ML20202G189
| ML20202G189 | |
| Person / Time | |
|---|---|
| Issue date: | 12/04/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-277, SECY-97-277-C, WIR-971128, NUDOCS 9712090313 | |
| Download: ML20202G189 (18) | |
Text
3 Kha 0:?iis ^
December 4. 1997
-SECY 97-277 f_Qt:
The Commissioners frm:
James L. Bluha. Assistant for Operations Office of the E00 Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 28, 1997 Contents Enclosure
-Nuclear Reactor Regulation A
Nuclear. Material Safety and Safeguards B
Nuclear Regulatory Research C*
Analysis and F 31uation of Operational Data D
General Counsel E*
Administration F
Chief Information Officer G
Chief Financial Officer H*
Human Resources I
Small Business & Civil Rights J*
Enforcement K*
State Programs L*
Public Affairs M
International Programs N*
Office of the Secretary 0
= Region I P
Region.II P
Region III P
Region IV P
Executive Director for Operations 0*
Congressional Affairs R*
- No input this week.
"ggg ym L Bmh3 James L. Blaha Assistant for Operations OEDO 0
Contact:
{fD) i T. Hiltz OEDO-Document Name: C:\\WEEKN28.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20865 INFORMATION REPORT December 4. 1997 SECY 97-277 For:
The Commissioners From:
James L. Blaha. Assistant for Operations. Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 28, 1997 Contents Enclosure Nuclear P.eactor Regulation A
Nuclear Material Safety and Safegualds B
Nuclear Regulatory Research C*
Analysis and Evaluation of Operational Data D
General Counsel E*
Administration F
Chief Information Officer G
Chief Financial Officer H*
Human Resources I
Small Business & Civil Rights J*
Enforcement K*
State Programs L*
Public Affairs M
International Programs N*
Office of the Secretary 0
Region 1 P
Region 11 P
Region 111 P
Region IV P
Executive Director for Operations 0*
Congressional Affairs R*
- No input this week.
ames L. Bla a Assistant for Operations. OEDO
Contact:
T. Hiltz, OE00
4 Office of Nuclear Reactor Regulation Items of Interest Week Ending November 28, 1997 Seminars on Risk-informed Reaulation Continue On November 10. 1997. Dr. John Flack. Acting Branch Chief of NRR's Probabilistic Safety Assessment Branch. presented the third and final
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Headquarter *3 (H0) scheduled seminar on risk-informed regulatory approaches.
Approximately 400 NRR staff members attended one of the three presentations.
A videotape of the seminar is available for staff members not able to attend the formal presentations.
The seminars provided mandatory training and are intended to inform and motivate technical staff on the uses of risk-informed regulatory initiatives.
Topics included the Commission's PRA policy and implementat.an alan and staff expectations and responsibilities.
The next seminars on risvinformed regulatory approaches will be presented at the Regions ill and IV resident inspector counterparts meeting ending December 13.
'1997. The last scheduled seminar will be given at Region II in February 1998.
Generic Letter 96-06. Suoolement 1. Issued Supplement 1 to Generic Letter (GL) 96 06. " Assurance of Ecuipment Operability and Containment Integrity During Design-Basis Accident Concitions." was issued on November 13, 1997. The supplement informs licensees about ongoing efforts and new developments associated with GL 96-06. and provides additional guidance that licensees may find useful in scheduling and completing corrective actions. The supplement also informs licensees that a public workshop will be held on December 4. 1997. to discuss current issues related to GL 96-06 and to provide additional guidance.
The workshop will be jointly sponsored by NEI and the NRC. and will include presentations by the NRC staff and by licensees. The GL supplement is informational and requires no specific action or response.
Prior to the supplement. GL 96-06 was issued on September 30, 1996. requesting that licensees review cooling water systems that serve the containment air coolers and determine if they are susceptible to waterhammer or two-phase flow effects during postulated accident conditions. Additionally. the generic letter requested that licensees determine if piping systems that penetrate the containment are suscept!ble to thermal expansion of fluid such that over-pressurization may occur GL 96-06 also requested that licensees address the specific concerns that had been identified in a 120-day response, and the NRC staff is currently reviewing those responses.
Public Workshoo on Risk-Informed RG/SRP A public workshop was held to facilitate solicitation of public comments on the draft Regulatory Guide DG 1063 and the Standard Review Plan Section 3.9.8 for application of risk informed in-service inspection. The workshop was held on November 20 and 21. 1997, at the Bethesda Mariott Hotel in Bethesda.
Maryland to explain the draft documents and to answer questions.
The workshop was well attended by industry representatives.
They offered a number of constructive coments, some criticisms, and some suggestions for changing the NOVEMBER 28. 1997 ENCLOSURE A
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i guidance. Overall, the comments indicated general support for pursuing risk-informed in-service inspection (RI-ISI) but in a manner which would necessitate'some modifications to the draft guidance. The more significant-.
issues and industry comments raised during-the workshop regarding the RI-ISI-regulatory guide included:
1) flexibility. to pursue partial plant or system level application should be-supported:
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role of qualitative risk impact assessment is weak and supporting-appendices are extremely detailed and provide prescriptive methodologies instead of giving a framework:
3) the EPRI approach should be explicit-as a way to cl6ssify safety significant pipe segments:
4) there shculd be a strong recommendation to validate pipe failure probabilities-to De benchmarked against actual service experience:
5)
ASME Code Cases N-560. N-577. and N-578 should be endorsed as acceptable alternatives per_ 10CFR50.55a(a)(3)(I).
The staff is reviewing the comments provided at the workshop and those written public comments it has received. The results of the proposed implementation of the ASME Code Case N560. applicable to ASME Class 1 piping. at the Vermont Yankee-(VY) plant were presented at the workshop by a representative of VY.
The scope at VY is not only the reactor coolant piping but the recirculation system. main steam system (including MS Orain. RCIC and HPCI). main feed water system, core spray system standby liquid control system and reactor water cleanup system code case.
Code Case N560 has been fully approved by ASME and the staff has accepted the VY allot plant for review, Pilot plant submittals utilizing the WOG (Surry) and' EPRI (AN02)' approaches have also been submitted to the staff.
Workshoo for NRC Staff on Use of Vodated SRP Chaoter 7 Guidelines for Diaital Instrumentation and Control System Reviews On November 24 and 25, 1997, the members-of the Instrumentation and Controls Branch (HICB) with assistance from its contractor, the Lawrence Livermore National Laboratory. conducted a workshop for other NRC staff to familiarize
-them with the.use of the updated SRP_ Chapter 7 guidance for reviews of digital instrumentation and control-(I&C) system modifications.
The workshop focussed on what a reviewer should look-for in an evaluation of a-digital system design and how the review is conducted rather than on specific acceptance criteria.
The workshop is intended to broaden the understanding of staff not routinely exposed to digital I&C system technology so that they may undertake future reviews as the workload in this area-increases, p
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. NOVEMBER 28, 1997 ENCLOSURE:A i
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a Crystal River 3 Restart Proaress i
-Licensing Submittals-Florida' Power Corporation (FPC or the licensee) continues to maintain its target:for com December 1997 pleting the corrective actions and restarting the-facility by.
FPC identified 37-potential licensing submittals that would require NRC approval prior to restart in December 1997 - Additionally, during its recent Safety. System functional-Inspection (SSFI), the staff identified several: unresolved issues and the region submitted four Task -Interface Agreements (TIAs) for NRR determination of whether the issues.must-be resolved prior to restart. The current status ~ of these-issues is as follows:
Status of: Licensing Submittals that are Required for Restart
- Total: Identified (including the -four TIAs) 41 Awaiting initial submittal 5
Awaiting supplemental information 3
Information received and review 15 in progress Completed / Closed 18-On No'vember 6, 1997, in a telephone conference with the staff, F.PC stated that
-it intends to make operability determinations and complete justifications-for continued operation (JC0s). consistent with GL 91-18. Revision 1, for those licensing actions that will be deferred until after restart.
The NRC staff.
- informed the licensee that the JCOs will be subject 13 audit.
Licensing action / activity continues to be on the critical. )ath.
Snecifically, the license amendment relating to small breat loss-of-coolant accident (SBLOCA). mitigation strategy is complex. involving 17 required operator actions and significant design basis changes. Another significant
-license' amendment is-related to b.ron precipitation prevention.for which the -
licensee has yet to complete the necessary supporting calculations.
SAlfE Salem Assessment Panel - An Assessment Panel meeting was held on November 13, 1997, to review the items that have-to be closed 3rior to restart of Salem -
Unit'1. Following the meeting, the Panel met witi the licensee to discuss the.
plant. status. A public meeting with the licensee:is= scheduled for December 4.
L1997, at the plant to' discuss-lessons-. learned during the Unit 2 restart and.
operation to'date, and to discuss the' status of the Unit'l restart preparaticas.
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NOVEMBER 28, 1997L ENCLOSURE A a
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Office of' Nuclear Material Safety and Safeguards Items of Interest Week Ending November 28, 1997 Public Meetino on Rea Guides DG-0006. and DG 0007 On November 21. 1997, the Nuclear Regulatory Commission staff held a public meeting to discuss comments received on two draft regulatory guides. Draft Regulatory Guide DG 0006. " Guide for the Preparation of Applications for Commercial Nuclear Pharmacy Licenses"; and Draft Regulatory Guide DG-0007,
" Guide for the Preparation of Applications for Licenses to Authorize Distribution of Various Items to Commercial Nuclear Pharmacies and Medical Use Licensees." Representatives of the nuclear pharmacy and radiopharmaceutical industries were invited to participate in a panel discussion of the comments, the NRC staff's 3roposed resolution of the coments. and other alternatives for addressing tie comments. The panel also discussed the level of flexibility provided by the draft guidance, and the degree to which it is risk-informed and performance-oriented.
The discussion focussed primarily on proposed changes to the guidance documents resulting from the Final Rule,
" Preparation. Transfer for Commercial Distribution, and Use of Byproduct Material for Medical Use" (Radiopharmacy Rule 1995), and on those comments and related changes under consiceration as part of developing a NUREG for cited use categcries.
The meeting resulted in substantial input from the invited panel and positive feedback on the draft guidance.
American Society of Non-Destructive Testina Meetina On November 24, 1997, a Division of Industrial and Medical Nuclear Safety staff member gave a presentation on recent revisions to 10 CFR Part 34.
including an overview of all changes and other issues associated with its implementation, at the meeting of the Old Dominion Section of the American Society of Non-Destructive Testing held in Richmond, Virginia.
The presentation was followed by questions and active discussion.
Meetino of American National Standards Institute Subcommittee N43-15 On November 19-20. 1997. American National Standards Institute (ANSI)
Subcommittee N43-15 met at Nuclear Regulatory Commission Headquarters to review and consider issuance of a national standard for underwater irradiators (Category III), also called "self-contained wet storage gamma irradiators."
Attendees included representatives of the irradiator-industry (manufacturers and irradiator licensees) and an Office of Nuclear Material Safety and Safeguards staff member representing the NRC.
The proposed Standard will follow the format of the Category IV Irradiator Standard (ANSI N43.10) and contain suggested guidance and criteria for persons who design, fabricate, and use Category III irradiators.
Category III irradiators are used on a variety of commercial products for various purposes including sterilization of medical supplies, eradication of insects and microbial contamination in foodstuffs, and changes to the material structure of wood flooring products.
Category III irradiators differ from Category IV NOVEMBER 28, 1997 ENCLOSURE B
in that the irradiation of the nroduct is accomplished underwater rather than in air, and therefore. Category 111 sources are always in the shielded position.
At its next meeting, scheduled for January 1998, the subcommittee is expected to complete review of the standard and put it into final form for publication.
Storaae of Westinahouse Fuel in the TN-32 Soent Fuel Dry Storaae Cask On November 25. 1997. Spent fuel Project Office.(SFP0) staff members met with Transnuclear. Inc.. to discuss Transnuclear's proposal to store Westinghouse Upper Head Injection Fuel with burnable poison rod assemblies (BPRAs) in the TN-32 cask.
Duke Power Company also represented at the meeting, is interested in using the TN-:12 cask to store this type of fuel at the McGuire Nuclear Station near Charlotte. North Carolina. This fuel will not fit into the cask without either compressing the BPRA springs, or redesigning the TN-32 lid.
Further, this cask currently is not approved to store BPRAs.
Transnuclear discussed both options, stating where they thought additional analysis would be required.
Transnuclear's preference would be to compres),
the BPRA springs since this option requires less change to the current analysis and maintains a generic cask design.
SFP0 staff stated that both options were feasible. lhe a) plication for this use of the TN-32 cask is expected in the next few montis.
Additional Transoort Controls for Radicarachic Exoorure Devices On November 21, 1997. the Nuclear Regulatory Commission amended Certificate of Compliance No. 9033, for Model 660 series radiographic exposure devices, to include additional transport controls.
The additional controls specify that Model 660 series packages must be transported within a steel box of welded construction or a steel drum for common carriage, and within a box secured to the vehicle or a steel box or steel drum for private carriage. The controls are needed to ensure that the package does not sustain damage that reduces its effectiveness in the event of a transportation accident and fire. The new controls were proposed by the Certificate holder. Amersham Corporation, as a result of the unexpe:".ed failure of a test s)ecimen subjected to the hypothetical accident test sequence in 10 CF1 Part 71.
Visit to France and the United Kinadom During November 3-7. 1997. Nuclear Regulatory Commission staff members and an NRC contractor attended technical exchange meetings with the regulators and site operators of radioactive waste vitrification facilities in France and the United Kingdom.
In addition to the meetings, the NRC staff members were given tours of both the La Hague vitrification facility in France and the Sellafield vitrification plant in the United Kingdom.
The purpose of the meetings and visits was to accuire knowledge and understanding of the processes, technologies, anc hazards involved in the pre-3rocessing and vitrification of radioactive waste. materials.
This additional (nowledge will enable NRC to continue to assist the Department of Energy (DOE) in the development and execution of a-comprehensive regulatory program during the demonstration phase NOVEMBER 28. 1997 ENCLOSURE B
(Phase 1) of Tank Waste Remediation System (TWRS) privatization activities at Hanford. Washington, and to be better prepared for the potential licensing of DOE contractor-owned and contractor-operateu TWRS facilities at Hanford during full-scale operations (Phase 11). These activities are in keeping with the January 29, 1997, NRC/00E Memorandum of Understanding on this subject.
NOVEMBER 28, 1997 ENCLOSURE 8
l' Office for Analysis and Evaluation of Operational Data Items of-Interest Week Ending November 28, 1997 PRELIMINARY NOTIFICATIONS 1.
PNO-I-97-071. NORTPCAST Utilities (Millstone 1 2 3). MANAGEMENT RE0RGANIZATION 2.
PN0-I-97-072. Boston Edison Co. (Pilgrim 1).. UNPLANNED SHUTDOWN GREATER TMAN 72 HOURS - EN 33303 3.
PNO II-97-059. Floridu Power Corporation (Crystal River 3). CRYSTAL RIVER 3 REACHES MILESTONE-DRAWS VACUUM IN MAIN CONDENSER AND STEAM BUBBLE IN PRESSUhlZER 4.
PNO II-97-060. Georgia Power Co. (Hatch 2) UNPLANNED SHUTOOWN GREATER THAN 72 HOURS 5.
PNO II-97-061. Virginia Beach General Hospital. MEDICAL MISADMINISTRATION INVOLVING 10 DINE-131 6
PNO-III-97-093. Mqs Inspection. Inc., NOTIFICATION OF RADIOGRAPHY SOURCE DISCONNECT-AND OFF-SCALE DOSIMETER 7.
PNO IV-97-068, Halliburton Energy Services. REPORT OF LEAKING SEALED SOURCE 8.
PNO-IV-97-069. Union Electric Co. (Callaway 1). SECURITY THREAT 9.
PNO-IV-97-070. U.S. Air Force (Dover Air Force Base). LOSS OF GENERALLY LICENSED EXIT SIGNS 10.
PNO-IV-97-071. Terracon Consultants Western. Inc.. STOLEN MOISTURE DENSITY GAUGE NOVEMBER 28, 1997 ENCLOSURE D
Office of Administration Items of Interest Week Ending November 28. 1997
'tS. Enricht ?nt Corocration (USEC)
On November 25. 1997. USEC submitted a copy of their safeguards and security plan covering IAEA inspections at the Portsmouth Gaseous Diffusion Plant (GDP) scheduled to begin December 1. 1997.
USEC requested NRC's review and approval of the plan.
The IAEA inspections will occur in DOE owned and controlled areas of the GDP. however, some classified information being used by the IAEA inspectors will be handled and stored in USEC leased s) ace subject to NRC regulations. A Division of Facilities vid Security. A)M and Division of Fuel Cycle Safety and Safeguards. NMSS coordinated response reflects no' objection to IAEA inspectors handling and storing DOE classified information in areas subject to 1RC regulations.
The "Portsmouth Gaseous Diffusion Plant Security Plan for the Protection of Classified Matter" will be used to ensure proper protection of classified information in this area.
Contract Awards On November 18. 1997. two contract awards were made as a result of competitive solicitation RS-NMS-97 007.
Contract No. NRC-02-98-004 entitled "Su) port to t;ie FSU Republics for Activities Under the Cooperative Threat leduct'on (CTR) Program and Lisbon Initiative for the Material Control and Accanting Programs (MCM)" with 21st Century Industries. Inc. (TCI) in the amant of $144.639.56 for the base year with four options year.
The total eetimated ceiling amount including the oation years is $767.557.60.
The period of performance is November 18, 1997 t'irough November 17. 1998.
Contract No. NRC-02-98 005 entitled "Sup) ort to the FSU Republics for Activities Under the Coo)erative Threat Reduction (CTR) Program and Lisbon Initiative for Physical 3rotection Area" with Science and Engineering Associates. Inc. (SEA) in the amount of $222.463 for one year with four options year.
The total estimated ceiling amount including the option years is 51.176.182.00. The period of performance is November 18, 1997 through November 17. 1998.
Streamlining Procedures implemented:
The CBD requirement'for this procurement was waived.
Simplified evaluation criteria were employed.
Competition was limited to known qualified sources.
Electronic transmittal of S0W and final selection report.
Tha competitive range report step was deleted because the contract went straight to award.
i NOVEMBER 28, 1997 ENCLOSURE F
Chief Information Officer Items of Interest Week Ending November 28, 1997 Freedom of Informatio1 and Privacy Act Recuests Recuests Received durina the 4 Day Period of Novencer 21 Novembtr 27. 1997:
Cor 'ract. NRC 33-95173. Ruland Associates.
(F01A/PA 97-457)
IMPAC listing.
(F01A/PA 97 458) i J. Robert Oppenheir.cr, Hanhattan Project.
(F01A/PA 97-459)
OlG report and exhibits, case 97-81G.
(F01A/PA 97 460)
St. Lurie employee complaints and investigations of those complaints.
(F01A/PA 97 461)
Named individual and RAD 5 S. L., Inc., and Anglorad.
(F01A/PA 97 462) i a
NOVEMBER-28. 1997 ENCLOSURE G
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Office of Human Resaurces Items of Interest Week Ending November 23, 1997 I Arrivals None Retirements OLSEN William RESIDENT INSPECTOR (PF7)
R1 Departures None NOVEMBER 28, 1997 ENCLOSURE I l
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Office of Public Affairs items of Interest Week Ending Nuvcsber 28. 1997 Media Intereel There was considerable press interest at Headquarters and Region 111 regarding INP0's report on the poor performance of Commonwealth Edison.
Charlie Haughney. SPF0. and Region 111 conducted a telephone interview with a Chicago Sun Times reporter regarding the transportation of spent fuel.
School Volunteers Proaram Ed O'Donnell RES. visited Weller Road E.S. to discuss geology with firs; grade students.
Lee Abramson, RES. agreed to mentor an eleventh grade student at Col. Zadok Magruder H.S.
Press Releases Headquarters:
97-175 NRC Revises its Regulations to Eliminate Five Security Requirements Associated With Internal Threats at Nuclear Power Plants97-176 NRC Changes Regulations to Permit Exempt Distribution of Radioactive Diagnostic Drug 97-177 NRC Advisory Committee on Nuclear Waste to Meet December 16 18 in Rockville. MD Regions:
I-97-151 NRC, PSE&G to Discuss Lessons Learned From Salem Unit 2 Restart-11-97-82 NRC Staff Schedules Predecisional Enforcement Conference to Discuss St. Lucie Nuclear Plant Regulatory Concerns 11-97 83 NRC Staff Sets Predecisional Enforcement Conference to Discuss Surry Nuclear Plant Concerns With Virginia' Power 111-97 102 NRC Predecisional Enforcement Conferer.ce on Apparent Violations of NRC Requirements at Quad Cities Station 111-97-103 NRC Staff to Meet With Commonwealth Edison to Discuss Possible Fitness For-Duty Program Violations at Zion NOVEMBER 28. 1997 ENCLOSURE M
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Office of the Secretary items of Interest Week Ending November 28. 1997 Memoranda _ Released to the Pu.blic Document Date Subject
- 1. M971105A 11/25/97 Staff Requirements Memorandum Briefing on Proposed Resolution to a Petition for Rulemaking Relating to Use of Potassium lodide (KI) Following Severe Accident at a Nuclear Power Plant. Wednesday. Nuvember 5. 1997 Commission Correspondence Released to the Public 1.
Letter to Representative Marcy Kaptur dtd 11/19/97 responds to constituent concerns regarding the meteorological information program at the Davis-Besse Nuclear Power Plant 2.
Letter to Representatives Stephen Horn and Carolyn Maloney dtd 11/19/97 provides the NRC's November 1997 quarterly report on the Year 2000 3.
Letter to Secretary of Energy Federico Pena provides the Memorandum of Urderstanding establishing a Pilot Program on External Regulation of DOE Nuclear Facilities ffdgral Reaister Notices Issued 1.
10 CFR Parts 30 and 32: Exempt Distribution of a Radioactive Drug Containing One Microcurie of Carbon-14 Urea: Final Rule 2.
10 CFR Part 73: Changes to Nuclear Power Plant Security Requirements:
Final Rule 3.
Advisory Committee on Nuclear Waste: Notice of Meeting on December 10-18.
1997 NOVEMBER 28. 1997 ENCLOSURE O L
t' Region I r
items of Interest Week Ending November 28. 1997 Manaaement Oversicht - Problems at Gauae Licensee During a November 6. 1997 inspection of License No. 37-18494-01. Windsor Service. Inc.
in Reading. PA., the inspector was informed that the com)any had been sold to Haines and Kibblehouse. Inc. (H&K). located in Skippact. PA.
The inspection continued on November 19 and 21. 1997, to include License No.
37 20809 01 issued to H&K. As a result of the inspection of both licenses.
the inspector found numerous apparent violations indicative of lack of management oversight. Region 1 issued a Confirmatory Action Letter and will consider escalated enforcement against the H&K license.
The violations include. for example. failures to amend the licenses for change of. ownership, addition of locations of storage, change of Radiation Safety Officer without notification and approval by the NRC. and failures to provide training to assure that users were qualified and authorized and followed the requirements of the licenses and NRC regulations.
The licensee possessed nine portable nuclear gauges, New Enaland Radioloaical Health Committee Annual Meetino from November 18 through 20. 1997, the Region State 1 Agreements Officer (RSA0) attended the annual New England Radiological Health Committee (NERHC) meeting in Hyannis. Massachusetts.
The meeting was attended by program W.nagers. su)ervisory and technical staff of all six New England States (Maine. New lampshire. Vermont Massachusetts. Rhode Island and Connecticut).
Also in attendance were representatives from the Conference of Radiation Control Program Directors from New Jersey. Illinois, various federal agencies (FDA. FEMA. EPA, and NRC) and the Atomic Energy Control Board of Canada. The four-day meeting included technical sessions and workshops on a wide range of current byproduct materials, machine-produced, naturally-occurring, and non-lonizing radiation issues.
During the meeting, the RSA0 presentcd a status report on current NRC activities.
NOVEMBER 28, 1997 ENCLOSURE P i
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Region II Items of Interest Week Ending November 28. 1997 Carolina Power and Licht Company Robinson On November 25. 1997, the Regional Administrator and other NRC managers and staff held a pre-decisional enforcement conference with licensee representatives.
The purpose of the conference was to discuss the apparent violations and licensee corrective actions regarding a mispositioned output breaker switch on an emergency diesel generator. This condition was discovered by the NRC resident and the mispositioned switch caused the generator to be inoperable.
Southern Nuclear Company. Inc. - Hatch On November 20. 1997, at about 2:30 p.m.
plant operators manually scrammed the reactor from 70 >ercent power because of damage to a portion of the condensate system.
[arlier in the day, the 2A condensate booster pump was removed from service for maintenance. When operators locally reported that the 2A condensate booster pump was rotating backwards, operators closed the suction isolation valve.
This stopped the reverse rotation: however, a flexible bellows on the 2A condensate booster pump suction became over
]ressurized.
The licensee initiated a controlled shutdown: however because Jellows pressure continued to increase, the unit was manually scrammed.
The licensee has repaired isolati n valves, piping and hangers that were damaged during the event.
The reactor was taken critical on November 26.
1997 with condensate booster pump 2A out of service.
Virainia Beach General Hosoital On November 25. 1997. Virginia Beach General Hospital reported that a medical misadministration had occurred on November 21. An authorized user prescribed the administration of 100 microcuries of iodine-131 (1-131).
Instead five millicuries of I-131 were administered.
Region 11 will review the circumstances of the misadministration during an inspection the week of December 1.
Region 11 is contacting a medical consultant to assist in review of the event.
4 NOVEMBER 28, 1997 ENCLOSURE P 1
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Region 111 Items of Interest Week Ending November 28, 1997 I:
Predecisional Enforcerat Conference with Connonwealth Edison Comoany - Quad Cities On November 26, 1997. a Predecisional Enforcement Conference was conducted in the Region 111 Office. Lisle. Illinois, becween management representatives of Commonwealth Edison Company and members of the NRC staff.
The conference was held to discuss the utility's apparent inadequate implementation of NRC's maintenance rule at the Quad Cities Nuclear Power Station.
During an inspection in August and September NRC inspectors found apparent inadequacies in the monitoring of systems and equipment, in developing system performance criteric, and in reviewing the historical performance of systems.
Manacement Meetina with Northern States Power Comnany Prairie Island On November 25, 1997. a management meeting was conducted in the training l
building at the Prairie Island Nuclear Power Station between management i
representatives from Northern States Power Company and members of the NRC staff.
The meeting discussion focused on the status of improvements in operator performance.
Discussion also took place regarding a review of operator errors over the last year by the utility's consultant and various procedural problems.
following the meeting, Region Ill Regional Administrator A. Bill Beach and State Liaison Officer Roland Lickus met with the Prairie Island Dakcta Indian Tribe and Minnesota State Liaison Officer Kris Sanda.
NOVEMBER 28. 1997 ENCLOSURE P
i Region IV Items of Interest Week Ending November 28, 1997 Meetina'at San Onofre Recardina Emoloyee Concerns Procram On November 21, 1997, a aublic meeting was held between the Agency Allegation Advisor, members of the Region IV staff and Southern California Edison Company management at the San Onofre site. The meeting was held in aesponse to an NRC request because the number of allegations received by the NRC for San Onofre in the preceding 12 months was greater than three times the industry median.
The purpose of the meeting was to discuss the licensee's i
employee concerns program, and to give a better understanding of the status of actions taken following a 1996 site survey to assist organizations that were identified as needing improvement in handling employee concerns.
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