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| {{Adams | | {{Adams |
| | number = ML20212B542 | | | number = ML20197F431 |
| | issue date = 10/10/1997 | | | issue date = 12/18/1997 |
| | title = Insp Repts 50-373/97-15 & 50-374/97-15 on 970908-12. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Engineering | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-373/97-15 & 50-374/97-15 |
| | author name = | | | author name = Vegel A |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| | addressee name = | | | addressee name = Subalusky W |
| | addressee affiliation = | | | addressee affiliation = COMMONWEALTH EDISON CO. |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-373-97-15, 50-374-97-15, NUDOCS 9710280118 | | | document report number = 50-373-97-15, 50-374-97-15, NUDOCS 9712300216 |
| | package number = ML20212B511 | | | title reference date = 11-14-1997 |
| | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 10 | | | page count = 2 |
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| | December 18, 1997 Mr. W. Jr. |
| U.S. NUCLEAR REGULATORY COMMISSION REGIOM111
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| Dockets No: 50-373, 50-374 Licenses No: NPF 11, NPF-18
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| Report Nos: 50-373/97015(DRP), 50-374/97015(DRP)
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| Licensee: Commonwealth Edison Company Facility: LaSalle County Station, Units 1 and 2
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| Location: 2601 N. 21st Road >
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| Marsellies,IL 61341 Dates: September 8 - September 12,1997 Inspectors: K Riemer, Dresden Senior Resident inspector M. Miller, Reactor Inspector, Region lli Approved by: A. Vegel, Acting Chief Division of Reactor Projects Branch 2 9710200118 971010 PDR ADOCK 05000373 G PDR
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| EXECUTIVE SUMMARY LaSalle County Station, Units 1 and 2 NRC Inspection Report 50-373/97015(DRP); 50-374/97015(DRP)
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| This inspection report documents the NRC assessment of the September 4,1997, incident when the licensee was unable to comply with a required action statement of the plant Technical Specifications. The report covers a 1-week period of inspection conducted by regional and resident inspector staf Licensee performance during this event was characterized by work planning deficiencies due to a
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| . loss of focus on Technical Specification complianc Plant Operations
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| The 1 A emergency diesel generator failed its surveillance test and as a result, the licensee was unable to comply with the minimum technical specification (TS)
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| requirements for operable emerger'cy core cooling systems while in operational condition 4. The inspectors identified a violation conceming failure to meet TS criteri (Section O1.1)
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| Maintenance a
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| The licensee's positive emphasis on shutdown risk came at the expense of TS compliance. As a result, the licensee was not as sensitive to the TS requirement These factors contributed to a situation where all of the station's emergency core cooling systems were technically inoperable and the licensee was unable to perform the required action statement specified in the TS. (Section M1.1)
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| The licensee missed a prior opportunity to address the issue of TS compliance in the work planning process when a problem identification form documenting a similar situation was initiated in January 1997. (Section M1.1)
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| Engineering personnel failed to thoroughly address the frequency meter warmup issue due to a lack of a questioning attitude. (Section E1.1)
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| Report Details Summary of Plant Status
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| Unit 1 was in cold shutdown for a forced outage during the entire inspection period and Unit 2 remained shut down for a refueling outage with all fuel removod. The licensee continued to keer, both units shut down to perform design basis configuration reviews and to address equipment and human performance problem I. 00erations 01 Conduct of Operations -
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| 0 Inocerability of Technical Specification Reauired Ememency Core CooFoo Systems M.CJ11 Inspection Scope (7170Z)
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| On September 4,1997, the licensee entered a Division I work window with only the 1 A ,.
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| mmergeacy diesel generator (EDG) operable. The 0 EDG was inoperable and the 18 EDG was "available" but not " operable." Prior to cc,mpleting the Division I work window, a Technical Specification (TS) required surveillance test was run on the 1 A EDG. The diesel failed the surveillance test and as a result, the "1B" and "1C" low pressure coolant injection (i.PCI) subsystems, as well as the 1 A EDG, were declared inoperable. The licensee was unable to meet the required action statement of TS 3.5.2. The inspectors reviewed the licenseo's response to this even Observations and Findinas The initial plant ECCS configuration on September 4,1997, was in compliance with TS requirements for operational condition 4. Specifically Technical Specification 3. (ECCS Shutdown) requiced that at least two of the following shall be operable when the plant was m operational condition 4 or 5: Iow pressure core spray (LPCS) system Iow pressure coolant injection (LPCI) subsystem "A" The above two systems were Division I systems, powered by the 0 EDG. The systems were unavailable due to the Division I work windo LPCI subsystem "B" LPCI subsystem "C" The above two systems were Division ll systems, powered by the 1A EDG. The systems were operabl the high pressure core spray (HPCS) system
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| The HPCS system was the Division ill system, powered by the 1B EDG, This system was "available", yet not " operable."
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| The Division 11 systems (items c. and d. above) were operable and the licensee met the minimum TS requirements for shutdown ECCS equipment prior to commencing the '
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| 7 Division I work windo LaSalle Administrative Procedure (LAP) 100-47," Shutdown Risk Management Instruction," stated that an inoperable system (as defined by TS) was considered
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| "available"if the system was able to perform its intended safety functio On September 4,1997, the licensee operated the 1A EDG to satisfy the surveillance requirements of TS 4.8.1.1.2. The TS required (once per 184 days) that the licensee verify that the fast start voltage, frequency, and speed come up to specification within 13 seconds. Specifically, TS 4.8.1.1.2 required that the diesel reach a rated frequency of 60
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| + 3.0,- 1.2 Hz within 13 seconds. The actual time to reach the required frequency was 17.95 seconds. The diesel failed to meet the surveillance acceptance criteria and was declared inoperatie. As a result, the LPCI "1B" and "1C" systems were subsequently declared inoperable. Technical Specification 3.5.2 required, in part, that with none of the above referenced systems inoperable, the licensee needed to restore at least one subsystem / system to OPERABLE with 4 hours or establish SECONDARY CONTAINMENT INTEGRITY within the next 8 hours. The licensee was unable to meet the required action statements of TS 3.5.2 as discussed in Section M The licensee replaced the frequency meter and reperformed the surveillance on September 5,1997. The recorded time for frequency response was 14.41 seconds. The licensee performed an operability determination and subsequently declared the 1 A EDG operable (reference Section E.1 of this report for inspector assessment of the licensee's operability evaluation). The total time that the 1 A EDG was technicaPv inoperable was approximately 34 hours. The failure to meet the TS required action statement within the required 4-hour time period is a violati~1 of TS 3.5.2 (50-373/97015-01). Conclusions The 1 A EDG failed its surveillance test and as a result, the licensee was unable to comply with ihe minimum TS requirements for operable ECCS while in operational condition 4. The inspectors identified a violation concerning the failure to meet TS criteri II. Maintenance M1 Conduct of Maintenance M Schedule issues for Work Windows Co_ntribute to TS Non-compliance Inspection Scope (62707)
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| During the inspection period, tho inspectors interviewed cognizant licensee personnel responsible for the planning of the ECCS work window and reviewed the equipment status in effect when the issue occurred
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| | Site Vice President LaSalle County Station Commonweshh Edison Company 2601 North 21st Road Marseilles,IL 61341 SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. O-373/97015(DRP); |
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| I Observations and Findinna Prior to commencing the Division I work window the licensee established the following systems as either "availatee" or TS operable for decay heat removal, core coverage, and electrical power:
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| For Decay Heat Removal
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| LaSalle System Operating Procedure (LOP)-CD 10,"Lise of Main Condenser as an Altemate Decay Heat Removal Method in Cold Shutdown." The licensee considered this method to be Availabl *
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| LOP-RT 13, ''RWCU [ reactor water cleanup) Lineup for Heat Removal." The licensee considered thh, method to be a TS equivalent method for decay heat removal, .
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| "1B" loop of shutdown cooling: This method was Operabl For Core Coveraag a
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| LPCI subsystem "1B": This syste'n was Operabl +
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| LPCI subsystem "1C"; This system was Operabl .
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| HPCS system: The licensee considered this system Availabl 'filectrical Power
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| 0 EDG: This diesel was inoperable (Division I work window).
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| | ==Dear Mr. Subalusky:== |
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| 1A EDG: This diesel was Operabl +
| | This will acknowledge receipt of your letter dated November 14,1997, in response to our |
| 1B EDG: This dieselwas Availabl The licensee established the minimum required TS requirements prior to commencing work on the Division I systems. The licensee had planned for redundancies in the systems designated as "available," but did not establish contingencies for the TS required
| | . letter dated October 10,1997, transmitting a Notice of Violation associated with inspection |
| " operable" systems. The 1B EDG and HPCS were "available"; the licensee had operated the diesel and verified that the pump performed The work remaining on the 1B EDG was relatively minor and in some casea, required only paperwork completion prior to declaring the diesol operable. Tt e standby gas treatment (SBGT) sysu:m was "available" to perform its function, but required cbsure of engineering issues and testing to demonstrate TS operabilit The licensee knew,vnd discussed, the fact that the 1 A EDG surveillance would come due during the other division work window. The licensee assumed that the 1 A EDG would pass the surveillance based on past successfu: performances. As a result of this assumption and the lack of contingency planning, the licenseo was unable to meet the TS required actions when the 1 A EDG failed the surveillance tes During the root cause investigation of the incident, the licensee identified that a prior problem identification form (PIF) 97 0575, documenting a similar occurrence, had been initiated in January 1997. In that case TS requirements were met but Operations department personnel raised concerns about being put in the situation where a TS entry was required. The licensee classified the January 1997 PIF as e scheduling concern (i.e., had the existing schedule been met the issue would not have occurred) rather than as a planning concern. The licensee missed a prior opportunity to address the issue of TS compliance in the work planning proces . _ - - _ _ _ - _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _ = - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
| | ' Report No. 50-373/97015(DRP); 50-374/97015(DRP). We have reviewed your corrective actions and have no further questions at this time. These corrective actions will be examined during future inspections. ; |
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| l Conclusions The licensee's positive emphasis on shutdown risk came at the expense of TS
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| compliance. As a result, the licensee was not sensitive to the TS requirements. These y factors contributed to a situation where all cf the station's ECCS were technically iroperable and the licensee was unable to perform the required action statement (
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| specified in the TS. The licensee also missed a prior opportunity to address the issue of TS compliance in the work planning proces q M1.2 Systems "Available" Durina Division I Work Window
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| s a h;nection Scope (62707)
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| The inspectors assessed the status of the equipment "available" during the Division I work window to determine the safety significance of the even Observations and Findinas Though not technically operable, the 18 EDG was "available" to provide electrical power to the HPCS system. The inspectors reviewed the Inoperable / Degraded Equipment .
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| Listing with cognizant licensee personnel and determined that additional testing and documentation closeout were needed to declare the 1B EDG operable. The licensee had operated the diesel to verify it could perform and eupply electrical power to the HPCS syste The status of secondary containment was similar to that of the 1B EDG and HPCS systems. The SBGT system was "available" to perform its function. There were no physicallimitatiens that would have prevented secondary containment from performing its function. However, outstanding engineering issues and design questions would have required a lengthy amount of time to resolve and enable the licensee to declare secondary containment " operable " Conclusions Due to the redundant systems available for decay heat removal and core crurage, the inspectors concluded that the issue was of minor safety significance. The inspectors concluded that the issue was a TS compliance issu Ill. Enaineerina E1 Conduct of Engineering E Review of Failed Division 11 Emeroency Diesel Generator (EDG) Surveillance Inspection Scope (37551 and 6172#)
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| The inspectors reviewed the circumstances related to the failed 1 A EDG surveillance (LOS-DG-M2) on September 4,1997, the succeeding surveillance conducted on September 5,1997, and the surveillance evaluation used to determine that the EDG was operable following the second surveillanc _ _ _ _ _ _ _ _ _ _ - _ _ _ - __ _ _ - _ _ - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - -
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| 4 - e Objiervations and Findinot On September 4, the 1 A EDG was not able to attain the TS required frequency band within a maximum of 13 seconds. Using a meter located in the control room panel, the operators documented that the frequency was attained in 17,95 seconds. The TS also required the EDG to reach a required speed within 13 socords. The operators noted that the EDG reached the required speed in 9.58 seconds. The licensee issued PlF L1997-05525 to document the surveillance test failure, and determined that the control room meter performed erratically, and as a result replaced the mete On September 5,1997, during the post-maintenance test, the operators observed that the required frequency was reached in 14.46 seconds based on control room indicatio However, the time from a local frequency meter was 9.14 seconds. The licensee performed a surveillance evaluation to justify operability by using the local meter. The licensee determined that the control room frequency meter had a relatively long response characteristic until a steady and stable frequency reading could be obtained. This response time was significantly longer than 13 seconds. The TS did not specify which frequency meter to use to demonstrate compliance; therefore, the local indication was used to support the operability of the diesel. In addition, the licensee considered the voltage and diesel speed responses as an independent demonstratloa that the EDG was operabl The licensee also determined that the operators were not provided guidance on when to stop the stop watch in relation to the meter indication. The frequency meter received power from the EDG and was energized following the flashing of the generator field The initial response of the control room meter was to peg high and then start to decrease into the required range. As the meter decreased off the high peg, operators were unclest if the meter was recovering from being pegged or if the meter was starting to track actual frequenc The inspectors had the following comment:
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| The vendor manual (Yokogawa 4555K24 701) stated in a note, " Allow ten minutes warm-up after energizing frequency meter before reading." The control room and local frequency meters for the EDGs on both units were subject to this guidance, Since the meters were energized during the EDG start sequence, the ten minute warm up was not met before using either meter to validate TS compliance. The existence of the warm up note was known to the licensee when the evaluation for the September 5,1997, surveillance test was performed. However, this information was not considered when referencing the l~al meter to justify the operabihty conclusio The inspectors were also concerned about the past operabihty of all EDGs due to the questionable frequency meters. Following further hcensee evaluation and consultation j with the vendor, the vendor provided verbalinformation that the frequency meters would respond in 2.5 seconds with an accuracy of three percent of full scale upon initial energization. The 10-minute period was required for one percent accuracy. This instrument inaccuracy did not affect the results of previous test l l
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| s in addition to the surveillance problems encountered, the frequency meters used for all the EDGs were not consistent. Some meters had a frequency ranges of 58 to 62 Hz, some had 55 to 65 Hz and others had 45 to 65 Hz. Some meters pegged high when the generator field was flashed and others pegged low, in the de-energized state, some meters pegged low, some high, and one stopped at 60 H Conclusions The frequency meters had been used to validate TS compliance for many years, although the vendor manual clearly raised questions about the meters suitability. When the licensee was faced with the second failure of the surveillance, they became aware of the meter warm up question but did not address it in the evaluation. The failure to address the warmup isste when identified, demonstrated J poor questioning attitude on the part .
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| of engineering. Additionally, the Operations department accepted the evaluation without questioning the limited scope of the initial call. Despite the quality of the evaluation, the inspectors considered the EDG operable based on the vendors supplemental informatio The mixture of frequency meter ranges and response characteristics placed an additional human factors problem on the operators. While the m.eter characteristics for this surveillance contributed to the surveillance problem, having differently responding meters for the operators to deal with, added to the overall potential of an operational errors. The licensee identified the inconsistencies between the meters but listed it under"Long Term" solutions to prevent recurrence of this even VI. Manaaement Meetinas X1 Exit Meeting Summary The inspectors presented the results of these inspections to licensee management listed below at an exit meeting on September 12,1997. The licensee acknowledged the findings presented. The inspectors asked the licensee if any materials examined during the inspection should be considered proprietary. The licensee identified non _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - - _ _ _ - _ _ _ _ _ _ - - - _ - _ - . -
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| f PARTIAL LIST OF PERSONS CONTACTED -
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| Comed W. Subalusky, Site Vice President S. Smith, Unit 2 Plant Manager J. Mcdonald, Quality . id Safety Assessment (Q&SA) Manager J. Pollock, Support Engineering Supervisor R. Chrzanowski, ISEG Supervisor J. Bums, Operations Support Supervisor *
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| R. Palmieri, System Engineering Manager W. 'Jekielski, Shift Manager T. Gupana, QC Supervisor J. Bally Restart Manager B. Riffei, Corrective Actions Manager H. Vinyard, EMD Master Mechanic NRC A. Stone, Acting Branch Chief, Region 111 DRP K. Riemer, Senior Resident inspector, Dresden Station D. Calhoun, Acting Senior Resident inspector, LaSalle Station Present at exit meeting on September 12,1997,
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| ________-___ ____ _____. .-___----- _ -
| | /s/ A. Vegel Anton Vogel, Acting Chief Reactor Projects Branch 2 Docket No. 50 373 Docket No. 50-374 - |
| | See Attached Distribution i |
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| | - DOCUMENT NAME: G:\LASA\LAS97015.TKU T. . n ., m. 4 c h.e i. m. 6 c - c.n wen.w .a u i r - con im n e av.a.i OFFICE Rill , l C- l l l NAME- Veoellet M ' |
| | DATE 12/4/97 12/ /97 12/ /97 12/ /97 9712300216 971218 ~~~1CIAL RECORD COPY PDR ADOCK 05000373 G PDR 300048 1.1 .I 1.1!!1.11.11.1.11.1 |
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| INSPECTION PROCEDURES USED IP 37551 Onsite Engineering IP 61726 Surveillance Observation IP 62707 Maintenance Observation IP 71707 Plant Operations ITEMS OPENED, CLOSED, AND DISCUSSED 9PEl
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| 50 373/97015-01 VIO Failure to meet TS action as required UST OF ACRONYMS USED EDG Emergency Diesel Generator HPCS High Pressure Core Spray LAP LaSalle Administrative Procedure LOP LaSalle System Operating Procedure LOS LaSailo Operating Surveillance LPCI Low Pressure Coolant injection LPCS Low Pressure Core Spray NRC Nuclear Regulatory Commission PIF Problem identification Form RHR Residual Heat Hemoval SBGT Standby Gas Treatment System TS Technical Specification VIO Violation
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| | oc: O. Kingsley, Nuclear Generation Group President and Chief Nuclear Group , |
| | M. Wallace, Senior Vice - |
| | President, Corporate Services E. Kraft, Vice President - |
| | BWR Operations Liaison Officer, NOC-BOD D. A. Sager, Vice President, Generation Support |
| | - D. Fa. Tar, Nuclear Regulatory Services Manager 1. Johnson, Licensing Operations Manager Document Control Desk-Licensing F. Decimo, Plant General Manager P. Bames, Regulatory Assurance Supervisor Richard Hubbard Nathan Schloss, Economist Office of the Attomey General State Liaison Officer Chairman, lilinois Commerce Commission Distribution: |
| | Docket File DRP , |
| | PUBLIC IE-01 TSS-A. Beach DRS (2) |
| | Deputy RA RlliPRR Rlli Enf. Coord. RAC1 (E-Mail) |
| | SRI LaSalle . CAA1 (E-Mail) |
| | Project Mgr., NRR DOCDESK (E-Mail) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999
Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl
ML20217H6341999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld
ML20217H6251999-10-15015 October 1999
Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld
ML20217F4301999-10-14014 October 1999
Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1
ML20217D3191999-10-12012 October 1999
Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon
ML20217C1671999-10-0808 October 1999
Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2
ML20217A7601999-10-0606 October 1999
Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20212M0931999-10-0404 October 1999
Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff
05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999
Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl
ML20216J8241999-09-30030 September 1999
Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr
ML20217A6201999-09-30030 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl
ML20212E7171999-09-22022 September 1999
Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads
05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl
ML20212C0591999-09-17017 September 1999
Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97
ML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
ML20211Q9911999-09-10010 September 1999
Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring
ML20212A1141999-09-10010 September 1999
Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage
ML20211P2211999-09-0808 September 1999
Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness
ML20212A8571999-09-0707 September 1999
Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20211Q6861999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023
05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl
ML20211M1151999-08-31031 August 1999
Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006
ML20211G1831999-08-27027 August 1999
Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS
ML20211G1221999-08-27027 August 1999
Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d)
ML20211F8731999-08-25025 August 1999
Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles
ML20210U3201999-08-17017 August 1999
Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted
ML20210N5651999-08-0606 August 1999
Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes
ML20210M9131999-08-0202 August 1999
Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed
05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999
Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed
ML20210E0501999-07-22022 July 1999
Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed
ML20210B7071999-07-16016 July 1999
Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7)
ML20209H5171999-07-15015 July 1999
Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129
ML20209G4031999-07-14014 July 1999
Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted
ML20209E1211999-07-14014 July 1999
Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram
ML20209F6931999-07-13013 July 1999
Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses
ML20210C1521999-07-0909 July 1999
Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage
ML20209G3901999-07-0909 July 1999
Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50
ML20209E0341999-07-0909 July 1999
Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101
ML20209E0361999-07-0808 July 1999
Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501
ML20196J9131999-07-0101 July 1999
Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3)
ML20196J9061999-07-0101 July 1999
Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21
ML20209B8241999-06-30030 June 1999
Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes
ML20196J4711999-06-30030 June 1999
Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2
ML20212J0311999-06-21021 June 1999
Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8
ML20196B1951999-06-18018 June 1999
Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated
ML20195J7761999-06-15015 June 1999
Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509
ML20196G8021999-06-15015 June 1999
Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls
ML20195G7101999-06-11011 June 1999
Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated
ML20195D6351999-06-0404 June 1999
Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs
ML20207D2821999-05-27027 May 1999
Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request
1999-09-08
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3191999-10-12012 October 1999
Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon
ML20217A7601999-10-0606 October 1999
Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20212M0931999-10-0404 October 1999
Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff
ML20217A6201999-09-30030 September 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl
ML20212E7171999-09-22022 September 1999
Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads
ML20212C0591999-09-17017 September 1999
Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97
ML20212A3581999-09-13013 September 1999
Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr
ML20212A1141999-09-10010 September 1999
Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage
ML20211P2211999-09-0808 September 1999
Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness
ML20212A8571999-09-0707 September 1999
Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20211Q6861999-09-0606 September 1999
Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023
ML20211F8731999-08-25025 August 1999
Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles
ML20210U3201999-08-17017 August 1999
Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted
ML20210E0501999-07-22022 July 1999
Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed
ML20210B7071999-07-16016 July 1999
Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7)
ML20209H5171999-07-15015 July 1999
Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129
ML20209G4031999-07-14014 July 1999
Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted
ML20209F6931999-07-13013 July 1999
Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses
ML20196J4711999-06-30030 June 1999
Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2
ML20195B6031999-05-24024 May 1999
Ack Receipt of Which Transmitted Changes Identified as Rev 60 to LaSalle Nuclear Station Security Plan,Submitted Per Provisions of 10CFR50.54(p)
ML20206U3641999-05-19019 May 1999
Confirms Plans to Conduct Routine Mgt Meeting on 990630 in Lisle,Il Re Recent Plant Performance & Lessons Learned from Unit 2 Restart
ML20206T0081999-05-19019 May 1999
Forwards Insp Repts 50-373/99-03 & 50-374/99-03 on 990401-0512.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations.One Violation Re Two Operators Failure to Log Suppression Pool Temp as Required
ML20206S5291999-05-14014 May 1999
Forwards Insp Repts 50-373/99-10 & 50-374/99-10 on 990419-23.Violation Noted:Nrc Determined That Previously Unresolved Item Involving Failure to Adequately Implement fitness-for-duty program,non-cited Violation
ML20206K7401999-05-0303 May 1999
Informs That as Result of April 1999 Senior Mgt Meeting, LaSalle Identified as Routine Oversight Plant.Summary of NRC Discussion Related to LaSalle Listed.Meeting Scheduled for 990506 to Discuss Latest Meeting of NRC Senior Managers
ML20206G6631999-05-0303 May 1999
Forwards Insp Repts 50-373/99-07 & 50-374/99-07 on 990329- 0402.NRC Determined That Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20206G7511999-05-0303 May 1999
Forwards Insp Repts 50-373/99-09 & 50-374/99-09 on 990406-09.No Violations Were Identified.Insp Focused on Actions Recently Taken to Identify Common Causes for Previously Identified Programmatic Radiation Staff Problems
ML20205S8101999-04-20020 April 1999
Forwards Insp Repts 50-373/99-08 & 50-374/99-08 on 990311- 26.No Violations Noted.Overall,Insp Results Indicated That Unit 2 Mods Properly Installed & That Plant Matl Condition of Unit 2 Acceptable
ML20205R5461999-04-16016 April 1999
Forwards Insp Repts 50-373/99-02 & 50-374/99-02 on 990217- 0331.Non-cited Violation Re Failure of Operator to Follow Procedure Which Resulted in Surveillance Procedure Acceptance Criteria Being Evaluated
ML20205R4171999-04-16016 April 1999
Forwards Summary of 990406 Meeting Re Readiness for Restart of Plant,Unit 2 & Dual Unit Operation & Recent Plant Performance Review Issued by NRC
ML20205J2381999-04-0505 April 1999
Submits Summary of 990322 Meeting with Util to Discuss Experiences & Performance of Plant Since Startup of Unit 1 Status of Matl Condition & Unit 2 Outage.Associated Meeting Summary & Handouts Provided by Util Encl
ML20205D5801999-03-29029 March 1999
Refers to Insps 50-373/98-17 & 50-374/98-17 & Subsequent OI Investigation 3-98-032 Into Info Reported to NRC by Comed on 980518,that Deliberate Violation of NRC-required FFD Program May Have Occurred at LaSalle & Forwards NOV
ML20205D6971999-03-29029 March 1999
Discusses Insp Repts 50-373/98-17 & 50-374/98-17 & OI Rept 3-98-015 Completed on 981119 & Forwards Nov.Apparent Deliberate Violation of NRC-required Comed Fitness for Duty Program Noted
ML20205G5411999-03-26026 March 1999
Advises of Completion of Plant Performance Review on 990204 to Develop Integrated Understanding of Safety Performance. Overall Performance at Plant Improved as Discussed.Insp Plan & Plant Issues Matrix Encl
ML20205A6411999-03-25025 March 1999
Refers to Investigation Conducted by OI (Investigations Rept 3-1998-028) to Determine If Employment Discrimination Occurred After Contract Worker Raised Radiation Safety Concerns Re Plant.Synopsis from Subj Rept Encl
ML20204J8411999-03-24024 March 1999
Submits Summary of 990226 Meeting Re Performance of LaSalle Since Startup of Unit 1,status of Matl Condition of LaSalle & Status of Unit 2 Outage.List of Attendees & Matl Used Encl
ML20205A6211999-03-24024 March 1999
Discusses 990226 Mgt Meeting with Util Re Performance of LaSalle Since Startup of Unit 1,status of Matl Condition of LaSalle & Status of Unit 2 Outage.Associated Meeting Summary & Handout Provided to NRC by Util Encl
ML20204J7021999-03-22022 March 1999
Confirms Plans to Conduct Mgt Meeting on 990406 at Mazon Emergency Operations Facility to Discuss Readiness for Restart of Unit 2
ML20204E0751999-03-18018 March 1999
Discusses Review of Rev 6M to Portions of Plant Emergency Plan Site Annex
ML20207J8901999-03-10010 March 1999
Forwards Insp Repts 50-373/99-01 & 50-374/99-01 on 990106- 0216.No Violations Identified.Personnel Errors Occurred During Insp Period.Overall Performance of Plant Personnel Acceptable
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20203C9811999-02-0808 February 1999
Ack Receipt of ,Which Transmitted Changes Identified as Rev 59 to Security Plan.No NRC Approval Required
ML20203A1981999-02-0202 February 1999
Forwards Insp Repts 50-373/98-23 & 50-374/98-23 on 981121-990105.No Cited Violations Identified.Two Equipment Problems Identified During Shutdown for Planned Outage Were Not Effectively Addressed to Preclude Problem Recurrence
ML20198N4531998-12-18018 December 1998
Confirms Plans to Conduct Routine Mgt Meeting on 990119 at Mazon Emergency Operations Facility to Discuss Lasalle,Unit 1 Performance & Status of Lasalle,Unit 2 Restart Activities
ML20198E9281998-12-17017 December 1998
Forwards Insp Repts 50-373/98-22 & 50-374/98-22 on 981010- 1120.No Violations Noted.Overall Performance of Plant Personnel Was Acceptable
ML20198F2891998-12-16016 December 1998
Forwards Insp Repts 50-373/98-25 & 50-374/98-25 on 981102-06.No Violations Noted.Insp Was Evaluation of Operator Workaround Program
ML20198B3741998-12-14014 December 1998
Forwards SE Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves
ML20197H3561998-12-0404 December 1998
Final Response to FOIA Request for Docments.Records in App a Encl & Will Be Available in PDR
ML20198B1531998-12-0202 December 1998
Forwards Insp Plan for Next 6 Months & Plant Issues Matrix. Info Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite
ML20196F7361998-12-0202 December 1998
Informs That Document GE-NEDC-31531P,Suppl 1, ARTS Improvement Analysis for Lscs,Units 1 & 2,Removal of Direct Scram Bypassed Limits, Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20196G4601998-11-27027 November 1998
Forwards FEMA Correspondence, Transmitting FEMA Final Evaluation Rept for 980318 Emergency Preparedness Exercise at LaSalle Nuclear Generating Station
1999-09-08
[Table view] |
Inspection Report - LaSalle - 1997015 |
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Text
- - 11
'
December 18, 1997 Mr. W. Jr.
Site Vice President LaSalle County Station Commonweshh Edison Company 2601 North 21st Road Marseilles,IL 61341 SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. O-373/97015(DRP);
50 374/97015(DRF))
Dear Mr. Subalusky:
.
This will acknowledge receipt of your letter dated November 14,1997, in response to our
. letter dated October 10,1997, transmitting a Notice of Violation associated with inspection
' Report No. 50-373/97015(DRP); 50-374/97015(DRP). We have reviewed your corrective actions and have no further questions at this time. These corrective actions will be examined during future inspections. ;
Sincerely,
/s/ A. Vegel Anton Vogel, Acting Chief Reactor Projects Branch 2 Docket No. 50 373 Docket No. 50-374 -
See Attached Distribution i
D
- DOCUMENT NAME: G:\LASA\LAS97015.TKU T. . n ., m. 4 c h.e i. m. 6 c - c.n wen.w .a u i r - con im n e av.a.i OFFICE Rill , l C- l l l NAME- Veoellet M '
DATE 12/4/97 12/ /97 12/ /97 12/ /97 9712300216 971218 ~~~1CIAL RECORD COPY PDR ADOCK 05000373 G PDR 300048 1.1 .I 1.1!!1.11.11.1.11.1
.. . .- --_ - _- . . . _ . - -. . ._.
. ,
oc: O. Kingsley, Nuclear Generation Group President and Chief Nuclear Group ,
M. Wallace, Senior Vice -
President, Corporate Services E. Kraft, Vice President -
BWR Operations Liaison Officer, NOC-BOD D. A. Sager, Vice President, Generation Support
- D. Fa. Tar, Nuclear Regulatory Services Manager 1. Johnson, Licensing Operations Manager Document Control Desk-Licensing F. Decimo, Plant General Manager P. Bames, Regulatory Assurance Supervisor Richard Hubbard Nathan Schloss, Economist Office of the Attomey General State Liaison Officer Chairman, lilinois Commerce Commission Distribution:
Docket File DRP ,
PUBLIC IE-01 TSS-A. Beach DRS (2)
Deputy RA RlliPRR Rlli Enf. Coord. RAC1 (E-Mail)
SRI LaSalle . CAA1 (E-Mail)
Project Mgr., NRR DOCDESK (E-Mail)
_ ___ _
