ML20052F138
| ML20052F138 | |
| Person / Time | |
|---|---|
| Issue date: | 05/05/1982 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-820430, NUDOCS 8205120153 | |
| Download: ML20052F138 (38) | |
Text
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May 5, 1982 t
l For:
The Commissioners l
g i
From:
T. A. Rehm, Assistant for Operations, Office of the EDO l
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 30, 1982 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
Executive Legal Director 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 Report M*
Executive Director for Operations N*
Items Addressed by the Commission 0
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- No input this week.
/ fI O
T. A. Rehm, t for Operations Office of the Executive Director I
for Operations FOR SUBSCRIBERS,
Contact:
T. A. Rehm, E00 492-7781 8205120153 820505 PDR COMMS NRCC WECALYINFOREPT PDR
5
SUMMARY
OF WEEKLY INFORMATION REPORT Week Ending April 30, 1982 Quad Cities Station - Spent Fuel Storage Action In April 1981, Commonwealth Edison filed an application to increase spent fuel storage capacity at the Quad Cities Station.
All the intervenors involved in the spent. fuel modification proceeding requested withdrawal of all contentions and withdrawal from the proceedings.
St. Lucie Unit 1 On April 24, 1982, while operating, St. Lucie Unit 1 experienced a 15 to 20 gpm primary coolant leak from a pressurizer spray control valve to containment atmosphere. The leak exceeded the tech spec limit of 10 gpm but was isolated within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> allowed prior to required plant shutdown. The cause of the leak will be investigated and repaired during an outage scheduled to begin May 5, 1982.
Broken IAEA Seals During an IAEA inspection at the Rancho Seco reactor 6n April 26, the IAEA found that all four of their safeguards seals for the pressure vessel were broken. Although the cause has not been established, the breakage may be associated with the extensive maintenance that has taken place in the general area during the past month. There is no indication of missing material.
Memorandum of Agreement (M0A) with the Nuclear Safety Analysis Center (NSAC)
A M0A has been signed by the NRC and NSAC for a cooperative relationship in the exchange and feedback of operational experience, information and data related to the safety of nuclear power plants. The NSAC/NRC Agreement parallels the recently signed M0A with INP0 with regard to operational data.
Auxiliary Feedring Update B&W, along with the owners of the plants involved in this problem (0conee III, Davis-Besse, and Rancho Seco) have decided that a permanent "fix" must be found; Rancho Seco will be the first plant to receive and install the "fix".
All three plants will use the same design, however, the design for the "fix" is not yet decided.
0FFICE OF ADMINISTRATION Week Ending April 30, 1982 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 240 6
Granted 178 0
Denied 24 6
Pending 38 0
ACTIONS THIS WEEK Received (An individua.1 requesting Requests three categories of records relating information about himself) to himself.
(82-209)
Richard A. Udell, Requests a copy of the segregable portions of Critical Mass NUREG-0844, " Resolution of Unresolved Safety Energy Project Issues A-3, A-4, and A-5 Regarding Steam (82-210)
Generator Tube Integrity."
Richard I. Lavine, Requests all documents concerning the activities Counsel for Requester of the Texas Mobilization for Survival (Texas (82-211)
Mobe).
Katharine A. Watkins, Requests a copy of SECY-82-72A concerning a Lowenstein, Newman, proposal for a joint industry-NRC program on Reis & Axelrad steam generators.
(82-212)
Granted
-(NRC employees')
In response to requests for eight categories of (82-185,82-186 information regarding Vacancy Announcement 82-0570,
&82-187) made available two documents.
John W. Sullivan In response to a request for a list of companies, (82-190) individuals, institutions and government agencies which have been issued licenses for the ocean disposal of radioactive wastes, informed the requester this information is already available at the PDR.
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A O
5 2
Granted, Cont'd (NRC employee)
In response to a request for information on (82-197)
Vacancy Announcement 82-037, made.available three documents.
Kim Huls In response to a request for information on (82-208) nuclear energy, made available one document.
Denied Thonas C. Wheeler, In response to a request for five categories Pettit & Martin of documents concerning the Atlas Machine & Iron (82-20)
Works, Inc., Gainesville, Virginia, made available 36 documents.
Denied the Case File and two documents in their entirety because disclosure of the information would interfere with an ongoing enforcement proceeding or because the information consists of predecisional advice, opinions and recommendations.
Gary Redmore, In response to a request for a copy of a letter Pharmaco Nuclear, Inc.
from an individual alleging various unsafe practices (82-178) about operations at Pharmaco Nuclear, Inc., denied this record, disclosure of which would interfere with an ongoing enforcement proceeding.
L Thomas Devine, In response to an appeal to the Commission for Government Accountability access to documents relating to SECY-81-588_regarding Project the investigative jurisdiction of the Office of (82-A-2-81-470)
Inspector and Auditor (01A) and the Office of Inspection and Enforcement (IE), made available two documents.
Denied four documents in their entirety containing advice, opinions and recommendations.
Denied portions of one document containing advice, opinions and recommendations and to avoid unwarranted invasion of personal privacy.
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ENCLOSURE A 9
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' DIVISION OF CONTRACTS ITEMS OF INTEREST l
Week Ending April 30, 1982 PROPOSALS UNDER EVALUATION RFP No.: RES-82-006
Title:
"NEMAHA RIDGE SEISMOGRAPH NETWORKS"
==
Description:==
Seismological Research Period of Performance: Three years Sponsor: RES Status: The competitive range has been istablished and negotiations are scheduled for May 4, IPd2.
CONTRACTS AWARDED 1.
Contract No.: NRC-10-81 -401 Title :
" PARTITIONS"
==
Description:==
Acquisition of 200 Inter-Royal Partitions or Equal Period of Performance: 50 days after contract award Sponsor: Office of Administration Status: A fixed price contract award to Aspects, Inc., of Darien, CT was awarded on April 30, 1982. Contract awarded in the amount of $33,000.00 2.
Contract No. : NRC-04-82-014 Titl e:
"10TH WATER REACTOR RESEARCH MEETING"
==
Description:==
To coordinate and administer the planning and arrangements for conducting the 10th Water Reactor Safety Research Information.
Specifically, the contractor shall make arrangements for me'eting facilities, assist people with motel reservations, bus trarispor-tation, luncheons, the preparation and distribution of approx-imately 1,000 meeting notices.
Period of Performance: April 30,1982 through November 29, 1982 Sponsor: Office of Nuclear Regulatory Research Status: A fixed price contract awarded to Stanley A. Szawlezicz, of Rockville, Md.
Contract awarded in the amount of $20,000.00.
3.
RFP No. : RS-NRR-82-123
Title:
" REANALYSIS OF EXISTING DATA FROM TELEPHONE SURVEYS CONCERNING THREE MILE ISLAND"
==
Description:==
Using four existing data sets that were collected after the accident at TMI-2, the contractor will infer or extrapolate possible psychological responses that might be exhibited among the population as a result of TMI-l restart.
Period of Performance: 85 days Sponsor: Siting Analysis Branch, Office of Nuclear Reactor Regulation Status: Contract awarded April 15, 1982 to the Pennsylvania State University in the amount of $21,770.00.
In order to meet the stringent time frame for response, the Division of Contracts expedited the negotiation of this action which resulted in an award in 8 days.
ENCLOSURE A
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- Weekly Highlights-4/30/82 -
CONTRACTS CLOSED-0UT NRC-03-78-153 U.S. Army Cold Regions 4/22/82 Research & Engineering Lab.
AT(49-24)-0292 The Aerospace Corporation 4/29/82 NRC-04-74-149 Ohio State University Foundation 4/23/82 NRC-04-78-251 St. Louis University 4/27/82 NRC-02-81-041
'NUSAC Incorporated 4/27/82 NRC-03-78-173 Mr. Richard L. Doan 4/28/82 ADMINISTRATIVE MATTERS 1.
Contract No. NRC-10-82-378 was awarded March 31, 1982 to Beltway Limousine Inc.,
for shuttle bus service. A protest against this award was submitted to the General Accounting Office (GA0) by the legal representatives of International Limousine Service, Inc. The protest is based on a challenge of the small
-business status of the awarded contractor and the size standard utilized in the solicitation for this service. The administrative report from NRC is due to the GA0 by May 26,1982.
2.
The Division of Contracts is currently preparing to defend a claim by NUS against the NRC's decision to deny costs in excess of the contract amount under contract NRC-02-78-044. NUS has appealed to the GSA Board of Contract Appeals.
e e
0 ENCLOSURE A e
DIVISION OF SECURIT'l ITEMS OF INTEREST Week Ending April 30, 1982 DECA Program SEC arranged with the FBI for a DECA (Developmental Effort Counterintelligence Awareness) Program Briefing and will assess its app 1Tcability regarding NRC's activities.
Mr. William Webster, FBI Director, spoke of " Military and Indus-trial Spying - The Business Community Must Be Aware of the Threat" and of this program before the Electronic Industries Association.
The FBI has assigned a counterintelligence specialist in 'each Field Office who is tasked with famil-iarizing Security and other personnel with the latest tactics being used by hositle intelligence officers to obtain sensitive information and equipment.
SEC has arranged a DECA briefing for its personnel the week of May 10, 1982.
Classified Safeguards Program (CSP)
SEC personnel met with Edlow, a transportation company, and discussed proposed changes to their security plan which is being submitted under the provisions of 10 CFR Parts 25 and 95 " Requirements for Access to and Protection of National Security Information and Restricted Data."
Fort St. Vrain submitted a revised Part 25 and 95 security plan for their Denver, C0 and Platteville, C0 facilities.
The plan is currently being evaluated by SEC and Region IV personnel.
During a visit to Rockwell International, it was learned that they never received NRC's letter dated April 1,1982 advising them that they should be in compliance with Parts 25 and 95 by June 1,1982.
Region V received a copy of this letter.
Another copy of this letter was sent to Rockwell International.
Babcock & Wilcox, Lynchburg, VA, General Atomic Company, San Diego, CA, United Nuclear Corporation, Montville, CT, Nuclear Fuel Services, Rockville, MD, United Nuclear Company, Joplin, M0, have been approved under the CSP to handle clas-sified matter.
For particulars, including their classified mailing address, contact SEC's Facilities and Systems Security Branch.
Security Surveys The following facilities were surveyed to determine if their security program was in conformance with NRC Manual Chapter 2101, "NRC Security Program."
ENCLOSURE A 9
. t Date Facility Overall Security Ratino
'4/19 Science Applications, Inc.,
Satisfactory a contractor 4/21 Dr. Harold Lewis, Satisfactory an ACRS Consultant 4/26-27 Region V Satisfactory 10 CFR~Part 10 On April 23, 1982, the EDO approved a proposed rule which revised 10 CFR Part 10,
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" Criteria and Procedures.for Determining Eligibility for Access to Restricted Data or National Security Information" and makes conforming amendments to related Parts 11, 25 and 95.
The proposed rule, which SEC prepared, would revise Part 10 to clarify and update the criteria and procedures used for determining the eligibility of an individual for access to Restricted Data or National Security Information, or an employment clearance.
Revisions of substance will (1) reduce the number of criteria from 22 to 13 by combining several and eliminating 3 that are outdated, (2) provide for taarings to be conducted by a Hearing Examiner rather than-a Personnel Security Board, (3) modify the hearing and administrative review procedures to expedite both the conveying and conduct of a hearing.
It should not result in any increased cost to licensees and if promulgated, will'
'not have a sufficient economic impact on a substantial number of small entities as defined in the Regulatory Flexibility Act of 1980, 5 U.S.C. 605 (b).
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ENCL.0SURE A I
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DIVISION OF ORGANIZATION AND PERSONNEL ITEMS OF INTEREST Week Ending April 30, 1982 Presidential Rank: Nominations The Agency's 1982 Presidential Rank nominations were submitted to the Office of Personnel Management on April 19.
r ENCLOSURE A i
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, OFFlCE OF NUCLEAR REACTOR REGULAT10N 1TEMS OF 1NTEREST Week Ending April 30, 1982 t
Three Mile Island Unit 1 (TMI-1) t 1.
The results'of the TMI-1 SRO and R0 February 1982 NRC reexam have been issued.
ihe results are:
I Applicants Passed Failed
}
f R'O 8
7 1
SR0 5
5 0
The R0 applicant who f, ailed was not from the Operations Department.
This exam was given primarily to reexamine several operators who failed a portion of the October 1981 exam, but additional previously unqualified operators also took the exam.
With these exam results, the licensee.now has a total of 15 qualified R0s.
Although the staff had concluded that the licensee could meet the ASLB minimum requirements by augmenting the normal shift with qualified cperators who do not normally stand watches, these exam results will allow the licensee greater flexibility if and when restart is authorized.
The Appeal Board and hearing parties have been notified of t'hese exam:
results.
2.
Three Mile Island Unit 1 (TMI-1)
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~ On April 28, 1982, the Special Master issued his initial decision on the cheating hearing portion of the TMI-l restart proceeding.. Although
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the Special Master concluded that there was no e'vidence that licensee's upper level management was involved in any way with the operator cheating during the April NRC exam, he concluded that the licensee showed an unacceptable attitude toward the NRC examination.
Additionally, he stated that the "overall integrity of the operations staff was shown to be inadequate."
He also concluded that the licensee's training and testing program was poorly administered, weak in content, ineffective in its method of introduction, and not an adequate response to the Comission's Order of August 9, 1979.
k'ith respect to the staff, the Special Master concluded that the staff l
was lax and its procedures inadequate with respect to p'roctoring add n.
grading the NRC examination in April 1981. Second, he, concluded that the staff's new proctoring procedures should prevent. future cheating if the procedures are carefully followed.. Third, the content of the April e.xam was inadequate and the Co,raission should take steps to upgrade the examination to test the type of knowledge the operator should have. The Special Master considered the NRC staff.'s investigatioh adequate with respect to some of the cheating which ocentred, but inadequate with respect'to other cheating which occurred.
It was recomended that the Commission pursue criminal prosecution of the tw operators who originally cheated.
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ENCLOSURE B
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f.
2.
Three Mile Island Unit 1 (TMI-1) (Continued)
- I The Special Master's decision is now before the Licensing Board.
All parties' have. opportunity. to file. comments with the. Board.by.i. l---
f s
May 12 and, reply comments by May 17, 1982.
(
North Anna Power Station, Unit No. 2 (NA-2)
Quantitative information is now available regarding tube denting...,.-.-
observed from,the inservice inspection of Steam Generators (SG).at NA-2 which was highlighted earlier.
Eddy current testing has not been completed on all three SG's (A,B,C).
From these tests, the following information has been derived.
"A" SG:
All 3330 (less 5d) tubes inspected.
There is zero (0) %
denting.
g.
"B" SG:
All 3330 (less 30) tubes inspected.
There"is-zero(0)%
denting.
'"C" SG:
All 3330 (less 168) tubes inspected.
On'the hot leg side
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-there is, ap-oximately 95% tube denting of less than one (1) mil.
On the cold leg side there is zero (0)% denting.
All three SG's show some indications of low level support-plate-corrosion (not.yet quantified).
The denting occu'rs in the region of the 1st to 5th support. plate.
The 6th and 7th..supp, ort p]ates are, free froin them" denting phenomena.
A preliminary report on the test results is expected to be sent by the licensee to the NRC during week of May (3-7),1982.
OUAD CITIES STATION - SPENT FUEL STORAGE ACTION As a result of a conference call among staff, intervenors, licensee, and ASLB members held on April 23, 1982, the intervenors involvec in the spent fuel modification proceeding requested withdrawal of all contentions and withdrawal from the proceedings.
Following docketing and noticing of an application in April 1981 to increase the spent fuel storage capacity at Quad Cities Station, eleven intervenor contentions were admitted b~f the appointed ASLB. 'Over a period of time DL and OELD worked with the intervenors and licensee to address all the concerns expressed in their contentions.
This sustained effort has resulted in a one-by-one withdraw'al of contentions by the intervenors, which culminated in the intervenors withdrawing their' request for a hearing (scheduled to begin May 11,1982).
This withdrawal was agreed to and supported by all parties.
The Board Chaiman stated that upon receipt of a brief document expressing the sense of the agreement he would issue an Order to terminate the' Hearing.
ENCLOSURE B
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Duane Arnold Eneroy Center (DAEC)
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Representatives of Iowa Electric Light and Power Company met with the staff on April 27, 1982 to. outline and discuss its proposal for satis.fying
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NRC requirements on~ an?" integrated schedule" basis..
To~ date, the licensee estimates that the effort to develop this comprehensive
, schedule plan has involved the expenditure of some 3-4 man-years of effort and $250,000.
In developing its integrated schedule, Iowa Electric
'(and its contractor) utilized a computer based scheduling tool because of
.the complexities of this undertaking and the numerous interrelationships
. among projects which impact schedules.
The licensee has stated that it expects to ake its formal submittal (on.
its own initiative) on this matter.in May 1982...
,.. :., e__
St. Lucie Unit 1 On April 24, 1982 St. Lucie Unit 1 experienced a 15 to 20 gpm primary coolant leak from a pressurizer spray control valve (PCV 1100F) to containment atmosphere. The leak was detected about 2:15 pm when operators noticed Volume Control Tank level decreasing.
The leak was isolated about 3:30 PM by shutting manual valves in the spray line., The plant was operating during the event.
The leak exceeded the technical specification limit of 10 gpm but was isolated within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> allowed prior to ' required plant shutdown.
Continued automatic pressurizer spray control.is available via a redundant full capacity control valve. The cause ofsthe leak will be investi. gated and repaired during an outage scheduled to commence May 5, 1982..
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LA SALLE COUNTY STATION, UNIT NO. 1 As of the morning of April 26, 1982, 342 fuel bundles out of a total of 764 have'been loaded into the reactor.
Presently, the pacing items on the schedule for reaching criticality are correcting the preoperational deficiencies that were deferred until after commencement of fuel load and the internal preoperaticnal vibration test.
The licensee indicates that the fuel load program is still on its projected schedule of 60 days from initiating fuel load to criticality.
ENCLOSURE B
L 1
l Planned Meetings
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1.
Subject:
Meeting to review with the Safe End Task Force progress on the long term program for evaluation of the cracking problem in B&W plant make-up nozzles.
Date/ Time:
May 7, 1982, 1:00 p.m. - 5:00 p.m.
Location:
P-110, Phillips Building, Bethesda, MD l
Attendees:
B&W Owners Group Safe End Task Force (P. Baynard),
NRC and Regional Representatives I-V, NRR contact is S. Miner.
2.
Subject:
Meeting to inform the staff on the current program of the WOG Pressurized Thermal Shock Program.
Date/ Time:
May 10, 1982, 1:00 p.m. - 4:00 p.m.
Location:
P-ll8, Phillips Building, Bethesda, MD Attendees:
NRC-Pressurized Thermal Shock Task Group, Westinghouse Owners Group (Licensee), NRR contact is G. Vissing.
r ENCLOSURE B
t.
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT April 25,1982 - May 1,1982 Plant Status _.
- Core Cooling Modei Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient.
Available Core Cooling Modes:
Decay heat removal (DHR) systems, Mini DHP, (MDHR) system.
RCS Pressure Control Mode: Standby p. essure control (SPC) system.
Backup Pressure Control Modes: MDHR and DHR system.
Major Parameters (as of 0500', April 30,1982) (approximate values)
Average Incore Thermocouples: 102*F Maximum Incore Thermocouple:
129*F RCS Loop Temperatures:
A B
Hot Leg 97*F 100*F Cold Leg (1) 82 F 81 *F (2) 85 F 85*F RCS Pressure: 96 psig Reactor Building: Temperature :
66 F Water level:
Elevation 283.2 ft. (0.5 ft. from floor)
Pressure:
.5 psig Airborne Radionuclide Concentrations :
1.7 E-6 UCi/cc H3 (sample taken 4/27/82) 3.2 E-6 uCi/cc Kr85 (sample taken 4/27/82) 1 Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period April 23, 1982, through April 29, 1982, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources, which originated within Unit 2, contained no detectable radioactivity.
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ENCLOSURE B
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2 Airborne Effluents _
'Airbor'ne releases to the environment as measured by licensee installed monitors at discharge stacks are listed below.
These releases were well within regulatory limits.
. March 1982 Unit 11 EPICOR II
<1.04 x 102
<2.97 x 101 Noble Gases (Ci))
1.39 x 10-7 1.69 x 10-7 Particulates. (C1 l
Tritium (Ci) 3.97 x 10
- 7.71 x.10-1
- This indicates an estimate..of H-3 releases during March since the release value was based on a short sampling period which may not be representative of the entire monthly release.
3.
Environmental Protection Agency (EPA) Environmental Data The EPA Middletown Office has not received the environmental Kr-85 analytical results for the samples which were taken' April 2,1982, through April 16, 1982, from the EPA's Counting Laboratory at Las Vegas., Nevada.
These results will be included in a subsequent report.
j No radiation above normally occurring background levels was r
detected in any of the samples collected from the EPA's a.ir and gamma rate networks during the period from April 21, 1982 -
through April 29, 1982.
On April 30, 1982, the EPA reported the January and February 1982 results of its tests for tritium (H-3) in atmospheric mo,isture.
The first series of results were reported in TMIPO Weekly Status Report dated February 21-27, 1982.
4 NRC Environmental Data Results from NRC monitoring of the environment around the TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-1 31 Cs-137 Sampl e Period (uCi/cc)
(uCi/cc)
H P-317 April 2,1982 - April 28,1982
<6.7 E-14 <6.7 E-14 ENCLOSURE B
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9
. 5
~ Licensee Radi6 active Material and Radwaste Shipments
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4 On Tuesday, April 27,1982,15 Unit 1 flush samples (liquids l
from various locations) were shipped to the Westinghouse f
Electric Company Laboratory, Madison, Pennsylvania.
i-
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On Tuesday, April 27,1982,'10 Unit 2 SDS samples (Submerged Demineralizer System) were shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
l On Tuesday, April 27, 1982, one Unit 2 SDS sample was shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
On Thursday, April, 29, 1982, three Unit 1 liquid samples (spent fuel pool, borated water storage tank and decay heat A) were shipped to the Babcock and Wilcox Research Center, Lynchburg Vi rginia.
On Thursday, April 29, 1982, three Unit i liquid samples (same as above) were shipped to the Westinghouse Electric Company Laboratory, Madison, Pennsylvania.
On Thursday, April 29,1982, three Unit i liquid samples (same as above) were shipped to the Nuclear Water and Waste Technology Laboratory, San Jose, California.
l t
On Thursday, April 29, 1982, 68 drums and 6 metal boxes containing Unit 2 compacted and non-compacted low specific activity (LSA). _,
trash were shipped to U.S. Ecology, Inc., Richland, Washington.
Major Activities 1.
. Submerged Demineralizer System (SDS).
The SDS processed approximately 11,000 gallons of reactor coolant bleed tank water during the week.
The remaining water in the Reactor Building (approximately 40,000 gallons) is now being transferred into the SDS feed tanks using the jet pump installed into the incore instrument trough in the reactor building.
This water will remain in the SDS feed tanks until a sufficient time period is available to process the water without interferring with preparations for Reactor Coolant System Processing.
2.
EPICOR II.
The EPICOR II system commenced processing SDS effluent during the week.
3.
Reactor Coolant System (RCS) Water Processing.
Engineering and construction efforts by the licensee are continuing in preparation for RCS processing which is presently scheduled to commence around -
the middle of May 1982.
NRC/TMIPO review of the procedures needed to commence RCS water processing is expected to be completed during, the week of May 3,1982.
The NRC/TMIPO site office, with support from the Chemical Engineering Branch, NRR, is reviewing the licensee's request to revise the Recovery Operations Plan to incorporate changes to accomodate RCS processing.
ENCLOSURE B
O 4
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- Reacto_r Building Entries, The jet pump installation to remove the remaining six inches of water from the reactor building (RB) basement was completed during the RB entry on Wednesday, April 28, 1982.
The pump was energized from outside the RB on Thursday evening and began pumping the estimated 40,000 gallons (30,000 gallons of original sump water plus 10,000 gallons of water from the, decontamination experiment) of water from the RB basement to.the SDS feed tanks at approximately 10 GPM.
On Sunday, May 2,1982, the pumping operation was secured when filters on the inlet line,o the SDS feed tanks reached 40 PSI of differential pressure (plugged filter indication) and pump flow decreased to 2 GPM.
Approximately 36,000 gallons of water were pumped from the sump before the high differential pressure was reached.
Additional work inside the RB cn Wednesday included the testing of six RB smoke detectors.
The smoke detectors are part of the RB fire protection system and are designed to activate an alarm in the control room and automatically to secure portions of the RB ventilation system.
None of the six detectors performed their designed functions during the test.
Technicians are trouble shooting the fire protection circuits from outside the RB to determine the cause of the malfunction.
The next RB entry is scheduled for Wednesday, May 5,1982 A
health physics technician will perform an area and airborne radiation survey of the RB before any other work is undertaken to determine how the removal of the sump water affected the RB radiation levels.
7 5.
Groundwater Monitoring Program.
As part of the groundwater mo'nitorin'g program, weekly water samples are taken from test borings 1, 2, 3, ~
10,16, and 17.
The weekly samples are analyzed by the onsite 1aboratery.
Once per month the water samples are sent to two independent laboratories offsite.
The latest onsite analysis; results are available from samples taken on April 26, 1982. Offsite samples results for all wells are available for samples taken on March 2,1982.
Based on the available sample results, tritium concentrations in the groundwater have remained in the same range as those reported in previous Weekly Status Reports.
Except for tritium, there have been no other radionuclides detected in the latest water samples.
9 ENCLOSURE B 4
i 4 i
Past Meeting On Tuesday, April 27, 1982, Lake Barrett met with a group of Middletown j
i mothers to discuss progress on the cleanup at TM1 Unit 2. various funding plans for Unit 2 cleanup, Unit 1 steam generator repairs and sources of GPU funding for steam generator repairs.
They expressed their opinion that Unit 1 should not be restarted until Unit 2 was cleaned up.
Future Meeting 1.
On Tuesday, May 4,1982, Harold Denton, Bernard Snyder.and Lake Barrett will testify in Washington, DC, before Senator Alan K.
Simpsons' Senate Subcommittee on Nuclear Regulation, Evnironment
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and Public Works Committee.
2 On May 11,1982, Lake Barret't will meet a group of Middletown mothers to discuss issues and concerns related to the cleanup program at TMI Unit 2 and the status of Unit 1 3.
Cm May 11,1982, Lake Barrett will participate in a panel discussion on TM1 issues to be aired on cable television in the Central Pennsylvania Other panelists include, Susan Shanaman, Chairman of State area.
Public Utility Commission; General. DeWitt Smith, Director of Pennsylvania Emergency Management Agency; Representative James Wright, Chairman House Select Committee on TM1; respresentatives from Union of Concerned Scientists; Bipartisan Committee to Vote No; GPUN, and TMI Friends and Family.
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e ENCLOSURE B
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0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending April 30, 1982 Broken IAEA Seals During an IAEA inspection at the Rancho Seco reactor on April 26, the IAEA found that all four of their safeguards seals for the pressure vessel were broken.
One of these had previously been broken and reported to the IAEA.
Although the cause has not been established, the breakage may be associated with the extensive maintenance that has taken place in the eneral area during the past month. There is no indication of missing material.
The IAEA applied four new seals at less accessible locations. The broken seals have been reported to the IAEA in Vienna, Austria, by the State Department.
IAEA/NEA Symposium on Management of Wastes From Uranium Mining and Milling The International Atomic Energy Agency and the OECD Nuclear Energy Agency are sponsoring a joint symposium on the management of uranium mining and
' milling waste in Albuquerque, New Mexico, May 10 - May 14, 1982.
Staff members of the Division of Waste Management will present a paper on the Uranium Mill Tailings Licensing Requirements in the United States and will participate on a panel on Objectives, Problems and Solutions of Waste
-Management in the Milling Industry.
ENCLOSURE C
L Maetings - Division of Waste Management I
White' Mesa Uranium Project (SUA-1358) l 1.
Subject:
(1) Cont,emplated proposal by EFN for a new tailings
. disposal area, and
[
(2) Surety arrangme.ents for reclamation and decennis-sioning of the White Mesa mill.
Date/ Time:
May 5, 1982 - 9:30 a.m.
{
location:
Wills'te' Building, 4th floor conference room '
Attend.ees:
D. Gillen (WM) and representatives of EFN l
2.
Subject:
Rerhedial action of the Vitro' uranium mill tailings site and' vicinity properties in Saltlake City, Utah.
~
i Date/ Time:
May 3, 1982 - 1:00 p.m.
Location:
Willste Building, 4th floor conference room.
Attendees:
Dan Martin, Kathleen Hamill, (WM)
Rodney Dahl, General Manager, Central Valley Water Reclamation Facility s
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Meetings v. Division. of Safeouards
~
1,
Subject:
Review of decommissionion of plutonium fuel laboratory
~ ~ ~. Date:
May 3-4, 1982 GE-Vallecitos, California '
Location:
Attendees:
C. H. Smith, NRC; G. E. Cunningham (GE) 2,
Subject:
Review of MC&A licensing program.
Date:
May 5-7, 1982 Location:
GA-LaJolla, California Attendees:
D. R. Joy, C. N. Smith (NRC)
W. Mowry, K. Duffy (GA) 3
Subject:
Presentation at the 4th International Physical Protection Training Course at Sandia Labs.
Location:
Albuquerque,--New Mexico Date:.
May 5-7,1982 Attendees:
R. Erickson, E. Quinn (NRC)
' ~
4,
Subject:
Participation in.the FBI "In-Servi-ce" Training Exercise regarding nuclear-related matters.
~
Location:
FBI Acade_my -- Quantico, VA Date:
Aoril 30, 1982 Attendees:
E.Quinn,P.MacMurdy(NRC)
ENCLOSURE C P
s
j 2
Meetings - Division of Fuel Cycle and Material Safety 1.
Subject:
Spent Fuel Storage Date/ Time:
May 4, 10:00am Location:
Willste Building, 5th floor conference Room Attendees:
L. C. Rouse (FC), J. P. Roberts (FC),
N. Davison (FC), Rep from SG, 4-6 VEPC0 staff members, NRR Project Manager for Surry 2.
Subjdct:
fieeting to discuss the possibility of consolidating all D00 licenses into a single broad license.
Date/ Time:
May 4, 1:30pm Location:
Pentagon Attendees:
R. E. Cunningham (FC), V. L. Miller (FC),
Members of the Department of Defense Y
9 S*H 4
D P
ENCLOSURE C d
0
OFFICE OF INSPECTION AND ENFORCEMENT
~
ITEMS OF INTEREST Week Ending April 30, 1982 1.
There were no Significant Enforcement Actions taken during the.past week.
2.
The following Preliminary Notifications were dispatched during the past week:
a.
PNO-I-81-128B, W. R. Grace and Company (Wayne, New Jersey) - Radioactive Materials Discovered Offsite, Update.
b.
PN0-I-82-33, Vennont Yankee Nuclear Power Corporation (Vermont Yankee) -
Reactor Scram And HPCI/RCIC Actuation.
PN0-I-82-34, Long Island Lighting Company (Shoreham) - Impersonation of c.
NRC Inspector.
d.
PNS-I-82-02, Public Service Electric and Gas Company (Salem), General Public Utilities (Three Mile Island Units 1 and 2), Jersey Central Power and Light Company (0yster Creek) - Bomb Threat.
e.
PPS-I-82-03, Public Service Electric and Gas Company (Salem) - Suspected Saoatage.
f.
PNO-II-82-46, Virginia Commonwealth University (Medical Center, Richmond, Virginia) - Lost I-125 Radiotherapy Seeds.
g.
PNO-II-82-47, Duke Power Company (0conee Unit 3) - Shutdown Greater Than Two Days.
h.
PN0-II-82-48, Georgia Power Company (Hatch Unit 2) - Water Spill In Turbine Building.
1.
PNO-II-82-49, Carolina Power and Light Company (Robinson Unit 2) - Broken Reactor Coolant Pump Bolts.
- j. PNO-II-82-50, Georgia Power Company (Hatch Unit 1) - Unplanned Shutdown Due to Conductivity.
k.
PN0-II-82-51, Duke Power Company (0conee Units 1, 2, and 3) - Degraded Tendons In The Shield Wall.
1.
PN0-III-82-44, Commonwealth Edison Company (LaSalle) - Receipt of Allegations And Request For Suspension Of Operating License.
m.
PN0-IV-82-16, Public Service Company of Colorado (Fort St. Vrain) -
Unplanned Release Of Radioactive Gases.
ENCLOSURE D
< PNO-V-82-14F, Sacramento Municipal Utility District (Rancho Seco) - High n.
Pressure Injection Thermal Sleeve Degradation.
PNO-V-82-20, Portland General Electric Company (Trojan) - Reactor Fuel o.
Degradation.
PN0-V-82-21, Southern California Edison Company (San Onofre) - Declaration p.
Of Unusual Event Due To RCS Leakage.
PNS-V-82-01, Sacramento Municipal Utility District (Rancho Seco) - Bomb q.
Threat.
3.
Other Items a.
Division of Reactor Programs 1.
The Division Director and staff met with representatives of INP0/ANI on April 29, 1982 in Atlanta, Georgia to discuss owner's certification.
2.
Staff members from the Division of Reactor Programs, Program Support Branch, and the NRC Training Center met with representatives of TVA on April 26, 1982 to discuss the NRC Reactor Training Center building which is proposed to be constructed near the existing TVA Training Center in Chattanooga, Tennessee.
b.
Division of Fuel Facilities, Materials and Safeguards A training session on IAEA safeguards (US/IAEA' Safeguards Agreement and'IAEA safeguards inspections) was held in Region II this week. The training was sponsored by IE to inform the safeguards staff in the NRC Regional Offices of the impact of IAEA safeguards on the NRC program.
c.
Division of Emergency Preparedness An introductory meeting has been scheduled with GA0 and staff of the Division of Emergency Preparedness on May 4,1982, to discuss the planned GA0 survey of emergency preparedness activities.
d.
Division of Engineering and Quality Assurance Division staff will hold a meeting on May i,1982 with representatives of ANSI,EPRI and ASME to discuss qualification and certification of NDT personnel.
ENCLOSURE D
e.
3-e.
Enforcement Staff The following payments of civil penalties were received during the past week:
1.
Carolina Power and Light Company (Robinson) - $40,000, Enforcement Notification 81-44A dated February 23, 1982.
2.
Georgia Power Company (Hatch) - $40,000, Enforcement Notification 82-06 dated March 25, 1982.
3.
Tennessee Valley Authority (Sequoyah) - $50,000, Enforcement Notification 82-05 dated March 25, 1982.
4.
Maine Yankee Atomic Power Company (Maine Yankee) - $30,000, Enforcement Notification 81-40A dated March 29, 1982.
e 4
ENCLOSURE D
~-+or e
6 o
0FFICE OF NUCLEAR REGULATORY RESEARCH ITEMS OF INTEREST Week Ending April 30, 1982 BWR FIST Test vessel delivery has been delayed due to difficulty in honing the interior of the vessel to the final dimensions.
Arrangements for another machine shop have been made. A revised construction schedule will be issued after this problem is resolved.
Semiscale The last test in the feedline break series. a 100 percent break, is anticipated the week of May 3, 1982. A short steam line break series will follow.
Several utilities and vendors have tentatively indicated a willingness to share results of their investigations in exchange for the interim version of RELAP5 (ZELAP) and participation in ZELAP meetings. They are preparing letters to us outlining the information to be shared.
LOFT The Quick Look Report for the recent ATWS test, L9-3 was issued on schedule, April 23,1982.
INEL is still studying two problems: the PORV flow rate was higher than predicted and the clad surface-imbedded thermocouples all failed.
The second problem has some bearing on the instrumentation of the F-2 fuel bundle to be used in the. final test, L2-6, for the same thermocouples are planned for use in this bundle, and although they are to be mounted differently, their operation is significant to the success of the test.
Clarification of both problems is expected within one week.
The boron-dilution twin-tests were successfully run last week and the Quick Look Report will be issued next week.
In preparation for the next test - a large break LOCA, L2 work is proceeding on schedule to complete the waste-gas system, the decontamination systems and the isotope-detection system, and to rearrange the piping and relief valving as required for a large break test.
L2-5 is scheduled for June 16,1982.
A LOFT Review Group meeting will take piace in Salt Lake City on May 11 and 12, 1982.
Anyone wishing to attend who has not received the necessary.
details should contact Don McPherson on x74260.
ENCLOSURE E L
e 9
. ~
Data Bank Test data from Halden, Norway were added to the data bank this past week
~
and pertain to two blowdown and reflood series of tests.
The IFA511.2 test series used nuclear rods.
Runs entered into the data bank from IFA511-2 were 4693, 4694, 4695, 4696, 4697, 4698, 4711, 4712 and 4714.
The second test series, IFA511-3, used Semiscale electrically heated rods.
Thirteen runs were entered from this test series: 6023, 6024, 6025, 6026, 6027, 6028, 6029, 6030, 6031, 6032, 6033, 6034 and 5035.
Finally, data from Semiscale natural circulation test NC-10, were also added to the data bank.
Midyear Review of Independent Code Assessment Programs Midyear review of Independent Code Assessments Programs took place on April 23,1982.
All contractors attended technical sessions in order to be familiar with each other's work and to see how their contributions fit to the overall assessment program. Some of the code developers also attended the meeting to obtain the feedback necessary for improvements of their codes. All attendees found that this type of meeting was very useful and it was decided to hold such meetings three times a year where all independent code assessors and developers meet each other and discuss their findings, interpretation of results and problems.
Midyear Review of Containment Codes for H Transport 2
a.
PNL presented the status and the schedule of COBRA / Containment assessment.
mixing tests due to Delay was proposed in calculating EPRI's H9 consideration for other priority cases.
At NRC insistence, PNL agreed to perform the calculation with minimal delay.
b.
LANL, T-3 Group presented post-test predictions of EPRI's H2 "I*I"9 test, using the HMS code.
c.
After presenting their approach for pretest calculations of EPRI's H mixing tests, Sandia reiterated their desire to work on a' number of 7
edifications on the RALOC code. Because of the constraints imposed by GRS, Germany, who developed the code, against public release of the code, we consider the code to have only a limited value to our licensing.
Therefore, Sandia was advised to perform only those modeling modifications needed for immediate application of the code.
9 l
ENCLOSURE E i
l
Midyear Review of COBRA / TRAC PNL presented the latest COBRA / TRAC best-estimate simulation of a UHI-equipped i
PWR with large-break LOCA. The peak clad temperature was calculated to be j
11500F, which occurred at 8 seconds after the break initiation; the entire l
core was quenched at 14 seconds.
Improved gap conductance and top quench j
i front models were used in this calculation.
BNL Midyear Review A midyear review was held of BNL's RAMONA-3B (A-3014) and Plant Analyzer (A-3227) programs.
The main results concerning the technical aspects of the two programs were:
1.
A partial ATWS demonstration calculation has been completed. The results are presented in a draf t report transmitted to NRC.
2.
A draft of RAMONA-3B Manual Report has been transmitted to NRC for comments and revies.
3.
The Plant Analyzer program is on schedule.
Reference thermo-hydraulic calculations for demonstrating computing speeds and accuracy are expected by May 31,1984 BNL estimates that calculations performed on the AD-10 r
parallel processo.' will be approximately 10 to 20 times faster than real time.
Advanced Code Review Group Meeting The Advanced Code Review Group held a two-day meeting on the subject of pressurized thermal shock. Approximately 60 persons representing national laboratories, EPRI, industry, vendors and utilities were in attendance.
The objectives of the meeting were to:
1.
Review, comment and make recommendations on forthcoming thermo-hydraulic calculations relevant to the pressurized thermal shock problem.
2.
Review, comment and make recommendations on planned thermal-fluid mixing and heat transfer experiments to be carried out.at CREARE under joint sponsorship of NRC and EPRI.
The main conclusions were:
1.
The just completed experiments conducted in an adiabatic 1/5 scale facility at CREARE (under the sponsorship of ErRI) indicate that very good mixing occurs in the cold leg except when the ratio of loop to HPI flow approaches zero in W and CE plants. Consequently, with exception of this latter case,1-D loop calculations performed by codes such as ENCLOSURE E
. i i
RELAP-5 or TRAC-Pfl should predict realistically the liquid temperature entering the vessel.
For the case when the ratio loop to HPI flow approaches zero, empirical mixing coefficients could be derived using CREARE's data.
2.
Scaling thenno-hydraulic phenomena of interest to the PTS problem is not a big issue since one deals with single phase flows.
Consequently, the forthcoming experiments to be conducted in an adiabatic 1/2 facility at CREARE (under joint sponsorship of NRC and EPRI) should provide data on heat transfer coefficients and additional data on mixing, which could be extrapolated to full reactor conditions.
~
3.
The SOLA-30 code which models turbulent mixing, has the capability to predict the 3-D mixing phenomena in the downcomer.
However, it should be first assessed against experimental data for buoyancy dominated flows.
4 Publications to be Issued in the Near Future
Title:
Form of Nuclear Energy Liability Policy for Facilities
==
Description:==
Section 140.91 of 10 CFR 140 presently contains insurance policies provided as proof of financial protection under the Price-Anderson-Act. The Commission wants these policies published as a regulatory guide-rather than as a regulation.
Contact:
I. Dinitz 492-9884 Publications Issued During the Week of April 26-30, 1982 Reg. Guide 1.68.3 - Preoperational Testing of Instrument and Control Air Systems.
Draf t Regulatory Guide and Value/ Impact Statement: Qualifications for the Radiation Safety Officer in a Large-Scale Non-Fuel-Cycle Radionuclide Program, Task OP 722-4,
Contact:
J. M. Bell (443-5970).
Comments requested by June 30, 1982.
Regulatory Guide 1.80, "Preoperational Testing of Instrument Air Systems" is withdrawn.
9 ENCLOSURE E
OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING APRIL 30, 1982 San Onofre, Units 2 & 3 On April 26, 1982, the Appeal Board issued a Decision (ALAB-673) in this OL proceeding denying the Intervenor's application for a stay of the Licensing Board's January 11, 1982 Partial Initial Decision which authorized issuance of an operating license for fuel loading and operation up to 5%
of rated power.
Three Mile Island Nuclear Station, Unit 1 On April 28, 1982, the Special Master issued his Report in this Restart Proceeding on the question of operator cheating and related issues. The Report contains explicit findings of fact on the extent of cheating on NRC and Licensee examinations, Licensee's training and testing program, Licensee's system for certifying candidates, the NRC's licensing examination, and the NRC Staff's response to the cheating.
In addition, in a Memorandum and Order dated April 26, 1982, the Licensing Board in this Restart Proceeding denied the motion of two intervenors to reopen the record for consideration of various matters discussed in the Martin Report - a Report prepared by members of OIE following the THI-2 accident.
In its order the Licensing Board stated that it found "little, if any, new a.nd material facts or analyses to justify a reopening of the record."
ENCLOSURE F 9
0FFICE OF INTERNATIONAL PROGRAMS ITEMS OF INTEREST Week Ending April 30, 1982 Recent Travel by NRC Personnel Deputy Executive Director ' lictor Stello and IP Deputy Director Joseph D. Lafleur, Jr. presented papers at the seminar on U.S.
nuclear -technology April 19-21 at Lake Bled, Yugoslavia. The title of Mr. Stello's paper was " Reactor Licensing in the After-math of Three Mile Island." Dr. Lafleur presented a paper on the NRC Nuclear Safety Cooperation Program. Highlights of the seminar and other Stello and Lafleur visits in Yugoslavia are reported in State cable Belgrade 3303.
Following the Yugoslav seminar, Dr. Lafleur attended the U.S.-
Egypt Nuclear Cooperation Steering Committee Meeting April 25-27 in Cairo, Egypt. The ourpose of the meeting was to explore areas of expanded nuclear cooperation; this. meeting is reported in Cairo 10462. -
~
Canadian Visit to the U.S.
David Sinden, E. A. MacKay and R. M. Duncan of the Atomic Energy Control Board in Canada and H. A. Rose from. Atomic Energy of Canada, Ltd., accompanied by Marjorie Mahy of IP, Visited Region II, GE's Wilmington fuel fabrication plant, and BNL's high-flux beam reactor to discuss and observe the functioning of the U.S. nuclear material accountability system and its interface with IAEA safeguards requirements. The visit occurred April 26-29.
Foreign Visits to NRC On Wednesday,'Mr. George'Yadigaroglu and~Dr. Paul Protonotarios of the Nuclear Regulatory Service of the Greek Atomic Energy Commission met with A. B. Ibrahim and S. Brocoum of the Geosciences Branch of the NRR Division of Engineering and with J. Richardson of the Mechanical / Structural Engineering Branch of the RES Division of Engineering Technology to discuss future licensing trends in the areas of seismology and geology and an overview of the Seismic Safety Margins Research Project (SSMRP). Mr. Le'onella Serva, on assignment to the NRR'Geosciences Branch from the Italian regulatory authority, also attended the meeting.
On Thursday, Mr. Masaichi Kamimura, General Manager of the Overseas ~
Electrical Industry Survey Institute, met with E. F. Fox of the NRC Reactor Training Center, P. McKee and N. Hobbes of the Office of Inspection and Enforcement, and W. S. LaVine of IP to discuss training programs for resident inspector personnel.
ENCLOSURE G
i 2
On Thursday, Dr. Yair Tene, a consultant for the Israeli Electric Corporation, met with 0. Rothberg of the Structural Engineer.ing Branch and with A. Lee of the Equipment Qualification Branch of the NRR Division of Engineering to discuss the seismic qualifica-tion of structures and mechanical equipment.
On Friday, Mr. Keith D. Reeve, Leader of the Synroc Project of the Australian Atomic Energy Commission (AAEC) met with R. E. Browning, Deputy Director of the NMSS Division of Waste Management; M. J. Bell of the NMSS High-Level Waste Licensing Management Branch; R. B. Alexander, Chief of the RES Occupational Protection Branch; and K. S. Kim and M. McNeil of the RES Waste Management Bra'nch, to discuss the present status of the AAEC Synroc R&D Project and U.S.
licensing requirements for high-level waste forms, packages, and repositories.
t P
e e
ENCLOSURE G 9
h
o Foreign Reports f
I Deleted from PDR copy
- Indicates the reports are in English ENCLOSURE G
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0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING APRIL 30, 1982 Low Level Waste Compacts The States of Florida and Mississippi have enacted the Southeast Inter-state Low Level Radioactive Waste Compact into law and have entered into the Compact as parties. To date, these are the only eligible States to this Compact with enacted legislation.
Other eligible States are Alabama, Georgia, North Carolina, South Carolina and Tennessee.
NGA Study The National Governors' Association Task Force for the Study of the Agreement State Program will meet May 5, 1982 to review the study's progress and current study plans. Joel Lubenau will attend.
Utah Agreement State Status Meeting Staff from HQ and Region IV met with Darrell Warren, Director, Bureau of Radiation Control in the State of Utah to. discuss Agreement State status. The State is in the process of revising their regulations and preparing a program description. They have a tentative target date for an agreement of January 1984...
i
?
Review - California Radiation Control Program Review of the California radiation control program is scheduled for May 3-14.
Part 20 Meeting With States On April 26 State representatives appointed by the Conference of Radiation Control Program Directors met with the Part 20 working group to discuss State comments on a draft of the Part 20 revision. Comment letters had been received from 10 States.
ENCLOSURE H
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P OFFICE FOR ANALYSIS AND EVALUATION 0F OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING APRIL 30, 1982 Memorandum of Agreement (M0A) with the Nuclear Safety Analysis Center (NSAC)
A M0A has been signed by the NRC and NSAC for a cooperative relationship ir.
the exchange and feedback of operational experience, information and data relatedEto the safety of nuclear power plants. The MOA was effective April 1, and supersedes the previous.INP0/NSAC/NRC Agreement dated May 26, 1981.
The revised NSAC/NRC Agreement parallels the recently signed MOA with INP0 with regard to operational data.
Publication of Proposed Rule 50.73 By memorandum dated April 21, 1982, the Commission provided comments on the proposed addition to 10 CFR 50.73 formally establishing the Licensee Event Report (LER) system. The Commission comments have been incorporated into the Statement of Consideration for the Rule and the Rule has been forwarded for publication in the Federal Register. Publication is expected in early May.
O e
e ENCLOSURE J t
REGION V ITEMS OF INTEREST WEEK ENDING APRIL 30, 1982
~
~
Washington Public Power Supply System WNP DN 50-460 Construction Suspension: The Executive Board of the Washington Public Power Supply System, upon recommendation of the Federal Bonniville Power Administration, voted unanimously to suspend construction of WNP-1 for as long as five years.
Construction of the plant is 61% complete at this time.
Site management is meeting today to determine their immediate plan of action.
The suspension will affect 6,000 construction workers.
Southern California Edison Company SONGS DN 50-361 At 10:45 p.m. (PDT) on April 28, 1982, the licensee declared an unusual event at SONGS-2. The unit was in Mode 4 conducting precritical post core hot functional testing with a clean core. The unusual event was declared because both the identified and unidentified Reactor Coolent System (RCS) leak rates exceeded Technical Specification requirements.
Unidentified leakage was initially reported as about 12.5 gpm. There was no difficulty encountered in maintaining RCS inventory.
Region V opened the Incident Response. Center at 11:30 p.m. to evaluate the event circumstar
', and the Resident Inspector arrived on site at 12:30 a.m.
The licensee evaluated the situation and-identified leakage occurring past several check valves in the Safety Injection header and other isolation valves into various tanks.
Region V Incident Response Center was closed at 2:30 a.m. on April 29, 1982. The licensee is presently in the process of cooling down and depressurizing to partially drain the RCS and repair the leaking valves and other sources of RCS leakage. The impact of this additional delay on initial criticality and startup testing has not been determined.
(PNissuedon 4/29/82)
Sacramento Municipal Utility District Rancho Seco - DN 50-312 AUXILIARY FEEDRING UPDATE:
B&W, along with the owners of the three operating plants involved in this problem (0conee III, Davis Besse, and Rancho Seco), have decided that a permanent "fix" must be found.
Rancho Seco will be the first plant to receive and install the "fix."
All three plants will use the same design. An external ring header wi.11 be installed with either fou,r or six nozzles penetrating the OTSG shells. The present internal hefder must remain in place because.of the steam flow path in these OTSGs.
If the header were to be removed, excessive tube vibration would probably occur.
Therefore, as part of the "fix,"
the present header will have to be stabilized.
The design for these fixes, the externa' header, the number of holes, and the stabilization of the internal header' i
are not decided on yet.
The licensees hope to make a final decision in concert
)
on these designs by April'30,11982.
If no consensus is made by then, they will continue discussions into the following week.
There are two sets of external ENCLOSURE L
e
\\
Rancho Seco (Cont'd)
. headers being fabricated by B&W at present, with the hope on the licensees' part that these headers will suffice for the permanent "fix."
Since Rancho Seco will be the lead plant in this work, the other licensees will be closely following the entire project.
Radiation levels with the primary side filled, range from t
150 mr/hr just outside the manway to 5 R/hr on contact with the tubes.
Primary side eddy current work will probably be performed after the repairs such that the lane tubes, the perimeter tubes, and dowel pin location tubes may be inspected.
e o
G ENCLOSURE L
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ITEMS ' ADD'RESSED BY THE COMMISSION - WEEK ENDING APRIL 30, 1982 1
A.
SECY-82-110 - OBJECTIVE PERFORMANCE INDICATORS FOR EVALUATION OF AGREEMENT STATE RADIATION CONTROL PROGRAMS, Memo SECY to Dircks, 4/27/82 This is to advise you that the Commission (wi all Ccmmissioners,
agreeing) has approved your recommendation that the Agreement States and the Conference of Radiation Control Program t
Directors be given additional time to submit comments on approaches to objective performance indicators for Evaluation of Agreement State programs.
The Office of State Programs was informed of this action on April 27, 1982.
B.
SECY-82-136 - ABNORMAL OCCURRENCE RECOMMENDATION - BLOCKAGE OF COOLANT FLOW TO SAFETY-RELATED SYSTEMS AND COMPONENTS, Memo SECY to Dircks, 4/27/82 This is to advise you that the Commission (with all Commissioners agreeing) has approved the proposed abnormal occurrence recommendation and its Federal Register Notice.
You should forward the FRN to the Office of the Secretary for publication by May 11, 1982.
The Office for Evaluation and Analysis of Operational Data was informed of this decision on April 27, 1982.
C.
SECY-82-144 - PROPOSED RETRANSFER FOR REPROCESSING (SP IN TO THE U.K.)
Memo SECY to Dircks, 4/27/82
~
This is to advise you that the Commission (with all Commissioners agreeing) has approved the attached response to the Department.
of Energy (DOE).
The Office of International Programs was informed of the action on April 27, 1982.
Attachment:
Not Included ENCLOSURE O 6