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| | number = ML20149L208 | | | number = ML20217J968 |
| | issue date = 07/25/1997 | | | issue date = 08/11/1997 |
| | title = Summarizes 970721 Predecisional Enforcement Conference in Arlington,Tx Re Apparent Violation Identified in Insp Rept 50-285/97-09.Licensee Presented Summary of Causes & Corrective Actions.Attendance List & NRC Handout Encl | | | title = Discusses Insp Rept 50-285/97-09 on 970423-0610 & Forwards Nov.Violation Involves Failure to Comply W/Conditions of 10CFR50.65 Plant Had Not Demonstrated That Condition of Sys Was Being Effectively Controlled Through Preventive Maint |
| | author name = Howell A | | | author name = Merschoff E |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = Gambhir S | | | addressee name = Gambhir S |
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| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-285-97-09, 50-285-97-9, EA-97-280, NUDOCS 9707310192 | | | document report number = 50-285-97-09, 50-285-97-9, EA-97-280, NUDOCS 9708150095 |
| | | package number = ML20217J973 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 111 | | | page count = 5 |
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| | ?N% DNITrD1TATEs p. \ ''/ |
| | NUCLEAR REGULATORY COMMISSION - |
| | REoloN IV 611 RYAN PLAZA oRIVE, SulTE 400 ($, - |
| | ARLINoTofJ, TEXAS 760114064 August _ 11, 1997 EA 97 280 |
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| | S. K. Gambhir, Division Manager Production Engineering - |
| | Omaha Public Power District Fort Calhoun Station FC 2 4 Adm. |
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| } 'S p" "' 4 t y UNITED ST ATES l -
| | ; P.O. Box 399 Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399 |
| #$ %'; NUCLEAR REGULATORY COMMISSION
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| | SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT 50 285/97 09) |
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| ! REGloN iv i e N. '
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| C i S #* f 611 RY AN PL AZ A ORIVE. SUIT E 400 AR LINGTON, TEXAS 76011 8064
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| ; July 25, 1997 i
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| EA No. 97-280 l
| | ==Dear Mr. Gambh!r:== |
| S. K. Gambhir, Division Manager Production Engineering Omaha Public Power District Fort Calhoun Station FC-2 4 Adm.
| | This refers to the inspection conducted on April 23 through June 10,1997, at the Fort Calhoun Station reactor facility. The inspection focused on the causes, circumstances, and corrective actions associated with the April 21,1997, extraction steamline rupture at the Fort Calhoun Station. The inspection findings were discussed with you and your staff |
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| | during an exit briefing on June 10,19f'7, and the findings were 'Jeumented in the subject inspection report dated June 17,1997. The inspection report identmd one apparent violation of the Maintenance Rule,10 CFR 50.65. Subsequently, a predecisional enforcement conference was conducted in the Region IV Arlington, Texas office on July 21,1997. |
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| P.O. Box 399 Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399
| | During the July 21 conference, your position was that, although you viewed the event as serious, it did not involve a violation of the maintenance rule. Your staff stated that: |
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| | (1) industry experience provided a basis for including the extraction steam system into the scope of the maintenance rule because it could cause a plant trip (this is a requirement per 10 CFR 50.05(b)(iiill (2) the system was appropriately classified as nonrisk significant (this is not a regulatory requirement only a recommendation ir' the regulatory guide and industry guideline documents); and (3) no problems had been detected in the extraction steam system during a review of a four-year period prior to July 1996 (problems that caused the reactor to scram or cause actuation of a safety related system...not pipe ruptures]. Further, your staff stated that no known large radius piping sweep failures had occurred. Your position was that the Fort Calhoun Station's decision to monitor the system under 10 CFR 50.65(a)(2) was reasonable given the information available. The decision to monitor the system under paragraph (a)(2) of the rule was reviewed and approved by your expert panel. _ Station management considered the erosion / corrosion j program effective as indicated by, among other indicators, proactive replacement of piping $' |
| | prior to reaching minimum wall thickness. The April 21_ event'was the initial Maintenance Preventable Functional Failure, and so it was now (after the rupture) appropriate to- - |
| | establish goals in accordance with 10 CFR 50.65(a)(1) for certain piping that is susceptible t to flow accelerated corrosion. k 9708150095 970811 PDR G |
| | ADOCK 05000285_ |
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| ==Dear Mr. Gambhir:==
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| SUBJECT: PREDECISIONAL ENFORCEMENT CONFERENCE SUMMARY On July 21,1997 representatives of Omaha Public Power District met with NRC personnel in the Region IV office located in Arlington, Texas to discuss the apparent violation identified 'a NRC Inspection Report Number 50-285/97-09. The conference was held at the request of Region IV.-
| | Omaha Public Power District 2-We note that the maintenance rule was promulgated to require licensees to monitor the effectiveness of maintenance activities in order to minimize the likelihood of failures and events caused by the lack of effective maintenance. Where failures are likely to cause loss of intended function, monitoring should be predictive in nature, providing early warning of degradation. Erosion / corrosion programs are an essential element of preventive maintenance, which, if implemented properly, would give licensees ample information to identify degradation and to take effective corrective actions to prevent failures. This is achieved partly through performance and condition trending of plant structures, systems and components. Additionally, industry-wide operating experience must be addressed when maintenance programs are developed and implemented to assure that failures that have occurred elsewhere are not repeated. As required by the maintenance rule, industry-wide operating experience must be reviewed for plant specific applicability and, where appropriate, must be included in licensee programs and procedures. |
| The licensee presented a summary of the causes for the apparent violation and their corrective actions.
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| The attendance list, NRC handout, and the licensee's presentation are encloseo to this summary. In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of - | | The NRC's position in this case is that, in deciding to monitor the extraction steam system under paragraph (a)(2) of the rule, the Fort Calhoun Station had not first adequately demonstrated that the condition of this nonsafety related system was being effectively controlled through the performance of appropriate preventive maintenance, such that the system remained capabic of performing its intended function. Specifically, the Fort Calhoun Station's method for monitoring pipe wall thicknesses had used a predictive methodology to ensure that minimum wall thicknesses were not exceeded in the fourth stage extraction steam system. The Fort Calhoun Station improperly applied the methodology such that errors and omissions contributed substantially to erronevus predictions of wall thickness. Therefore, your staff's decision to monitor the system under paragraph (a)(2) of the rule was based on the improper implementation of the crosion/ corrosion program. As such, the Fort Calhoun Station did not demonstrate that the condition of these systems was being effectively controlled through the performance of appropriate preventive maintenance. As a result of the flaws in your erosion / corrosion program, the second downstream large radius piping sweep, in the fourth stage extraction steam system, ruptured on April 21,1997, which resulted in a plant transient. Also, the furthest downstream large radius piping sweep in the fourth stage extraction steam system line (S 32) was discovered to be below minimum wall thickness. |
| this summary and its enclosures will be placed in the NRC Public Document Room.
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| Sincerely, b
| | Based on the information developed during the inspection and the information that you provided during the conference, the NRC has determined that a violation of NRC requirements occurred. The violation is cited in the enclosed Notice of Violation (Notice) |
| h Arth r T. Howell 111, Director i
| | and the circumstances surrounding it are described in detail in the subject inspection report. The violation involves a f ailure to comply with conditions of 10 CFR 50.65 in that, at the time the Fort Calhoun Station elected to monitor the condition of the nonsafety related steam extraction system under paragraph (a)(2) of the rule, it had not demonstrated that the condition of this system was being effectively controlled through the performance of appropriate preventive maintenance, such tt it the system remained capable of performing its intended function. |
| Division of Reactor Safety ,
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| ===Enclosures:===
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| 1. Attendance List 2. Licensee Presentation ( k 3. NRC Handout i Docket No.: 50-285 01OObb License No.: DPR-40 9707310192 970725 I b!
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| | Omaha Public Power District 3-The reactor safety consequences of the April 21 rupture of the extraction steam pipe were not significant. The plant was quickly shut down, plant operators appropriately responded to the event, no safety-related systems were challenged, arid no complications to the plant transient were caused by the rupture. This violation has been categorized in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG 1600 at Severity Level IV. |
| gDR ADOCK 05000285 PDR
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| | You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements. |
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| Omaha Public Power District -2-
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| REGION IV, ARLINGTON, TEXAS
| | in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure, ard your response will be placed in the NRC Public Document Room. |
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| 1. ' INTRODUCTIONS / OPENING REMARKS - Ellis Merschoff, Regional Administrator
| | Sincerely, |
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| 2. ENFORCEMENT PROCESS Michael Vasquez, Enforcement Specialist i
| | Ellis W. Merscpp'ff Regional Admidstrator Docket No. 50 285 License No. DPR 40 Enclosure: Notice of Violation cc (w/ encl): |
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| | James W. Tills, Manager Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2 4 Adm. |
| 3. APPARENT VIOLATIONS & REGULATORY CONCERNS - Dwight Chamberlain, j. Deputy Director, Division of Reactor Safety
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| i 4. LICENSEE PRESENTATION -
| | P.O. Box 399 Hwy. 75 North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399 James W. Chase, Manager Fort Calhoun Station P.O. Box 399 Fort Calhoun, Nebraska 68023 |
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| { 5. BREAK (10-MINUTE NRC CAUCUS IF NECESSARY)
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| i j- 6. RESUMPTION OF CONFERENCE 7. CLOSING REMARKS - LICENSEE 8. CLOSING REMARKS - Ellis Merschoff, Regional Administrator l
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| | Omaha Pubito Power District 4-Petry D. Robinson, Esq. |
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| [ APPARENT VIOLATION *
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| ! PREDECISIONAL ENFORCEMENT CONFERENCE
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| OMAHA PUBLIC POWER DISTRICT l e
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| [ JULY 21,1997]
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| | Winston & Strawn 1400 L. Street, N.W. |
| * NOTE: THE APPARENT VIOLA TION DISCUSSED A T THIS PREDECISIONAL ENFORCEMENT CONFERENCE IS SUBJECT TO FURTHER REVIEW AND MA Y BE REVISED
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| : PRIOR TO ANY RESULTING ENFORCEMENT ACTION.
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| | Washington, D.C. 20005 3502 Chairrnan Washington County Board of Supervisors Blair, tJebraska 68008 Cheryl Rogers, LLRW Program Manager Environmental Protection Section Nebraska Department of Health |
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| | 301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 08509 5007 l |
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| e APPARENT VIOLATION I
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| | | bec w/ Enclosure: |
| 10 CFR 50.65(a)(1) states, in part, that each holder of a license to operate a nuclear plant shall monitor the performance of structures, systems, or components, against licensee-
| | PDR LPDR- |
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| | %%EINJDOCS ! |
| established goals, in a manner sufficient to provide reasonable assurance that such j structures, systems and components, as defined in paragraph (b), are capable of fulfilling l
| | SECY EC's: Rl, Ril, Rlli , |
| their intended functions. Such goals shall be established commensurate with safety and, '
| | CA PA (0 204) |
| where practical, take into account industry-wide operating experience.
| | EDO (017G21)- 010 (T 5028) |
| | | DEDO (017021) OE (0 7H5) ! |
| 10 CFR 50.65(b) states, in part, that the scope of the monitoring program specified in I paragraph (a)(1) shallinclude safety related and nonsafety related structures, systems, and !
| | OE:EAFile (0 7H5) 01 (0 3E4) ! |
| components as follows: (2) Nonsafety related structures, systems, or components: (iii) l
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| ; Whose failure could cause a reactor scram or actuation of a safety-related system, i l
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| 10 CFR 50.65(a)(2) states, in part, that monitoring as specified in paragraph (a)(1) is not required where it has been demonstrated that the performance or condition of a structure, system or component is being effectively controlled through the performance of appropriate preventive maintenance, such that the structure, system or component remains ,
| | OGC (015B18) . OGC (015B18) |
| capable of performing its intended function. I Contrary to the above, as of April 21, '.997, for certain nonsafety related structures within the scope of this rule, the licensee had neither monitored the performance of these structures against licensee-established goals, nor demonstrated that the performance or
| | NRR (012G18) . |
| ' | | NRR/ADP (012018) , |
| condition of these structures was being effectively controlled through appropriate preventive maintenance such that the structures remained capable of performing their I intended functions. Specifically, the large radius piping elbows of the fourth stage extraction steam system, sixth stage extraction steam system piping and other piping in the heater drains system were neither monitored nor effectively controllad through j preventive maintenance such that these piping locations remained capable of performing i their intended function. This was evidenced by: 1) the second downstream large radius piping elbow in the fourth stage extraction steam system failed catastrophically on April l 21,1997, resulting in a plant transient; and 2) the following piping structures were l subsequently determined to be below minimum wall thickness: a) the furthest downstream large radius piping elbow in the fourth stage extraction steam system line (S-32); b) a sixth stage extraction steam system " pup" piece (S-54); and c) three parallel lines in the heater drains system (D-95).
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| | | RWharton, NRR (013E10) OC/DAF (T 9E10) |
| I THIS APPARENT VIOLA TION IS SUBJECT TO FURTHER REVIEW AND MA Y BE REVISED
| | OC/LFDCB (T 9E10) AEOD (T 4018) : |
| | RA Reading File GSanborn EAFile , |
| | RIV Files MIS Coordinator PAO RSLO RIV Files E Mall DISTRIBUTION: |
| | OEMAIL JDyer (JED2) . |
| | EMerschoff (EWM) WBrown (WLB) |
| | GSanborn (GFS) GMVasquez (GMV) |
| | BHenderson (BWH) MHammond (MFH2) |
| | CHackney (CAH) DKunihiro (DMK1) 4 AHowell (ATH) DChamberlain (DDC) |
| | KPerkins (KEP) WJohnson' (WDJ) |
| | JShackelford(JLS2) KBrockman (KEB) |
| | PGwynn (TPG) WWalker (WCW) |
| | RCorreia (RPC) DPowers (DAP) |
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| | DOCUMENT NAME: G:\EA\ DRAFT \EA97280 DFT F, a.r'l To rece6ve copy or document, ind6cate in bou: "C" = Copy wMhout enclosures "E" * C wnh enclosures "N* a No copy ES SRA D:DRP NRR/ DRPH , D:DRSR MVasquez ' - JShackelf ord' - PGwynn' RCorreia'[f f AHowell P 08/ /97 08/ /97 08/ /97 08/.5/97 08/N/97 samma summasummmmmmmun mammammmmmmmmme summenummmmmmmuneammma JEDyer 3(jp EMerschoff 08/(/97 ' 08/ /97 |
| | ' denotes previous concurrence OFFICIAL RECORD COPY |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999
Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached
ML20217G9261999-10-15015 October 1999
Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted
ML20217G2331999-10-14014 October 1999
Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted
LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999
Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util
LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999
Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls
ML20217B5111999-10-0606 October 1999
Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate
ML20216H7231999-09-29029 September 1999
Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1
ML20212L9571999-09-27027 September 1999
Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001
LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999
Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl
LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999
Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl
LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999
Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999
Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls
LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999
Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection
LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999
Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters
IR 05000285/19990081999-09-0707 September 1999
Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License
ML20211P2581999-09-0303 September 1999
Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License
LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999
Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase
ML20211J9231999-09-0202 September 1999
Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2)
ML20211L3241999-09-0202 September 1999
Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl
LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999
Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld
ML20211F4491999-08-25025 August 1999
Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability
LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)
LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999
Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld
ML20210R1491999-08-13013 August 1999
Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance
LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999
Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20211B7881999-08-10010 August 1999
Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714
ML20210N1991999-08-0909 August 1999
Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20210P8991999-08-0909 August 1999
Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999
Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999
Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999
Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331
LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999
Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program
ML20210G1851999-07-27027 July 1999
Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application
LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999
Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630
ML20216D6951999-07-26026 July 1999
Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response
LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999
Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates
LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999
Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld
ML20210D9471999-07-22022 July 1999
Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation
ML20210C2041999-07-20020 July 1999
Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations
ML20210C0201999-07-20020 July 1999
Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl
ML20210B0761999-07-19019 July 1999
Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted
ML20209G5351999-07-15015 July 1999
Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl
ML20209F5741999-07-12012 July 1999
Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable
ML20209G5591999-07-0808 July 1999
Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept
LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999
Forwards Fort Calhoun Performance Indicators Rept for May 1999
LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999
Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld
ML20209D8771999-07-0101 July 1999
Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl
LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999
Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624
1999-09-08
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9261999-10-15015 October 1999
Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted
ML20217G2331999-10-14014 October 1999
Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted
ML20217B5111999-10-0606 October 1999
Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate
ML20216H7231999-09-29029 September 1999
Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1
ML20212L9571999-09-27027 September 1999
Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001
IR 05000285/19990081999-09-0707 September 1999
Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License
ML20211P2581999-09-0303 September 1999
Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License
ML20211L3241999-09-0202 September 1999
Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl
ML20211J9231999-09-0202 September 1999
Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2)
ML20211F4491999-08-25025 August 1999
Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability
ML20210R1491999-08-13013 August 1999
Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20211B7881999-08-10010 August 1999
Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714
ML20210P8991999-08-0909 August 1999
Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill
ML20210N1991999-08-0909 August 1999
Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210G1851999-07-27027 July 1999
Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application
ML20216D6951999-07-26026 July 1999
Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response
ML20210D9471999-07-22022 July 1999
Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation
ML20210C0201999-07-20020 July 1999
Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl
ML20210C2041999-07-20020 July 1999
Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations
ML20210B0761999-07-19019 July 1999
Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted
ML20209G5351999-07-15015 July 1999
Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl
ML20209F5741999-07-12012 July 1999
Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable
ML20209G5591999-07-0808 July 1999
Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept
ML20209D8771999-07-0101 July 1999
Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl
ML20196F4931999-06-24024 June 1999
Discusses 990617 Public Meeting at Dana College,Blair,Ne Re Overview of Pilot Insp Program
ML20196D2321999-06-21021 June 1999
Forwards Corrected Cover Ltr for Insp Rept 50-285/99-04. Original Cover Ltr Incorrectly Stated That Rept Contained Two Noncited Violations,When Rept Actually Documented Only One
ML20195J2121999-06-14014 June 1999
Ack Receipt of Ltr Dtd 990316,which Transmitted Rev 16B to Site Security Plan,Rev 2 to Safeguards Contingency Plan & Rev 6 to Training & Qualification Plan for Plant,Under Provisions of 10CFR50.54(p)
IR 05000285/19990041999-06-11011 June 1999
Corrected Ltr Forwarding Insp Rept 50-285/99-04 on 990425-0531.Insp Determined That One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation, Consistent with App C of Enforcement Policy
ML20195J2481999-06-11011 June 1999
Forwards Insp Rept 50-285/99-04 on 990425-0531.Violations Identified & Being Treated as Noncited
ML20195G3141999-06-10010 June 1999
Ack Receipt of & Encl Objectives for Facility Emergency Plan Exercise,Scheduled for 990810
ML20195E8391999-06-0909 June 1999
Ack Receipt of Transmitting Changes to Licensee Emergency Plan,Rev 14 & Emergency Plan Implementing Procedure OSC-1 Under Provisions of 10CFR50,App E,Section IV
ML20195G3621999-06-0808 June 1999
Ack Receipt of ,Which Transmitted Changes to Fort Calhoun Station Emergency Plan,App A,Rev 15,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required
ML20207G4741999-06-0808 June 1999
Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP-OSC-1, Emergency Classification,Rev 31,under Provisions of 10CFR50, App E,Section V
ML20207G4631999-06-0808 June 1999
Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Ep,App B,Rev 4,under Provisions of 10CFR50,App E,Section V.No Violations Identified During Review
ML20207G2981999-06-0808 June 1999
Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Radiological Er Plan,Section E,Rev 22,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required Due to Determination That Effectiveness Unchanged
ML20207G4661999-06-0808 June 1999
Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP OSC-1, Emergency Classification,Rev 30,under Provisions of 10CFR50, App E,Section V
ML20207G3401999-05-27027 May 1999
Informs That NRC Held Planning Meeting on 990511 for Fort Calhoun Station to Identify Insp Activities at Facility for Next 6 to 12 Months.Informs of NRC Planned Insp Activities & Offers Licensee Opportunity to Provide Feedback
ML20207A9041999-05-24024 May 1999
Informs That NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created. Reorganization Chart Encl
ML20206U6331999-05-18018 May 1999
Forwards Insp Rept 50-285/99-03 on 990314-0424.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy
ML20206L4151999-05-10010 May 1999
Forwards SE of OPPD Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20206H4471999-05-0707 May 1999
Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key,Encl for Info.Without Encl
ML20206E7201999-04-28028 April 1999
Responds to Meeting Conducted 990419 in Fort Calhoun,Ne Re Results of PPR Completed 990211.Addl Topics Discussed Included New Assessment Process & Upcoming Actions Planned in Response to Y2K Concerns
ML20205Q5671999-04-15015 April 1999
Forwards Amend 190 to License DPR-40 & Safety Evaluation. Amend Revises TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager
ML20205J2751999-04-0202 April 1999
Forwards Insp Rept 50-285/99-02 on 990131-0313.No Violations Noted.During Insp,Licensee Conduct of Activities at Fort Calhoun Station Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices
ML20205A7191999-03-19019 March 1999
Informs That on 990211 NRC Staff Completed PPR of Fort Calhoun Station.Review Was Conducted for All Operating NPPs to Develop an Integrated Understanding of Safety Performance
ML20207K6151999-03-11011 March 1999
Forwards Insp Rept 50-285/99-01 on 990208-26.One Noncited Violation Was Identified
ML20207E8691999-03-0303 March 1999
Forwards Correction to Amend 188 to License DPR-40 for Plant,Unit 1.Administrative Error,Three Pages of TSs Contained Errors,An Incorrect Page Number,Missing Parenthesis & Misspelled Words
ML20203F2041999-02-11011 February 1999
Informs That During 990208 Telcon Between Mc Ralrick & J Pellet & T Stetka,Arrangements Were Made for Administration of Licensing Examinations at Fort Calhoun Station for Week of 991018
1999-09-07
[Table view] |
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NUCLEAR REGULATORY COMMISSION -
REoloN IV 611 RYAN PLAZA oRIVE, SulTE 400 ($, -
ARLINoTofJ, TEXAS 760114064 August _ 11, 1997 EA 97 280
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S. K. Gambhir, Division Manager Production Engineering -
Omaha Public Power District Fort Calhoun Station FC 2 4 Adm.
- P.O. Box 399 Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399
.
SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT 50 285/97 09)
Dear Mr. Gambh!r:
This refers to the inspection conducted on April 23 through June 10,1997, at the Fort Calhoun Station reactor facility. The inspection focused on the causes, circumstances, and corrective actions associated with the April 21,1997, extraction steamline rupture at the Fort Calhoun Station. The inspection findings were discussed with you and your staff
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during an exit briefing on June 10,19f'7, and the findings were 'Jeumented in the subject inspection report dated June 17,1997. The inspection report identmd one apparent violation of the Maintenance Rule,10 CFR 50.65. Subsequently, a predecisional enforcement conference was conducted in the Region IV Arlington, Texas office on July 21,1997.
During the July 21 conference, your position was that, although you viewed the event as serious, it did not involve a violation of the maintenance rule. Your staff stated that:
(1) industry experience provided a basis for including the extraction steam system into the scope of the maintenance rule because it could cause a plant trip (this is a requirement per 10 CFR 50.05(b)(iiill (2) the system was appropriately classified as nonrisk significant (this is not a regulatory requirement only a recommendation ir' the regulatory guide and industry guideline documents); and (3) no problems had been detected in the extraction steam system during a review of a four-year period prior to July 1996 (problems that caused the reactor to scram or cause actuation of a safety related system...not pipe ruptures]. Further, your staff stated that no known large radius piping sweep failures had occurred. Your position was that the Fort Calhoun Station's decision to monitor the system under 10 CFR 50.65(a)(2) was reasonable given the information available. The decision to monitor the system under paragraph (a)(2) of the rule was reviewed and approved by your expert panel. _ Station management considered the erosion / corrosion j program effective as indicated by, among other indicators, proactive replacement of piping $'
prior to reaching minimum wall thickness. The April 21_ event'was the initial Maintenance Preventable Functional Failure, and so it was now (after the rupture) appropriate to- -
establish goals in accordance with 10 CFR 50.65(a)(1) for certain piping that is susceptible t to flow accelerated corrosion. k 9708150095 970811 PDR G
ADOCK 05000285_
PDR l)lkl
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Omaha Public Power District 2-We note that the maintenance rule was promulgated to require licensees to monitor the effectiveness of maintenance activities in order to minimize the likelihood of failures and events caused by the lack of effective maintenance. Where failures are likely to cause loss of intended function, monitoring should be predictive in nature, providing early warning of degradation. Erosion / corrosion programs are an essential element of preventive maintenance, which, if implemented properly, would give licensees ample information to identify degradation and to take effective corrective actions to prevent failures. This is achieved partly through performance and condition trending of plant structures, systems and components. Additionally, industry-wide operating experience must be addressed when maintenance programs are developed and implemented to assure that failures that have occurred elsewhere are not repeated. As required by the maintenance rule, industry-wide operating experience must be reviewed for plant specific applicability and, where appropriate, must be included in licensee programs and procedures.
The NRC's position in this case is that, in deciding to monitor the extraction steam system under paragraph (a)(2) of the rule, the Fort Calhoun Station had not first adequately demonstrated that the condition of this nonsafety related system was being effectively controlled through the performance of appropriate preventive maintenance, such that the system remained capabic of performing its intended function. Specifically, the Fort Calhoun Station's method for monitoring pipe wall thicknesses had used a predictive methodology to ensure that minimum wall thicknesses were not exceeded in the fourth stage extraction steam system. The Fort Calhoun Station improperly applied the methodology such that errors and omissions contributed substantially to erronevus predictions of wall thickness. Therefore, your staff's decision to monitor the system under paragraph (a)(2) of the rule was based on the improper implementation of the crosion/ corrosion program. As such, the Fort Calhoun Station did not demonstrate that the condition of these systems was being effectively controlled through the performance of appropriate preventive maintenance. As a result of the flaws in your erosion / corrosion program, the second downstream large radius piping sweep, in the fourth stage extraction steam system, ruptured on April 21,1997, which resulted in a plant transient. Also, the furthest downstream large radius piping sweep in the fourth stage extraction steam system line (S 32) was discovered to be below minimum wall thickness.
Based on the information developed during the inspection and the information that you provided during the conference, the NRC has determined that a violation of NRC requirements occurred. The violation is cited in the enclosed Notice of Violation (Notice)
and the circumstances surrounding it are described in detail in the subject inspection report. The violation involves a f ailure to comply with conditions of 10 CFR 50.65 in that, at the time the Fort Calhoun Station elected to monitor the condition of the nonsafety related steam extraction system under paragraph (a)(2) of the rule, it had not demonstrated that the condition of this system was being effectively controlled through the performance of appropriate preventive maintenance, such tt it the system remained capable of performing its intended function.
,
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Omaha Public Power District 3-The reactor safety consequences of the April 21 rupture of the extraction steam pipe were not significant. The plant was quickly shut down, plant operators appropriately responded to the event, no safety-related systems were challenged, arid no complications to the plant transient were caused by the rupture. This violation has been categorized in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG 1600 at Severity Level IV.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure, ard your response will be placed in the NRC Public Document Room.
Sincerely,
. /
Ellis W. Merscpp'ff Regional Admidstrator Docket No. 50 285 License No. DPR 40 Enclosure: Notice of Violation cc (w/ encl):
James W. Tills, Manager Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2 4 Adm.
P.O. Box 399 Hwy. 75 North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399 James W. Chase, Manager Fort Calhoun Station P.O. Box 399 Fort Calhoun, Nebraska 68023
,
.
Omaha Pubito Power District 4-Petry D. Robinson, Esq.
Winston & Strawn 1400 L. Street, N.W.
Washington, D.C. 20005 3502 Chairrnan Washington County Board of Supervisors Blair, tJebraska 68008 Cheryl Rogers, LLRW Program Manager Environmental Protection Section Nebraska Department of Health
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301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 08509 5007 l
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l Omaha Public Power District 5- !
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bec w/ Enclosure:
PDR LPDR-
%%EINJDOCS !
SECY EC's: Rl, Ril, Rlli ,
CA PA (0 204)
EDO (017G21)- 010 (T 5028)
DEDO (017021) OE (0 7H5) !
OE:EAFile (0 7H5) 01 (0 3E4) !
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OGC (015B18) . OGC (015B18)
NRR (012G18) .
NRR/ADP (012018) ,
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RWharton, NRR (013E10) OC/DAF (T 9E10)
OC/LFDCB (T 9E10) AEOD (T 4018) :
RA Reading File GSanborn EAFile ,
RIV Files MIS Coordinator PAO RSLO RIV Files E Mall DISTRIBUTION:
OEMAIL JDyer (JED2) .
EMerschoff (EWM) WBrown (WLB)
GSanborn (GFS) GMVasquez (GMV)
BHenderson (BWH) MHammond (MFH2)
CHackney (CAH) DKunihiro (DMK1) 4 AHowell (ATH) DChamberlain (DDC)
KPerkins (KEP) WJohnson' (WDJ)
JShackelford(JLS2) KBrockman (KEB)
PGwynn (TPG) WWalker (WCW)
RCorreia (RPC) DPowers (DAP)
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DOCUMENT NAME: G:\EA\ DRAFT \EA97280 DFT F, a.r'l To rece6ve copy or document, ind6cate in bou: "C" = Copy wMhout enclosures "E" * C wnh enclosures "N* a No copy ES SRA D:DRP NRR/ DRPH , D:DRSR MVasquez ' - JShackelf ord' - PGwynn' RCorreia'[f f AHowell P 08/ /97 08/ /97 08/ /97 08/.5/97 08/N/97 samma summasummmmmmmun mammammmmmmmmme summenummmmmmmuneammma JEDyer 3(jp EMerschoff 08/(/97 ' 08/ /97
' denotes previous concurrence OFFICIAL RECORD COPY
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