ML20210T594
| ML20210T594 | |
| Person / Time | |
|---|---|
| Issue date: | 10/02/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-861002, NUDOCS 8610090086 | |
| Download: ML20210T594 (35) | |
Text
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e October 2, 1986 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 26, 1986 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
General Counsel F*
International Programs G
State Programs H*
Resource Management I
Analysis and Evaluation of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L*
CRGR Monthly Reports M*
Executive Director for Operations N
Items Addressed by the Commission 0*
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
7 T. A. QRe
/
I ssistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781 8610090086 861002 PDR COMMS NRCC WEEKLYINFOREPT PDR
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING SEPTEMBER 26, 1986 i
Seabrook. Unit 1 On September 20, 1986, Massachusetts Governor Michael S. Dukakis arinounced his decision that he will not submit Seabrook emergency plans for the six l
Massachusetts communities closest to the plant. He indicated that in his
(
best.iudgment emergency _ plans could not constitute appropriate protective measures adequate to protect the pu111e health and safety in the event of a radiological emergency. The announced decision did not note any conditions that would mitigate his decision.
Hope Creek Generating Station An Augmented Inspection Team (AIT) will be dispatched to Hope Creek and a Confirmatory Action letter (CAL) will be issued to PSE&G as a result of the cquipment performance deficiencies experienced during the September 11, 1986, Loss of Offsite Power (LOP) test, and the subsequent non-critical LOP retest held September 19, 1986. The AIT will commence Thursday, September 25, 1986, and will conclude late next week. The AIT will review Hope Creek design control and the adequacy of the preoperational test program. The CAL will require PSE&G to provide additional information regarding the LOP tests, and to investigate the broader implications of the equipment performance deficiencies.
In the meantime, Hope Creek is to be maintained in the shutdown condition.
Prairie Island Nuclear Generating Unit Nos.1 and 2 License Extension L
On September 23, 1986 the Commission issued amendments for the operating licenses of the Prairie Island Nuclear Generating Plant Unit Nos. I and 2 that extend the license expiration dates for both units from 40 years after the issuance of the Construction Permit to 40 years after the issuance of the Operating License.
Sequoyah Fuels Corporation On September 22, 1986, Sequoyah Fuels Corporation (SFC) representatives met with NRC staff to discuss the status of the SFC facility and some of the commitments to NRC.
Also discussed was the termination of a shift analyst that was found to be falsifying analyses of operational control samples.
Regarding the facility status, SFC provided the staff with a copy of a letter sent to employees to inform them of a reduction in forces until authorization is received to restart the facility.
A total of 104 employees were laid off, SFC some of which will be recalled to process existing liquids to UF.
representativesprovidedthestatusof(1)commitmentsmadeintkeinformation provided by letter dated June 25, 1986, (2) decontamination of Pond 2, and (3) the perimeter security system.
f 0FFICE OF ADMINISTRATION Week Ending September 26, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 704 192 Granted 532 69 Denied 145 39 Pending 208 99 ACTIONS THIS WEEK Received Pat Costner, Requests seven categories of records regarding the National Water Sequoyah Fuels Corporation.
Center (86-688)
Donald Schlemmer, Requests records related to Western Piping and Engineering Government Materials furnished for the Perry Units 1 and 2 Accountability nuclear power plants.
Project (86-689)
Stephanie Murphy, Requests two categories of records regarding the Nuclear Sequoyah Fuels Corporation.
Information and Resource Service (86-690)
Nancy Ridgway, R(auests a copy of the contract awarded under Booz Allen &
solicitation No. RS-01E-86-154.
Hamilton Inc.
(86-691)
Michael Sweig, Requests a list of NRC licensed nuclear pharmacies.
Altheimer & Gray (86-692)
Mary Wagner, Requests copies of Commissioners' comments on SECY McGraw-!!ill 174.
Nuclear Publications (86-693)
CONTACT:
Donnie H. Grimsley 492-7211 SEPTEMBER 26, 1986 ENCLOSURE A
a 2
Received, Cont'd (An individual Requests records concerning himself maintained by the requesting NRC.
information about himself)
(86-694)
Michael Terry, Requests records providing the position description, Attorney-At-Law grade and salary of the Personnel Director and the (86-695) number of NRC employees.
Stephanie Murphy, Requests two categories of records regarding a loss Nuclear of coolant accident at a foreign reactor.
Information and Resource Service (86-696)
Homi Minwalla, Requests a copy of the non-proprietary version of the Pars Associates, technical proposal for NRC contract No. 03-85-055.
Inc.
(86-697)
Dick Graham Requests copies of NUREG-1153, NUREG-ll88, NUREG-1103, (86-698)
NUREG-ll79 and PN0-I-86-69.
Dorothy F. Dickey, Referral from the 00J of records regarding the Diablo Public Utilities Canyon nuclear power plant.
Commission, State of California (86-699)
Raymond Mayer Requests information regarding the regulations to which (86-700)
U.S. Ecology must conform for temporary storage of low level radioactive material on the south side of Indianapolis, Indiana.
Joshua Gordon, Requests three categories of records regarding the use or Critical Mass abuse of drugs at nuclear power plants since January 1, (86-701) 1984.
Charles Pace Requests a copy of the Sacramento Municipal Utility (86-702)
District nuclear insurance policy.
Raymond bonner Referral from the DOS of two records.
(86-703)
Mozart Ratner, Requests copies of 13 specified inspection reports, with Mozart G. Ratner, related responses and replies to responses and notices of P.C.
violation, and two information notices regarding GE's (86-704) facility in Wilmington, North Carolina.
Billie P. Garde, APPEAL TO THE COMMISSION for the release of the denied Government portions of one record in NRC's August 26, 1986 response Accountability to requests for records generated or prepared by V. Stello Project since his appointment as Acting Executive Director (86-A-179-86-80) for Operations.
(86-A-180-86-82)
SEPTEMBER 26, 1986 ENCLOSURE A
e 3
Received, Cont'd Billie P. Garde, APPEAL TO THE COMMISSION for the release of nine denied Government records in NRC's August 25, 1986 response, to requests Accountability for records generated or prepared by V. Stello since Project his appointment as Acting Executive Director for (86-A-181-86-80) Operations.
(86-A-182-86-82) 86-A-183-86-201) 86-A-184-86-209 86-A-185-86-263 Pat Costner, APPEAL TO THE E00 for the lack of response to a request National Water for records regarding the Sequoyah Fuels Corporation.
Center (86-A-186-86-447)
Stevi Stephens, APPEAL TO THE COMMISSION AND THE ED0 for the lack of Nuclear Awareness response to a request for records within the Office of Network Investigations' cases regarding investigations which have (86-A-187-86-331) occurred and/or been closed within the time frame of January 27, 1986, and May 12, 1986, and all Quality First files within the NRC.
Stevi Stephens, APPEAL TO THE COMMISSION AND THE EDO for the lack of Nuclear Awareness response to a request for records relating to the Network special inspection of the Quality First Program conducted (86-A-188-86-340) by the NRC during the period of May 27 through May 31, 1985.
Pat Costner, APPEAL TO THE ED0 for the lack of response to a request National Water for a copy of a letter dated March 20, 1986, from Stauter, Center Sequoyah fuels Corporation (SFC), to Mr. Crow, NRC, on the (86-A-189-86-627) subject of SFC's monitor well FTP-2A.
Pat Costner, APPEAL TO THE ED0 for the release of records relevant to National Water the materials balance, cumulative and annual, of the Center Sequoyah Fuels Corporation, i.e., specific activities of (86-A-190-86-298) the raw materials and its finished products.
APPEAL TO THE ED0 for three categories of information Pat Costner, National Water regarding the proposed restart of the Sequoyah Fuels Center Corporation facility near Gore, Oklahoma.
(86-A-191-86-471)
Z. Reytblatt, APPEAL TO THE ED0 for the lack of completeness to a Illinois Institute request for a list of records in the NRC's possession of Technology related to a rulemaking action in October 1985 which (86-A-192-86-482) modified section 9.4 of 10 CFR.
Granted Stevi Stephens, In response to a request for copies of records related Nuclear Awareness to Kansas Gas and Electric's Corrective Action Report #7 Network regarding the Wolf Creek nuclear power plant, informed (85-595) the requester that records subject to this request are already available at the PDR.
SEPTEMBER 26, 1986 ENCLOSURE A
4 Granted, Cont'd Billie P. Garde, In response to a request for records related to all Government audits by the Office of Inspector and Auditor of Accountability the Office of Investigations in 1983, 1984, and 1985, Project informed the requester that these reports are (86-134) already available in the PDR in a previous request folder, F01A-85-334.
Robert G. Werner, In response to a request for a copy of the distribution EDP Audit mailing list for RFP RS-0RM-86-263, made available a copy Controls, Inc.
of the requested record.
(86-140)
Billie P. Garde, In response to a request for copies of records related Government to the NRR, IE and Region III onsite review of the Fermi Accountability Unit 2 SAFETEAM allegations on June 27-28, 1985, informed Project the requester that records related to the audit were (86-374) addressed in response to a previous request, F0IA-86-356.
Zinovy Reytblatt, In response to a request for two categories of records Illinois Institute regarding the 79th meeting of the CRGR on July 3, 1985, of Technology made available nine records.
Informed the requester that (86-483) four additional records subject to this request are already available at the PDR.
Michael J. Keegan, In response to a request for records pertaining to the Safe Energy Fermi 2 reactor dome and flange of the reactor vessel Coalition of concerning scratches, pitting, corrosion, and cracks, Michigan made available five records.
(86-508)
Diane Curran, In response to a request for (1) records which form the Harmon & Weiss basis for a NUREG-0956 conclusion about the Mark I (86-586)
Containmentinsevereaccidents,(2) post-operating license records regarding analysis or evaluation of the containment or related systems of the Vermont Yankee reactors, (3) records containing discussions, analyses of and reports on the significance of the Chernobyl accident for U.S. Containment Designs, (4) staff reviews of records subject to categories 1, 2, and 3, and (5) records regarding the Vermont Yankee Safety study of the Vermont Yankee containment to be completed by September 1, 1986, made available 18 records.
Informed the requester that 26 additional records subject to this request are already available at the PDR.
Jim Pedro, In response to a request for a copy of SECY-85-65, NUS Corporation
" Quality Assurance Program Implementation Plan," made (86-605) available a ccpy of the requested record.
SEPTEMBER 26, 1986 ENCLOSURE A
5 Granted, Cont'd (Anindividual In response to a request for a copy of the OIA requesting investigation report on his concerns at the Tennessee information Valley Authority, made available a copy of the requested (86-637 record.
Steven Aftergood, In response to a request for copies of transcripts, minutes, Committee to meeting summaries, and handouts related to the July 17-Bridge the Gap 18, 1986 meeting on iodine chemistry sponsored by EPRI (86-644) and NRC, made available two records.
Paul 0. Shapiro, In response to a request for copies of all inspection Radiation reports for 1986 relating to South Jersey Processing Technology, Inc.
Technology located in Salem, New Jersey, made available (86-645) two records.
Paul 0. Shapiro, In response to a request for copies of inspection reports Radiation relating to Isomedix, Incorporated, located in Whippany, Technology, Inc.
New Jersey, made available two records.
Informed the (86-647) requester that additional records subject to this request are already available at the PDR.
Paul 0. Shapiro, In response to a request for copies of all inspection Radiation reports for 1986 relating to Radiation Technology, Inc.,
Technology, Inc.
located in Rockaway, New Jersey, informed the requester (86-648) that the NRC has no records subject to this request.
O. W. Ward, In response to a request for copies of all records Met Lab related to inspections of Met Lab, Incorporated, by Incorporated C. Rowe on December 18-19, 1985, and July 16-17, 1986, (86-654) made available five records.
Roger D. Wensil In response to a request for a list of licenses issued (86-659) to B. F. Shaw Co. and the Blount Brothers Co, made available nine records.
Informed the requester that the NRC has no record of a license issued to Blount Brothers Co.
Nina B. Blecher, In response to a request for a list of current data Sigma Data processing-related contracts, made available one Services Corp.
record.
(86-665)
Michael Jurinske In response to a request for a list of Region V employees, (86-676) made available two records.
SEPTEMBER 26, 1986 ENCLOSURE A
. ~ -. - -.
6 Denied Nina Bell, In response to a request for five categories of records Nuclear Information regarding Board Notification 85-081, " Allegations and Resource Concerning Westinghouse Analyses and Quality Assurance,"
Service regarding the Turkey Point nuclear power plant, made (85-654) available 35 records.
Informed the requester that additional records subject to this request are already available at the PDR. Denied three records in their entirety and portions of one record containing confidential business (proprietary) information. Denied portions of one record, disclosure of which would cause a clearly unwarranted invasion of personal privacy. Denied two records in their entirety containing predecisional advice, opinions and recommendations of the staff. Denied four records in their entirety containing predecisional advice, opinions, and recommendations of the staff and release of the information would disclose investigative techniques and procedures. Denied records in other NRC files, disclosure of which would interfere with an ongoing enforcement proceeding.
Billie P. Garde, In response to a request for records regarding inspections Government by Region IV into allegations by current or former Accountability employees of the Comanche Peak project about the stainless Project steel liner plates of the spent fuel pool, transfer canal, (86-180) refueling cavity, or any other facility at the site, made available eight records.
Denied 16 records in their entirety and portions of three records, disclosure of which would reveal the identities of confidential sources.
Billie P. Garde, In response to a request for records regarding Enforcement Government Action 86-09 dated May 3, 1986, on the Comanche Peak Accountability nuclear power plant, made available one record.
Informed Project the requester that four additional records subject to (86-386) this request are already available at the PDR. Denied one record in its entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process. Denied one record in its entirety, release of which would interfere with an ongoing enforcement proceeding and would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Billie P. Garde.
In response to a request for records relevant to and/or Government generated in connection with Inspection Report 50-445/
Accountability 85-18,50-446/85-15 dated May 12, 1986, on the Comanche Project Peak nuclear power plant, made available 26 records.
(86-387)
Informed the requester that one record subject to this request is already available at the PDR. Denied 12 records in their entirety containing advice, opinions, and recommendations of the staff.
SEPTEf1BER 26, 1986 ENCLOSURE A
l DIVISION OF ORGANIZATION AND PERSONNEL ITEMS OF INTEREST Week Ending September 26, 1986 OPM Approval of NRC Performance Management Plan The Office of Personnel Managenent has approved the NRC Performance Management Plan implementing our new performance appraisal system. The following actions were required to implement the Plan.
1.
Revision of NRC Chapter 4151, Non-SES Performance Appraisal System. The provisions of this Chapter, which will be first published as a Bulletin, become effective October 1, 1986, which is the beginning of the next performance appraisal cycle. The Chapter is applicable to both bargaining unit and non-bargaining unit employees. Negotiations with the union in this area are still pending.
2.
Revision of NRC Chapter 4152, Senior Executive Service Performance Appraisal System. The provisions of this revision become effective July 1, 1987.
3.
Revision of NRC Chapter 4154, Incentive Awards, which becomes effective upon publication.
4.
Revision of NRC Chapter 4130-C, Part IV, Step Increase which becomes effective upon publication.
5.
Revision of NRC Chapter 4170, Non-SES Reduction in Force (RIF). Tnis revision is already published and in effect.
SEPTEMBER 26, 1986 ENCLOSURE A
_ _ ~ -
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING SEPTEMBER 26, 1986 PROPOSAL UNDER EVALUATION RFP No.: RS-MS-87-002 il
Title:
" Assessment of MSS Financial Assurance Regulation Framework"
==
Description:==
The objective of this procurement is to assess NRC's Financial Assurance Program for NMSS licensees to determine the adequacy of the existing regulatory framework to assure that adequate l
financial assurance and sufficient coverage are in place and maintained at all times.
Period of Performance: 24 months Sponsor: Office of Nuclear Material Safety and Safeguards Status: The competitive range has been established and negotiations are scheduled for October 7, 1986.
)
i CONTRACTS AWARDED i
IFB No.: RS-0RM-86-282
Title:
"On-Call Maintenance of NRC's Computer Peripheral Equipment" 1
==
Description:==
Contractor to provide all necessary maintenance, labor, documentation, spare parts, maintenance supplies, tools, test equipment, and transportation for the maintenance of NRC's computer peripheral equipment.
j Period of Performance: Two years l
Sponsor: Office of Resource Management i
Status: A time and materials requirements type Contract No. NRC-33-86-282 was awarded to General Scientific Corp., effective September 23, 1986.
RFP No.: RS-0IE-86-155
Title:
" Technical Assistance for Design Inspections"
==
Description:==
The design inspections are intended to provide a close examination of the design process and design implementation for a limited sample of structures, systems or components for a specific facility and any of its associated design organizations.
Period of Performance:
36 months Sponsor: Office of Inspection & Enforcement i
Status: A cost-plus-fixed-fee task ordering type Contract No. NRC-05-86-155 was awarded to Westec Services, Inc., in the amount of $4,200,000
{
effective September 24, 1986.
RFP No.: RS-RES-86-117
Title:
"Paleoliquefaction Features on the Atlantic Seaboard"
==
Description:==
The objective of this project is to catalogue the characteristics j
of seismically induced liquefaction and paleoliquefaction features identified in the Charleston Earthquake area.
Those characteristics will then be used to design and carry out an investigation program in selected areas of the Atlantic i
Coastal Plain and at least one area that is relatively aseismic.
Period of Performance:
24 months i
Sponsor: Office of Nuclear Regulatory Research
~
A cost-plus-fixed-fee type Contract No. NRC-04-86-117 was awarded Status:
to Ebasco Services Inc., in the amount of $416,231.00 effective September 22, 1986.
j SEPTEftBER 26, 1986 ENCLOSURE A
Weekly Information Report Division of Contracts CONTRACTS AWARDED (cont'd)
RFP No.: RS-0IE-86-168
Title:
" Independent Assessment and Analysis"
==
Description:==
Perform independent assessments of materials and components for reactor construction and operation including fabrication and installation to ensure licensee compliance with applicable codes, star.dards and federal regulatory requirements.
Period of Performance:
36 months Sponsor: Office of Inspection & Enforcement Status: A cost-plus-fixed-fee task ordering type Contract No. NRC-05-86-168 was awarded to Franklin Research Center in the amount of $315,717.00 effective September 30, 1986.
RFP No.: RS-0RM-86-261
Title:
" Engineering Cost Analyses of Proposed Changes in NRC Requirements"
==
Description:==
Services for engineering cost analyses to identify, derive and analyze the engineering costs of proposed changes in NRC regulatory requirements.
Period of Performance:
30 months Sponsor: Office of Resource Managenent Status: A cost-plus-fixed-fee task ordering type Contract No. NRC-33-86-261 was awarded to Science & Engineering Associates, Inc., in the amount of $516,829.00 effective September 24, 1986.
ADMINISTRATIVE MATTER On September 10, 1986, Equitec Properties Company (Equitec) filed a protest with the General Accounting Office (GAO) under Solicitation No. RS-ADM-87-171 for " Commercial Facilities Management of One White Flint North." The protest disputes the Contracting Officer's decision to eliminate Equitec's proposal from consideration for contract award due to the late receipt of Equitec's proposal. On September 19, 1986, the GA0 concurred in the Contracting Officer's decision by dismissing the protest as without merit.
SEPTEf1BER 26, 1986 ENCLOSURE A
- ' [
u OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending September 26, 1986 1j Turkey Point' Plant, Units 3 and 4
^
The Atomic Safety and Licensing Board issued an initial decision (LB-86-23) on July 24, 1986, which disposed of Ms. Joette Lorion's and the Center for Nuclear Responsibility. Inc., contention relating to license amendments.
The amendments allowed changes in the F and F operating limits.
WH g
The Board retained jurisdiction on a previously disposed of contention which was related to an ECCS evaluation model using BART. Subsequent to disposing of the contention, Westinghouse notified the staff of errors in the code and the staff in turn notified the Board (BN-86-17). The Board will make its final decision on this issue when the staff informs the Board of its resolution of the identified errors.
1 By memorandum and Order dated September 16, 1986, the Atomic Safety and' Licensing Appeal Board indicated that their customary sua sponte review found s
no errors that warrant corrective action and ordered that LBP-86-23 is affirmed, i
La Salle County Station Unit 1 i
On September 15, 1986, La Salle 1 initiated a startup after a prolonged l
refueling outage, which commenced on October 18, 1985. The licensee was performing a scram discharge volume operability test required by the Technical Specification 4.1.3.1.4 by performing a plant scram after the rod configuration of less than or equal to 50% rod density has been attained.
In performing this test, the transient imposed a reactor water level variation such that i
the level 3 switches were actuated.
(These switches are the SOR switches t
which failed to actuate in Unit 2 in June 1986.) The scram level in the Technical Specification is 11 inches. Three out of the four level 3 switches did actuate above 11 inches. One appears to have reached 11 inches and did
+
not actuate. Unit 1 is currently down to investigate the switch performance.
- L Region III has asked the licensee to develop an action plan for NRC review i
before performing any maintenance or testing of the switch.
l Hope Creek Generating Station i
J A previous Daily Highlight, dated September 16, 1986, identified various equipmentfailureswhichoccurredduringaLossofOffsitePower(LOP) Test at Hope Creek.
In a telecon held on September 17, 1986, PSE&G provided additional information/ clarification concerning those failures:
loss of Reactor Auxiliary Cooling System (RACS) 4 RACS responded properly to LOP, but tripped on low head tank level.
diesel generator C output breaker failed to automatically close on its vital bus l
f SEPTET 1BER 26, 1986 ENCLOSURE B
. Failure to close due to hardware problems related to the infeed breakers.
diesel generators A and B (2 of the 4 DGs) output breakers closed in
" droop mode" (58Hz vs. required 60Hz)
Diesel generators A and B loaded properly, but shifted, per design, to droop mode after restoration of offsite power.
Source Range Monitors (SRMs)/ Intermediate Range Monitors (IRMs) did not drive into core after scram SRMs/IRMs did not drive into core, nor are they designed to after LOP.
position indication lost on 17 control rods
" Full-in" on 17 rods was not indicated after the scram; however, rods were indicated inserted to the "0-0" position. The 0-0 position is one notch above full-in.
false fire indication received Diesel generator exhaust fumes blown by high winds, reverted down the exhaust header causing an exhaust header fire sensor to indicate a fire.
certain water system pumps failed to start The "B" Safety Auxiliary Cooling System (SACS) (closed loop component cooling water system) pump failed to start. Licensee investigation ongoing.
Main Steam Isolation Valve (MSIV) position indication lost MSIV position indication was lost since it is powered from a non-vital bus.
certain Filtration Recirculation Ventilation System (FRVS) Standby Gas Treatment System (SGTS) fans failed to start FRVS fans are not automatically started on LOP. However, the Reactor Building Ventilation System fans, which are started automatically, tripped, due to a supply damper remaining closed.
Prior to going critical again, the licensee will perform a "non-critical" LOP test to re-test plant performance.
i SEPTEMBER 26, 1986 ENCLOSURE B
Proposed Assignment of NRR Staff Member to French Regulatory Agency Arrangements are being made for Dr. Arthur J. Bus 11k, a senior reliability and risk analyst in the NRR Division of Safety Review and Oversight, to begin l
a one-year assignment to the staff of the French Central Service for the l
Safety of Nuclear Installations (SCSIN) either this fall or early in 1987.
This assignment is in response to numerous invitations we have received from the French CEA/SCSIN. France has sponsored key personnel for the past several years to work on and learn from the NRC staff under similar circumstances.
Dr. Busiik will assist in the application of probabilistic safety analysis in France, beginning with the results of a just-completed NRC study of their 900 MW nuclear power plants. The staff expects this assignment to result in NRC's increased knowledge of safety technology, regulatory decision-making, and licensing in France, as well as better understanding of the effects of standardization on the safety, economy, and costs of regulation of nuclear l
power plants.
Seabrook, Unit 1 On September 20, 1986, Massachusetts Governor Michael S. Dukakis announced his decision that he will not submit Seabrook emergency plans for the six Massachusetts communities closest to the plant. He indicated that in his best judgment emergency-plans could not constitute appropriate protective measures adequate to protect the public health and safety in the event of a radiological emergency. The announced decision did not note any conditions that would mitigate his decision.
Hope Creek Generating Station An Augmented Inspection Team (AIT) will be dispatched to Hope Creek and a l
Confirmatory Action letter (CAL) will be issued to PSE&G as a result of the l
equipment performance deficiencies experienced during the September 11, 1986, l
Loss of Offsite Power (LOP) test, and the subsequent non-critical LOP retest held September 19, 1986. The AIT will commence Thursday, September 25, 1986, and will conclude late next week. The AIT will review Hope Creek design control and the adequacy of the preoperational test program. The CAL will require PSE&G to provide additional information regarding the LOP tests, and to investigate the broader implications of the equipment performance deficiencies.
In the meantime, Hope Creek is to be maintained in the shutdown condition.
. Prairie Island Nuclear Generating Unit Nos. I and 2 License Extension On September 23, 1986 the Commission issued amendments for the operating licenses of the Prairie Island Nuclear Gererating Plant Unit Nos. I and 2 that extend the license expiration dates for both units from 40 years after the issuance of the Construction Permit to 40 years after the issuance of the Operating License.
SEPTD!CER 26, 1986 ENCLOSURE B
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR SEPTEMBER 22 - 28, 1986 1.
DEFUELING One additional end fitting has been removed from the reactor vessel and stored in a shielded 55-gallon drum.
Problems with faulty in-vessel lighting and high turbidity are causing poor visibility and impeding defueling progress.
Efforts continue to restore water clarity in the reactor coolant system (RCS). Operation of the vacuum system with polypropylene bag filters proved to be of limited usefulness. Test runs with a deep bed diatomaceous earth filter installed in the Defueling Water Cleanup System (DWCS) were completed and the test data is being evaluated.
The NRC staff approved GPUN's plan for temporary end fitting storage. This allows GPUN to store a planar array (ie. no stacking) of 55-gallon drums containing end fittings and incidental attached fuel in a designated storage area on the 347 ft. elevation of the reactor building. The staff had previously approved storage of a single drum.
GPUN has had difficulty getting end fittings through the openings in fuel canisters. Since the end fittings currently impede free access to the debris bed and crust, removal and storage of end fittings will facilitate the defueling progress.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to the atmosphere. Core cooling is by natural heat loss to ambient building atmosphere, average air temperature of 56 F.
The average RCS temperature is 76*F.
The airborne radioactivity on the defueling platform above the reactor vessel is about 2.4 E-7 uCi/cc tritium and 9.7 E-12 uCi/cc particulates, predominately cesium-137 and strontium-90. About 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters provide shielding.
3.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and The City of Lancaster Agreement.
The Lancaster water sample taken at the water works river intake and analyzed by EPA consisted of a seven day composite sample taken September 7 - 13, 1986. A gamma scan detected no reactor related activity.
SEPTEMBER 26, 1986 ENCLOSURE B
TMI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven daily composite samples taken from September 7 - 13, 1986. A gamma scan detected no reactor related activity except.
The EPA analyses of the NRC outdoor air sample for the period September 19 - 25, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detection (LLD) for the system. The LLD varies around a value of 1E-13 uC1/cc.
4.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Start-up testing of the sludge transfer system continues.
5.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request numbers 49, 51, 52, and 54.
Recovery Operations Plan Change numbers 31 and 33.
Solid Waste Facility Technical Evaluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
Disposal of Processed Water Report.
Sediment Transfer and Processing System SER.
End Fitting Storage SER was approved on September 25, 1986.
SER for Use of Plasma Arc Cutting Torch.
Core Bore Operations (as a defueling method).
6.
PUBLIC MEETING The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 will be held on October 8, 1986 at the Holiday Inn, Center City, Harrisburg, PA from 7:00 PM to 10:00 PM.
Persons desiring to speak before the Advisory Panel are requested to contact Mr. Thomas Smithgall at 717-291-1042, or write him at 2133 Marietta Avenue, Lancaster, PA 17603.
SEPTEMBER 26, 1986 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending September 26, 1986 Pennsylvania -- Host State Appalachian Compact The Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection (BRP), and its Public Advisory Committee on LLW have developed draft documents for Area Screening and Facility Design Criteria.
BRP submitted its Design Criteria document to five potential contractors (Chem Nuclear, U.S. Ecology, Pacific Nuclear, Westinghouse Hittman, Nuclear Monitoring Systems) for review and comment. A meeting was held on September 18, 1986, to provide the potential contractors the opportunity to speak to the BRP and the Public Advisory Committee about the Design Criteria document.
Division of Waste Management staff will meet with BRP in October to discuss the Design Criteria document.
FBI Criminal History Rule The proposed FBI Criminal History Rule is being revised in accordance with the CRGR memorandum identifying proposed modifications.
In addition, on the advice of OGC, the staff is preparing an OMB clearance request regarding use of the FBI fingerprint cards.
Kerr-McGee -- West Chicago A representative of Kerr-McGee met with FC staff concerning the West Chicago facility.
They inquired into the status of two pending amendment applications.
They also inquired into the possibility of expanding their decontamination activities at the site.
It was decided that they should submit applications for the proposed activities.
Sequoyah Fuels Corporation On September 22, 1986, Sequoyah Fuels Corporation (SFC) representatives met with NRC staff to discuss the status of the SFC facility and some of the commitments to NRC.
Also discussed was the termination of a shift analyst that was found to be falsifying analyses of operational control samples.
Regarding the facility status, SFC provided the staff with a copy of a letter sent to employees to inform them of a reduction in forces until authorization is received to restart the facility.
A total of 104 employees were laid off, some of which will be recalled to process existing liquids to UF.
SFC representativesprovidedthestatusof(1)commitmentsmadeintheinformation provided by letter dated June 25, 1986, (2) decontamination of Pond 2, and (3) the perimeter security system.
N EC SEPTEMBER 26, 1986
~
Office of Inspection and Enforcement Items of Interest Week Ending September 26, 1986 1.
Items of Interest a.
Safety System Functional Inspection A Safety System Functional Inspection was initiated at the Consumers Power Palisades facility. The entrance meeting was held and'inspec-tion efforts were initiated to assess the operational readiness and functionality of the safety injection system.
b.
Systematic Assessment of Licensee Performance The initial issue of NUREG-1214, Historical Data Summary of the Systematic Assessment of Licensee Performance, has been approved for publication. This NUREG replaces the SALP Management Summary Periodic Update; the last issue was dated July 18, 1986.
2.
The following Signifi_ cant Enforcement Actions were taken during the past week:
a.
An Order Imposing Civil Penalty was issued to Duke Power Company (McGuire) in the amount of $50,000. This action was based on a viola-tion of tech spec requirements involving isolation valves for the Volume Control Tank on safety injection signal (EN 86-35A).
b.
A Notice of Violation and Proposed Imposition of Civil Penalty was issued to South Carolina Electric and Gas Company (Summer) in the amount of $50,000. This action was based on multiple violations involving the inoperability of charging pumps.
(EN 86-70) 3.
The following IE Preliminary Notifications were issued during the past week:
a.
PNS-I-86-15, Philadelphia Electric Company (Limerick), Federal Grand Jury Indictment of Security Contractor - Y0H Security, Inc. and Former Employees.
b.
PN0-I-86-74, Siemens Gammasonics (Chicago, IL) - Theft of Radio-active Material.
PN0-I-86-75, Public Service Electric & Gas Company (Salem ) - Unplanned c.
Shutdown in Excess of 48 Hours.
l d.
PNO-I-86-76, National Institutes of Health (Bethesda, MD) - Spill of Radioactive Water.
c.
PN0-I-86-77, Radiation Technology, Inc. (Rockaway, NJ), Line Break Involving Irradiator Pool Water.
f.
PN0-II-86-65, Carolina Power and Light Company (Brunswick 1) -
Unscheduled Shutdown Longer than 48 Hours.
SEPTEMBER 26, 1986 ENCLOSURE D
2 g.
PNO-II-86-66, Florida Power and Light Company (St. Lucie), Media Intere;t in Hydrogen Storage Tube Leak, b.
PN0-Ii.86-67, Virginia Electric and Power Company (Surry 1), Unsched-uled :inutdown Longer Than 48 Hours.
1.
PNO-II-86-68 Nuclear Fuel Services (Erwin), Media Interest in Repri-mand of Employee.
J.
PNO-III-86-101, Commonwealth Edison Company (Braidwood 1) - ASLB Authorization of Limited License.
k.
PN0-III-86-102, Dairyland Power Cooperative (LACBWR), Variation Between Alarm and Reactor Trip Set Points.
1.
PNO-III-86-103, Detroit Edison Company (Fermi 2), Water Chemistry Problems; Grid Synchronization.
PNO-III-86-104, Iowa Electric Light and Power Company (Duane Arnold),
m.
Shutdown for Recirculation Pump Bearing Problem.
PN0-IV-86-29, Public Service Company of Colorado (Fort St. Vrain),
o.
Results of PSCo Board Meeting.
p.
PNO-IV-86-30, Arkansas Power and Light (ANO-2), Outage Greater Than 48 Hours.
4.
The following IE Information Notices and Bulletins were issued during the past week:
None.
SEPTEMBER 26, 1986 ENCLOSURE D
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending September 26, 1986 Containment Performance Design Objective RES, in coordination with NRR, is developing a Containment Performance Design Objective (CPD0) for the Comission's approval for the staff to use as a guidance for implementation of the Comission's safety goal requirements. As a part of this effort, Brookhaven National Laboratory submitted their final draft of the Highlights Report of the May 12-13 workshop on September 18. The RES staff completed their preliminary position on the final CPD0 option. On September 23, the RES staff briefed the ACRS Subcomittee on Containment Requirements on the status of this work. The members of the Subcomittee felt that the staff approach for developing the final CPD0 was in the right direction. They made a number of valuable suggestions on the content and implementation of the CPDO. The Subcomittee expressed their interest in being kept appraised of the outcomes of this research.
Emergency Core Cooling Systems: Revisions to Acceptance Criteria (Part 50) (Appendix K)
On September 15, 1986 the Advisory Comittee on Reactor Safeguards (ACRS) transmitted a letter to the Comission recomending that the Notice of Proposed Rulemaking regarding the ECCS proposed rule be published in the Federal Register for public coment. Currently the proposed rule is under final review
-by OGC and NRR. Final concurrence from these offices is expected by the end of the week. The proposed rule has been reviewed by DEDO staff.
The proposed rule will be forwarded to the Comittee to Review Generic Requirements (CRGR) upon OGC and NRR concurrence.
International Code Assessment and Applications Program (ICAP)
The ICAP Program is an international cooperative reactor safety research program initiated by RES in 1985 to provide an independent assessment of NRC's thermal hydraulic codes developed for analysis of postulated transients and breaks. The program is planned to continue over a period of approximately five years. The results from the ICAP Program as well as the domestic code assessment studies will be used by the staff to quantify code uncertainty.
SEPTEMBER 26, 1986 ENCLOSURE E
2 Currently RES has 11 effective agreements with European and Asian countries, and 3 proposed agreements are under negotiation. Each ICAP participant has agreed to perform a certain number of code calculations and tests for NRC.
In order to ensure that proper tests are performed at each type of foreign facility to meet requirements of the uncertainty analysis, the RES staff is currently developing a complete matrix of assessment tests for the ICAP.
With the support of three national labs, INEL, LANL, and Sandia, a list of available experiments for every type of facility (domestic and foreign) has been established. The RES staff and the contractors will meet on October 6 and 7, 1986 at Nicholson Lane Building, Room 014, to determine the test matrix that will satisfy the goals of the ICAP Progam.
The 5-year program is only about one year old and is beginning to produce promising results. The results are being published as NUREG/IA Reports. The first NUREG/IA report on " Assessment of TRAC-PD2 Using Super Cannon and HDR Experimental Data" (Germany) was published in August, 1986. Three other NUREG/IA reports are being printed and will be distributed in September, 1986.
20/3D The 2D/3D test data are being usad to check how accurately the Transient Reactor Analysis Code (TRAC) can predict the phenomena occurring during the refill and reflood process of a PWR large-break LOCA. Mathematical model deficiencies still exist in various areas including steam-water direct contact condensation, entrainment and deentrainment of water droplets in the upper plenum, and the liquid droplet distribution above the quench front in the core.
In order to improve the models in these areas, RES is negotiating with the Japanese and the Germans to divert some of the funds allocated for post-test data analyses. Through a similar reprogramming during the past year, TRAC models have been improved in the areas of steam-water countercurrent flow model at the core-upper plenum interface, steam-water separator model, and capability of connecting more than one fluid source to a computational cell.
Symposium on Chemical Phenomena Associated with Radioactivity Releases During Severe Nuclear Plant Accidents A symposium on Chemical Phenomena Associated with Radioactivity Releases during Severe Nuclear Plant Accidents was held on September 9-12, 1986 at Anaheim, California. The Symposium, which was made possible in part by a grant from NRC to the American Chemical Society (ACS), was part of the overall 192nd ACS National Meeting.
It covered topics on chemical phenomena occurring in the fuel, the reactor coolant system, the concrete cavity and elsewhere in the ENCLOSURE E SEPTEMBER 26, 1986
3 containment. Some general overview papers were also presented to acquaint other professionals at the ACS meeting with severe accident chemistry. Of all the papers presented in the symposium, over 40 percent came from NRC-sponsored programs. By encouraging our contractors to present their work at an ACS National Meeting, additional severe accident research work has been made available for review by the mainstream technical community. During the meeting, two panel discussions were conducted. The first, which was held at the beginning of the meeting, was focused on the accident at Chernobyl.
Members of the panel included NRC contractors who participated in the IAEA meeting in Vienna. The second panel discussion was held on the last day of the meeting and was focused on important chemical phenomena that affect severe accident source terms. One of the conclusions reached by the panel was that core-concrete interaction is an important contributor to radioactivity release f
to the environment and is an appropriate area of current research.
I Wide-plate Crack Arrest Tests The eighth in a series of eighteen wide-plate crack arrest tests was conducted -
at the National Bureau of Standards, Gaithersburg, at approximately 2:30 p.m.
on Wednesday September 24, 1986. These tests sponsored by the NRC and conducted by the NBS in a cooperative effort with the Heavy Section Steel Technology (HSST) program have several objectives. First is the need to develop high value crack arrest data for the steels and weldments used in the first generation and present practice reactor vessels. Second is the validation of analytic methods used to predict the fracture characteristics of flawed reactor vessels subject to pressurized thermal shock conditions. And third is the need to develop data to better understand the entire fracture process during a crack initiation-run-arrest event.
To carry out these objectives these tests are structured to give strain
' readings, discriminating in the microsecond range. The test itself is comprised of a test section measuring 1 meter by 1 meter by 101.6 or 152.4 millimeters thick, welded to pull plates 10 meters between grips. The test section is highly instrumented with strain gages and thermocouples along the planned crack path. The specimen is emplaced in NBS's 12 million pound test machine (the largest in the U.S.) and pulled until fracture occurs. The strain gage data is captured by very high speed electronic recording instrumentation.
To simulate both the fracture degradation of the steel due to irradiation effects and the thermal conditions existing in a reactor vessel during a pressurized thermal shock event, the plated is cooled along its leading edge andheatedglongitstrailingedgetoestablishalineartemperaturegradient of over 200 C along the crack path. The length of the specimen was selected to ensure that the initiation-run-arrest event would be complete before the unloading stress wave, initiating at the running crack tip, travels to the grips and returns to the crack tip as a dynamic loading wave, again simulating what would occur in a real reactor vessel.
SEPTEMBER 26, 1986 ENCLOSURE E
4 i
The first six tests employed a present practice, high Charpy V-Notch Upper Energy toughness plate similar to that used in most of the reactors in service.
The results of these tests demonstrated, that at least for this material, the analytic methods applied to the resolution of Unresolved Safety Issue A-49,
" Pressurized Thermal Shock," are accurate and the assumed material properties The seventh and eighth test specimens were fabricated from are conservative.
a plate material which simulates low Charpy Y-Notch Upper Energy toughness plates and welds found in some of the older vessels in service.
The seventh test, with a plate thickness 101.6 mm. toughness gave results which indicated that the upper values of crack arrest values as specified in the ASME Boiler & Pressure Vessel Code,Section XI, are probably not applicable for judging the structural adequacy of reactor vessels fabricated with low-upper shelf energy plates and welds. It dramatically demonstrated that Charpy V-Notch, low-upper shelf energy plate and weld material, found in some of our older plants, would fail in a ductile failure mode if a crack were to initiate The eighth test specimen had a plate thickness of 152.4 mm, and in the vessel.
the results from this test reinforced the findings from the seventh and in addition clearly indicated that data taken from small specimens are subject to -
a size affect that must be compensated for before applicability of results could be shown for actual reactor pressure vessels.
This experimental program, which utilizes the talents of the staffs of the HSST program at Oak Ridge National Laboratory, the staff of the National Bureau of Standards, and personnel from the Southwest Research Institute, the Battelle Columbus Division, Harvard University, Ohio State University, Brown University and the University of Maryland, is generating data that not only validates and confirms present regulatory positions but is also generating fundamental information that is leading to a thorough understanding of the fracture process and the parameters affecting that process which will help in the establishment of the NRC's regulatory position on the questions of plant aging and plant life extension.
Recently Issued Publication i
Regulatory Guide 5.65, " Vital Area Access Controls, Protection of Physical Security Equipment, and Key and Lock Controls".
i 1
ENCLOSURE E j
SEPTEi18ER 26, 1986
5 l
RES RULEMAKING ACTIVITIES Primary Reactor Containment Leakage 'iesting for Water-Cooled Power Reactors (Part 50) (Appendix d)
The proposed rule would update and revise the 1973 criteria for preoperational and periodic pressure testing for leakage of primary and secondary containment boundaries of water-cooled power reactors. The revision is needed to reflect current regulatory practice and current technology which are no longer being reflected accurately by the existing rule, and endorsement in the existing regulation of an obsolete national standard that was replaced in 1981.
A SECY memo dated September 18, 1986, advised that all Commissioners had approved publishing for public comment the proposed revision to Appendix J and its related regulatory guide. Commission comments for incorporation into the Federal Register notice reflect difficulties with the application of the Backfit Rule to NRC rulemaking. A 90-day public comment period is planned.
SEPTEMBER 26, 1986 ENCLOSURE E
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING SEPTEMBER 26, 1986 International Meeting Notices The following international meeting notices supplement those announced earlier:
IAEA Technical Committee Meeting on Gas-Cooled Reactors and Their Applications, October 20-23, 1986, Juelich, Federal Republic of Germany IAEA Consultants' Meeting for a Coordinated Research Program on Dose / Intake Factors for the Public, October 20-24, 1986, Vienna, Austria IAEA Consultants' Meeting on Spent Fuel Management, October 27-31, 1986, Vienna, Austria IAEA Consultants' Meeting on Evaluation of Electron High-Dose Intercomparison, October 29-31, 1986, Vienna, Austria IAEA Technical Committee Meeting on Advances in Light Water Reactor Technology, November 24-25, 1986, Washington, D.C., USA IAEA Consultants' Meeting on International Criteria and Techniques in Quality Assurance and Quality Control in Nuclear Fuel Fabrication, December 1-3, 1986, Vienna, Austria IAEA Advisory Group Meeting on Nuclear Data for Fusion Reactor Technology, December 1-5, 1986, Technical University Dresden, Gaussig/Dresden, German Democratic Republic IAEA Interregional Training Course on Safety and Reliability in Nuclear Power Plant Operation, March 16-April 17, 1987, ANL, Argonne, Illinois, USA International Agency Vacancy Notices The following vacancy notices from the International Atomic Energy Agency located in Vienna, Austria, have been posted on NRC bulletin boards:
P-5 Nuclear Geologist / Economist, Nuclear Materials & Fuel Cycle Technology Section, Division of Nuclear Fuel Cycle, Department of Nuclear Energy and Safety P-4 Nuclear Medicine Physician, Medical Applications Section, Division of Life Sciences, Department of Research and Isotopes SEPTEMBER 26, 1986 ENCLOSURE G
2 International Agency Vacancy Notices continued P-1 Soil Scientist, Soil Science Unit, FA0/IAEA Agricultural Biotechnology Laboratory, Seibersdorf Laboratory, Department of Research & Isotopes P-5 Section Head, Dosimetry Section, Division of Life Sciences, Department of Research and Isotopes P-5 Section Head, Division of Operations A, Department of Safeguards P-4 Safeguards Analyst, Section for System Studies, Division of Development and Technical Support, Department of Safeguards P-3 Specialist in the Chemical Analysis of the Materials of the Nuclear Fuel Cycle, Safeguards Analytical Laboratory, Seibersdorf Laboratory, Department of Research and Isotopes Foreign Visitors On Monday Dr. Jan Baas, Head of Radiation Enforcement and Compliance of the Dutch Ministry of Housing, Fiscal Planning and Environment, visited NRC for discussions on nuclear waste management issues with NRR and emergency planning and inspection activities with IE.
Also on Monday Dr. Yasumasa Togo of the Department of Nuclear Engineering of the University of Tokyo met with Dr. D. F. Ross and J. Cortez of RES to discuss the status of the NRC's plant aging program and its regulatory implications.
On Friday Dr. Boris Friec, the Vice President of Slovenia, one of the Yugoslav states, met with Commissioner Roberts to discuss the Yugoslav nuclear program and cooperation between NRC and Yugoslav nuclear safety authorities.
SEPTEMBER 26, 1986 ENCLOSURE G
l 0FFICE OF RESOURCE MANAGEMENT Item Of Interest Week Ending September 26, 1986 i
Cash Payment Of Travel Vouchers i
Walk-in service for cash payment of travel vouchers will be expanded to include all Headquarters employees on September 29, 1986. An announcement is being issued tc provide further details.
1 SEPTEf1BER 26, 1986 ENCLOSURE I
DEPUTY EXECUTIVE DIRECTOR FOR REGIONAL OPERATIONS AND GENERIC REQUIREMENTS (DEDROGR)
Week Ending September 26, 1986 CRGR Attached is a summary of the CRGR activities for the period August I through August 31, 1986. Background material on topics reviewed by the Committee and the minutes of CRGR meetings are sent to the Commission. Copies are provided to the Public Document Room after the NRC has considered (in a public forum) or decided the matter addressed by the documents. Questions concerning this monthly report should be referred to Walt Schwink (492-8639).
l SEPTEMBER 26, 1986 ENCLOSURE N
Dato: September '26,1986 Page 1 of I
SUMMARY
OF CRGR ACTIVITIES August I through August 31, 1986 v,
9M85 Meeting No.
Sg Meeting Date CRGR CRGR Pecommendation n,(Announcement fn Date)
Agenda Status to EDO EDO Action G
ES 95 Review, Proposed Final Pending CRGR recommended that RES work None required at this 8/27/86 Revision of ECCS Pule with OGC to develop final rule.
time.
Contained in Appendix K and Revised package should be for-Section 50.46 of 10 CFR 50 warded to CRGR to determine if additional review is needed.
-Sponsoring Office - RES
_ Category 2 Item
-Issue # 141
_________________________________________________________d no comments or No action required.
Complete CRGR provide Briefing, Severe Accident Management Strategies to recommendations on this matter.
i Enhance Accident Mitigation Capabilities of the Park I Containment
-Sponsoring Office - NRR
-Category 2 Item
-Issue #14?
94 Review Final Draft of Pending CRGR recommended that the Policy No action required at Statement be modified to address this time.
C/22/86 Proposed Commission Policy CRGR concerns prior to resubmittal Paper on Tech. Specs.
to the CPGR.
m M
_ Sponsoring Office _ NRR Es
-Category 2 Item gj
_ Issue #143 m
2
m4 NRR MEETING NOTICES
- S SEPTEMBER 26, 1986 M
- o i
DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 9/17-10/15/86 50-456 Phillips Building Determine what staff require-NRC Staff / CECO J. A. Stevens 50-457 ments remain to te met to re-i solve Braidwood licensing issues 1
Room P-422 Discuss Connecticut Yankee's NRC/CYAPC0 A. Wang i
9/29/86 10:00 a.m.
Phillips Building Preliminary Findings and Report on Undefined Eddy Current i
Signals in the Tubesheet Region i
of the Steam Generator Tubes 1
Room 6507 Discuss management issues re-NRC/BWOG W. A. Paulson l
9/29/86 j
10:00 a.m.
MNBB lating to the BWOG prioritiza-tion, recommendation, tracking and implementation procedures 9/30/86 50-295 Room P-114 Discuss Zion's compliance with NRC/ CECO J. Norris 8:30 a.m.
50-304 Phillips Building Appendix R to 10 CFR 50 9/30/86 50-309 San Francisco Airport Discuss progress of the Seis-NRC/ Peer Review P. M. Sears 9:00 a.m.
Clarion Hotel mic Design Margins Program at Panel /LLNL/EQE,Inc/
Millbrae, CA Maine Yankee Maine Yankee /Energey 10/2/86 50-322 Room P-118 Discuss certain aspects of the NRC/LILCO R. Lo I
g 10:00 a.m.
Phillips Building Shoreham fire protection program o
8 i
C Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s)
A in the NRC and local public document rooms o
I A summary of these meeting notices can be obtained by calling 492-7424 i
i
a l
M ia NRR MEETING NOTICES
- g SEPTEMBER 26, 1986 4
m9 lM DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT C
,'8 10/1/86 50-416 Room P-118 Discuss (1) methods used to cal-NRC/HCOG L. L. Kintner i
9:00 a.m.
417/440 Phillips Building culate heat transfer to equipment 50-458 during hydrogen combustion &
459/461 (2) hydrogen release history assumptions which serve as a basis for emergency procedure guidelines i
10/1-2/86 50-267 Room P-422 Discuss the technical specifi-NRC/PSC/0RNL/INEL C. S. Hinson 9:00 a.m.
Phillips Building cation upgrade program (TSUP) status i
10/2/86 Room P-114 Discuss system accuracy capa-NRC/ Licensee /0ther J. Thoma i
10:30 a.m.
Phillips Building bilities of the inadequate j
core cooling system 10/3/86 50-295 Room P-110 Discuss Zion's compliance with NRC/ CECO /
J. Norris 9:30 a.m.
50-304 Phillips Building 10 CFR 50.61 - Pressurized Westinghouse l
Thermal Shock 10/6/86 50-213 Haddam Neck Plant Health Physics Training and NRC/NU F. M. Akstulewicz j
7:15 a.m.
East Haddam, Conn.
Access Badging l
10/8/86 Room P-422 Discuss content and schedule NRC/WOG/
F. Orr j
9:00 a.m.
Phillips Building for WOG ERGS Westinghouse 10/8/86 50-219 Room P-114 Discuss the status of licensing NRC/GPUNC mg 9:30 a.m.
Phillips Building actions for Oyster Creek I5 1 y A
Copies of summaries of these meetings will be made publicly. available and placed in the respective docket file (s) o in the NRC and local public document rooms y
i A summary of these meeting notices can be obtained by calling 492-7424 i
i
NMSS MEETING NOTICES 4
FOR WEEK ENDING: 9/26/86 mq Divisi,on of Fuel Cycle and Material Safety C!
ATTENDEES /
65 DOCKET APPLICANT NRC CONTACT g
DATE/ TIE NUM ER_
LOCATION PURPOSE
- 9/29/86-70-371 Montville, CT To participate in TI2600 G. Bidinger, FC Bidinger m
s cn inspection at UNC., Inc.
Region I Staff Representatives of G
10/3/86
)$
UNC,, Inc.
j 10/6-10/86 70-1113 Wilmington, NC To participate in'TI2600 G. Bidinger, FC Bidinger inspection at General Region II Staff Representatives of Electric j-General Electric San Francisco, Participate in Annual Agreement R. E. Cunningham, FC Wilde R. M. Wilde, FC l
10/5-10/86*
~
CA States Meeting S. L. Baggett, FC f
To discuss submittal by Nuclear J. Robert, FC Roberts i
10/9/86 Project Willste Bldg.
J. Rollins, et al, No. M-44 Silver Spring Packaging, Inc., of a topical NUPAC safety malysis report for a con-
{
crete dry spent fuel storage cask design.
Meeting with Japanese officials R. E. Cunningham, FC Cunninghant l
10/10/86 Room 560 W111ste Bldg.
regarding incorporation of ICRP Dr. Jun Akaishi of JAERI l
Silver Spring Paris statement into U. S.
regulations.
To discuss submittal by General J. Roberts, FC Roberts J
i No. M-37 Livermore Nat.
Nuclear Systems, Inc., related R. Anderson, et. aT, l
10/17/86 Project Lawrence GNSI Lab., Liermore,
'to design of a borated stainless California steel basket for the CASTOR V/21 i
!mg cask.
~
l5
,m E
,m jo
- Cunningham, 10/6-8/86; Baggett, 10/8-10/86; Wilde,10/5-10/86 l
i
DIVISION OF WASTE MAllAGEMEllT v,
9 y
PURPOSE ATTENDEES CONTACT i
O DA1E LOCATION 55 4
m 10/7-9 San Francisco, CA To attend OSP Annual Agreement State Meeting RMacDougall RMacDougall y
f1RKnapp MJSeemann l
G8 i
i 9
A 1
P S
E m
- U a
S:ptember 26, 1986 RII MEETING NOTICE y,
m 25 DOCKET ATTENDEES /
EE DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT ll 10/1/86 RIl Office Enforcement Conference Licensee, Regional Walker 10:00 am FP&L - Turkey Point Administrator and selected RII staff s,
as members G
E$
10/2/86 Dothan, AL Alabama Power Company Licensee, Deputy Ernst 8:30 am SALP Meeting Regional Administrator, and selected RII staff members 10/3/86 RII Office Enforcement Conference Licensee, Regional Walker 10:00 am CP&L - Harris 10/8/86 Raleigh, NC Commissioner Carr at Commissioner Carr, Carr Shearon Harris facility Regional Administrator for site familiarization and selected RII staff members 10/8/86 Erwin, TN NFS Improvement Program J. Roe and Regional Grace Administrator and selected RII staff members E
Pg
!5 m
T
REGION III MEETING NOTICES E
WEEK ENDING: October 12, 1986 9
EX ATTENDEES /
DOCKET y DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT m
10/09/86 50-409 Region III SALP Dairyland Power Cooperative A. B. Davis 10:00 a.m.
E P
E m
T