Chippewa Indians of Wisconsin ML24183A1532024-07-0101 July 2024 Tribal Letter Quechan Tribe of the Fort Yuma Indian Reservation ML24183A1432024-07-0101 July 2024 Tribal Letter- Match-e-be-Nash-She-Wish Band of Pottawatomi Indians ML24183A1492024-07-0101 July 2024 Tribal Letter - Pokagon Band of Potawatomi Indians ML24163A0822024-07-0101 July 2024 Ltr to J Loichinger Achp Re Initiation of Scoping Process, Section 106 Consult for Env Rev of HDI, LLC Request for Reauth of Power Operations at Palisades Nuclear Plant ML24152A1972024-07-0101 July 2024 Mayor Annie Brown, South Haven-Palisades-NOI to Conduct Scoping and Develop an Environmental Assessment for the Palisades Nuclear Plant Reauthorization of Power Operation ML24163A0552024-07-0101 July 2024 Rebecca Held Knoche NOAA-Palisades-NOI to Conduct Scoping Process and Prepare an EA - EPID No. L-2024-LNE-0003-Docket No. 50-0255 ML24183A1342024-07-0101 July 2024 Tribal Letter-Grand Portage Band of Lake Superior Chippewa ML24183A1262024-07-0101 July 2024 Letter to R. Yob, Grand River Bands of Ottawa Indians-Initiation of Scoping Process for Env Review of Holtec Decommissioning Intl, LLC Request for Reauth of Power Ops at Palisades ML24183A1582024-07-0101 July 2024 Tribal Letter Sault Ste. Marie Tribe of Chippewa Indians ML24183A1292024-07-0101 July 2024 Tribal Letter-Bois Forte Band ML24183A1242024-07-0101 July 2024 Letter to B. Hamlin, Burt Lake Band Re Initiation of Scoping Process for the Env Review of Holtec Decommissioning Intl, LLC Request for Reauth of Power Ops at Palisades ML24183A1362024-07-0101 July 2024 Tribal Letter - Keweenaw Bay Indian Community ML24183A1412024-07-0101 July 2024 Tribal Letter-Little River Band of Ottawa Indians ML24183A1512024-07-0101 July 2024 Tribal Letter-Prairie Island Indian Community ML24183A1462024-07-0101 July 2024 Tribal letter-Mille Lacs Band of Ojibwe ML24183A1282024-07-0101 July 2024 Tribal letter-Bay Mills Indian Community ML24183A1352024-07-0101 July 2024 Tribal Letter-Hannahville Indian Community ML24183A1252024-07-0101 July 2024 Letter to G. Gould, Swan Creek Black River Confederated Ojibwa-Init of Scoping Process for the Env Rev of Holtec Decommissioning Intl, LLC Request for Reauth of Power Ops at Palisades ML24183A1542024-07-0101 July 2024 Tribal Letter Red Cliff Band of Lake Superior Chippewa Indians ML24183A1272024-07-0101 July 2024 Tribal Letter-Bad River Band of the Lake Superior Tribe of Chippewa ML24183A1472024-07-0101 July 2024 Tribal Letter - Nottawaseppi Huron Band of the Potawatomi ML24183A1422024-07-0101 July 2024 Tribal Letter-Little Traverse Bay Bands of Odawa Indians 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML18344A4142018-12-10010 December 2018 LER 1979-037-00 for Palisades Nuclear Plant, Two Manual Three Inch Containment Isolation Valves in Bypass Line Were Discovered to Be Locked Open 05000255/LER-2017-0022017-07-17017 July 2017 Reactor Protection System Actuation While the Reactor was Shutdown, LER 17-002-00 for Palisades Regarding Reactor Protection System Actuation While the Reactor was Shutdown 05000255/LER-2017-0012017-05-24024 May 2017 Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions, LER 17-001-00 for Palisades Nuclear Plant Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions PNP 2014-100, Cancellation of Licensee Event Report (LER) 2004-002, Leak Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations2014-11-19019 November 2014 Cancellation of Licensee Event Report (LER) 2004-002, Leak Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations PNP 2011-009, Special Report of Inoperability of Main Steam Line Gross Gamma Activity Monitor2011-02-10010 February 2011 Special Report of Inoperability of Main Steam Line Gross Gamma Activity Monitor ML0726101822007-09-14014 September 2007 Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capability ML0609002832006-03-30030 March 2006 Cancellation of Licensee Event Report 05-006, Inoperable Containment Due to Containment Air Cooler Through-Wall Flaws ML18347B2971998-05-19019 May 1998 Submit, NPDES Notification Report, Incident No. Pal-98-05-NC138 for NPDES Permit No MI0001457 Re Difference from Daily Maximum Effluent Limitation for Facility ML18348A9021989-02-0707 February 1989 LER 1988-005-01 for Palisades, Inadequate Procedure Results in Valve Testing During Prohibited Conditions ML18346A2471981-06-19019 June 1981 LER 1981-020-00 for Palisades Nuclear Plant, Pcs Unidentified Leakage Greater than 1.0 Gpm ML18346A2481981-05-13013 May 1981 LER 1981-015-00 for Palisades Nuclear Plant, Safety Injection Tank Boron Concentration ML18346A2491981-02-20020 February 1981 LER 1981-005-00 for Palisades Nuclear Plant, Update - Inoperable Diesel Generator ML18346A2501981-02-19019 February 1981 LER 1981-007-00 for Palisades Nuclear Plant, Inoperable Auxiliary Feedwater Pump ML18346A2511981-01-26026 January 1981 LER 1981-002-00 for Palisades Nuclear Plant, Inadequate Mounting of DC Distribution Panel ML18346A2521981-01-16016 January 1981 LER 1981-001-00 for Palisades Nuclear Plant, During Charging of Station Batteries, Output Breakers of Both Batteries Were Inadvertently Opened for Approximately One Hour ML18346A2531981-01-14014 January 1981 LER 1980-046-00 for Palisades Nuclear Plant, Hydraulic Snubber Failure ML18346A2541981-01-0707 January 1981 LER 1980-045-00 for Palisades Nuclear Plant, Low Condensate Makeup Inventory ML18347A8141980-10-10010 October 1980 LER 1980-037-00 for Palisades Nuclear Plant, Pipe Support Sway Struts Identified to Have the Potential of the Bushing Becoming Loose And/Or Disengaged from the Clamp End of the Sway Strut ML18347A8461980-08-27027 August 1980 License Event Report 1980-027-00 Re Gaseous Release, Extended Due Date of Reporting by Region III on 8/26/1980 ML18347A8471980-08-12012 August 1980 License Event Report 1980-024-00 Re Containment High Radiation Monitor ML18347A8481980-08-0808 August 1980 License Event Report 1980-023-00 Re Containment High Radiation Monitor ML18347A8491980-08-0808 August 1980 License Event Report 1980-022-00 Re Inoperable Nuclear Instrumentation ML18347A8501980-08-0606 August 1980 License Event Report 1980-021-00 Re Misaligned Containment Sump Valve ML18347A8521980-07-29029 July 1980 License Event Report 1980-020-00 Re Misaligned Control Rod ML18347B2071980-06-19019 June 1980 Licensee Event Report 80-018 Regarding Oil Level in Snubber No. 2 Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers ML18347B2081980-06-13013 June 1980 Licensee Event Reports 80-014, 80-015, and 80-016 Regarding Oil Level in Snubbers No. 5, 9, and 7 Were Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers ML18347B2091980-05-15015 May 1980 Licensee Event Report 80-012 Regarding Bottom Half of the Barrier for Fire Penetration HO-12 Was Missing During Inspection of Fire Barriers ML18347B2101980-05-14014 May 1980 License Event Report 1980-011-00 Re Improper Return-to-Service of Porv'S ML18348A9071980-05-12012 May 1980 Submittal of LER 1980-006-00 Purge Valve T-Ring Air Supplies ML18348A9051980-05-12012 May 1980 Submittal of LER 1980-008-00 Update of Valve Leakage ML18347B1411978-09-0606 September 1978 LER 1978-029-00 for Palisades Plant Re Lower Level of Hydrazine in Iodine Removal Tank Due to Approximately 6% of Drainage from the Tank T-102 ML18347B1421978-08-18018 August 1978 LER 1978-028-00 for Palisades Plant Re Containment Building Purge Valve T-Ring in CV-1806 Was Not Pressurized ML18347B1441978-08-11011 August 1978 LER 1978-022-00 for Palisades Plant Re Four Incore Alarms Following Reactor Start-up ML18347B1451978-08-10010 August 1978 LER 1978-021-00 for Palisades Nuclear Plant, Containment Purge Supply Valve CV-1808 Failed to Open During Monthly Test ML18347B1491978-07-20020 July 1978 LER 1978-024-00 & LER 1978-025-00 for Palisades Nuclear Plant, Steam Generator Ph Dropped to 8.02 & One of Two Heaters for T-53B (Concentrated Boric Acid Tank) Failed ML18347B1781978-04-28028 April 1978 License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal ML18347B1801978-04-19019 April 1978 License Event Report 78-008: Cycle 2 Core Axial Power Distribution Limits of TS 3.10.3 Were Exceeded by Approximately 12% for Steady State Operation During Cycle 2 ML18347B1811978-03-27027 March 1978 License Event Report 1978-007-00 Relates to Electrical Connectors Inside of Containment ML18347B1841978-03-13013 March 1978 Two Updated License Event Reports, LER-78-004 & LER-78-006 ML18348A1951978-03-0202 March 1978 License Event Report 1978-006-00 Re Shipping Cask Movement ML18347B1851978-03-0202 March 1978 License Event Report 1978-005-00 Re Steam Generator Level Instrumentation ML18348A1961978-03-0101 March 1978 License Event Report 1978-004-00 Re Steam Generator Pressure Instrumentation ML18348A1981978-02-0101 February 1978 License Event Report 1978-003-00 Re CV-3025 Failed Closed ML18348A1971978-02-0101 February 1978 License Event Report 1977-065-00 Re Operation in a Degraded Mode Permitted by a Limiting Condition for Operation ML18348A1991978-01-20020 January 1978 LER 1977-063-00 Re Iodine Removal System Hydrazene Tank, LER 1978-001-00 Re Containment Door Interlock Failure & LER 1978-002-00 Re Setpoints of Five Valves Were Outside Band ML18348A2001978-01-0606 January 1978 License Event Report 1977-062-00 Re Iodine Removal System Naoh Tank (T-103) ML18348A2011978-01-0606 January 1978 License Event Report 1977-064-00 Re HPSI Pump P-66B ML18348A2021977-12-21021 December 1977 LER 1977-054-00 Re Four Coincident In-Core Alarms, LER 1977-057-00 Re Pressure Set Point for Channel C, & LER 1977-058-00 Re De-Energized R Bus ML18348A2031977-12-16016 December 1977 License Event Report 1977-055-00 Re Loss of Off-Site Power and Plant Trip ML18348A2041977-12-12012 December 1977 License Event Report 1977-056-00 Re Gaseous Waste Discharge 2018-12-10
[Table view] |
Text
- J LICENSEE EVENT. (LERt U.S. llUCLIAll lllQULA TOllY CQllmtt9!0fl Olle llO. J1111-01CW IXPlllll:
11'1 * 'ACILITY NAttt 111 PALISADES PLANT TITLI I., INADEQUATE PROCEDURE RESULTS IN VALVE TESTING DURING PROHIBITED CONDITIONS IYINT DATI Ill 111 llll'OllT OATI 171 OTMlll 'ACILITIU -OLVID *1 NA.MU N/A* o I 3 o I s s s I s -o I ol s -o I 1 o 12 oj 6 s I 9 N/A OOCKIT NUlllllllll 0151010101 I I DnllATINO TMll lllPOllT 11.-ITTID PUlllUAlllT TD THI lllQUlllllllNTI O' 10 C,11 §:.IC'lool'.,..."'
-of IN '911-.,.J 1111 llllDDI 111 N :1111.*clit 20.a111 to.11111111111w1
"°"'" I *.ac.uucn
-**1i1111
- i--*.nc.1 1111w1 . l I 0 I 0 -*.ac.1111111
-I0.-111121
-I0.7111111211"1
--OTHlll IS-"'1 ;,, AbtOwt .,_-_ ,,. r .. r. NlfC .-.J ,_K I0.7Sllll21111
-*,71191111ft11111AI I0.7111111211MI I0.71111111fwllllll
--I0.7:111112111HI I0.7Jlloll211sl LICIHAI CONTACT ,011 THll Liii 1121 NAMI "'"" COOi C S Kozup, Technical Engineer, Palisades 61116116141 18191113 COMl'LITI ONI LINI .,011 IACM COWQNINT 'AILUlll DllClllllO IN TMll lllflOllT 1111 CAUll SYITIM COMl'ONINT I I . I I I I No I I I .I I I I I I I I I I I I I I I I I I
- MONTH OAY t'l YH (If ..............
IXHCTID IUlllllfSION DA Tl/ I I I On .March 4, 1988 during a review of Technical Specification (TS) Surveillance Test Q0-5, ;'Valve Test Procedure", the stroking of the service water containment isolation valves CV-0824 and CV-0847 [BI;ISV] for the.containment air coolers [BK;CLK] was discovered to have occurred during prohibited conditions.
valves are containment isolation valves and will isolate if a large break of the service water line occurs containment.
However, with a safety injection signal or a containment isolation signal, these valves remain open to supply service water to the containment air The stroking of these valves momentarily defeats the design safety function of these valves; ie, remain open and supply service water. TS 3.4.2 allows a total of two components to be .inoperable, but cycling of these valves would render all three containment air coolers inoperable.
During the same review, a similar problem was noted with the stroking of the non-critical service water isolation valve CV-1359 [KG;ISV] in both TS Surveillance Tests *Q0-1 and Q0-5. These occurrences have been attributed to procedure deficiencies resulting from inadequate procedure development and review. The administrative controls for the review of procedures have been strengthened.
A review of other TS tests to determine if similar conditions existed did not identify other tests where conditions outside TS were introduced by test performance.
LER 88005-0J
'\ NAC Form 311A 19-831 U .*. NUCLEAR IUGULATORY COMMISllON LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED OMil NO. . '" EXPIRES:.
Bf.II 185 FACILITY NAME 111. DOCKET NUM9ER 121 LER NUMllER 181 PALISADES PLANT TEXT l/f men -
-<<ldltiotwl NlfC Fann lliu'111171 Description Nl=IC FORf..' 36EiA On March 4, 1988 during a review of Technical Specification (TS) Surveillance Test Q0-5, "Valve Test Procedure", the stroking of the service water containment isolation valves CV-0824 and CV-0847 [BI;ISV] for the containment air coolers [BK;CLK] was discovered to have occurred during prohibited conditions.
These valves are containment isolation valves and will isolate if a large break of the service .water line occurs inside containment.
However, with a safety injection signal or a containment isolation signal, these valves remain open to supply service water to the containment air coolers. The stroking of thes.e valves momentarily defeats the design safety function of these valves; ie, remain open and supply service water. TS 3.4.2 allows a total of two *components to be inoperable, but cycling of these valves would render all three containment air coolers inoperable.
During the same revi.ew, a similar problem was noted with the stroking of the non-critical service water isolation valve CV-1359 [KG;ISV].
During the performance of Q0-5, CV-1359 is stroked from the C.ontrol Room [NA]. In order to perform this stroking without disrupting the service water flow to secondary side of the Plant, the manual bypass valve MV-SWlOl [KG;V] is opened. .CV-1359 receives a close signal whenever the safety injection system actuates in order to assure adequate cooling flow to the engineered safety equipment.
The opening of Mv-SWlOl defeats the design feature of CV-1359 to isolate the non-critical service water loads in an accident.
The opening of MV-SWlOl is* conducted by an auxiliary operator who remains at the valve until CV-1359 is stroked and then closes the bypass valve. The total evolution of opening the manual _ valve, stroking the control valve and reopening the manual valve generally is accomplished within approximately ten minutes. Further engineering review of TS Surveillance Procedures associated with non-critical service water system [KG] isolation, identified that manual bypass MV-SWlOl was opened while CV-1359 is stroked during performance of Surveillance Test Q0-1, "Safety Injection System". A review of surveillance test schedules identified that Q0-1 was to be performed twice prior to plant conditions that would allow opening of MV-SWlOl in accordance with TS 3.4.1. Therefore, a TS interpretation or surveillance test exemption was deemed necessary.
Operation of isolation valve CV-1359 is controlled by TS 3.4.l'which requires service water pump valves, piping and interlocks to be operable.
TS 3.4.2 allows one component associated with containment cooling to be inoperable provided corresponding redundant components are tested. However, the non-critical service water header isolation valve CV-1359 can be assumed to have no redundant component since there is only one isolation valve. An interpretation of TS 3.4 was submitted to the NRC on April 6, 1988. This interpretation noted the factors listed above, and that if service water flow was partially diverted due to failure of CV-1359 to close, the critical component cooling function would not be lost as long as all <9-8 31 LER 88005-0 l )
NAC Form JlaA 19.S*I U.I.
llEGl'!
COMMIDION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEC
'**'J.
EXPIRES: 8/31,, .l. fACILITY NAMI C1I DOCKET NU .. 111 121 Liii Ill 'AOI 131 PALISADES PL.ANT o 1 s I o I o I o I 21 5 15 81 8 -o *1 o Is -o I i o I 3 oF o I h TEXT I/I mare-ii ,..,.,;.d, --NM: Fomt.-.'111171 three service water pumps were operable; ie, the third service water pump is the functionally redundant component.
Subsequently, provisions were made to assure an auxiliary operator remain in the vicinity of MV-SWlOl during the surveillance test. Additional provisions were emplaced such that prior to test performance, both diesel generators would be verified as operable via a status board check and idle*service water pump(s) would be verified operable via a test starting.
On*May 6, 1988 the NRC documented their acceptance of this interpretation with the temporary provisions.
This letter further noted CP's intent to modify test circuitry of the safety injection system to block the stroking of CV-1359. This modification was completed during the recent refueling outage. 7 Cause Of The Event The cause of the procedural inadequacies of Q0-1 and Q0-5 were the result of inadequate procedure development and review. The present administrative controls for procedure reviews do not assign responsibility to ensure the TS requirements are properly addressed.
Presently, Administrative Procedure 9.21, "Technical Specification Surveillance Procedure Development" requires the technical reviewer to ensure that and limitations are adequate and that they recognize limiting conditions of operation entered during the conduct of the test or which must be addressed if equipment is determined to be inoperable".
However, the technical reviewer is often only cognizant of several of the systems on the test and not all of them. For tests which involve Operations during the performance of the test an review is required, however, no guidance was given on how to perform an Operations.
review. Corrective Action Administrative Procedure 9.21 has been revised to include guidance on how to perform an Operations review. As part of the Operations review, TS requirements will be reviewed to ensure they are adequately addressed during the performance of the TS test. In addition.
to the TS interpretation received in regard to the performance of Surveillance Test Q0-1 and the modification to block the stroking of CV-1359 during a simulated safety injection system actuation signal, the requirement to stroke time CV-1359 was added to Q0-6, "Cold Shutdown Valve Test Procedure" which is conducted in the cold shutdown condition.
For Q0-5, the test methodology was revised to also place the stroking of CV-0824, GV-0847 and CV-1359 into Surveillance Test Q0-6. A review of other TS tests was conducted to determine if similar conditions existed. This review revealed no other tests where _ conditions outside TS were introduced by test p*erformance.
During this review it was noted that several surveillance tests required N"C FO"'-' l&eA 19.SJI LER 88005-01 NAC Form 311.A i9-ll)l LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.I. llUCLEAlll lllEGULATOlllY COMMllllOH AjlpROVED OMll 1'10. l150-41ci' . EXPIRES: 8/31 /15 PACILITY NAMI 111 DOCKET 1'1U .. Ell 121 Liii 111 'AO I l PALISADES PLANT 0 1 s I 0 I 0 I 0 I 215 15 . s, 8 -0 I 0 I 5 -0 11 0 14 OF 0 I h TEXT llf,,.. _it __ , --*NllC Forrrt.-..'111171 to.identify limiting conditions of operation entered during test pert'ormance.
Procedural revisions to include these enhancements have been completed.
-Analysis Of The Event The closure of CV-0824 and CV-0847 would render all three containment air cooler fans inoperable due to the loss of service water until the valves are reopened.
The cycling interval .takes a maximum of five minutes to complete and is accomplished by a _Control Room operator operating t.he valves from the Control Room. Th,e limiting accident would be a LOCA coincident with a loss of offsite power which has a probability of occurring at approximately 3.0 E-8 events per hour. For the LOCA with a loss of offsite power, the containment pressure would be controlled within the accident limits by the containment spray system. The cycling O'f CV-1359 resulted in the opening of MV-SW101 for a maximum of 15 minutes and is accomplished by an auxiliary operator in conjunction with a Control Room operator.
The auxiliary operator opens the bypass valve, the control operator cycles CV-1359 then the auxiliary operator closed the bypass valve. *The limiting condition would be a LOCA as above with the containment air coolers receiving less than design flow due to the bypass valve open. However, containment pre.ssure would be controlled within the accident limits by the containment spray system until full service water flow could be restored.
No adverse risk to the safety of the public resulted due to the low probability of occurrence of an accident coincident with the short time which the above valves were inoperable.
Additional Information Two related reportable events involving inadequate reviews of TS tests were: Licensee Event Report 83-039 H 2 Recombiners Tested Simultaneously Licensee Event *Report 86-021 Inoperable Containment Building Water Level Instrument NlllC FOlllM 368A 19-1131 T_!'.:R 88005-01 '! !
Power
' l'fif POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 February 7, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -LICENSEE EVENT REPORT 88-005-01
-INADEQUATE PROCEDURE RESULTS IN VALVE TESTING DURING CONDITIONS Licensee Event Report (LER) 88-005-01 (Inadequate Procedure Results in Valve Testing During Prohibited CondHions) is attached.
event is repo"rtable to the NRC per 10CFR50.73(e)(2)(i).
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector
-Palisades Attachment