ML19318B037
| ML19318B037 | |
| Person / Time | |
|---|---|
| Issue date: | 06/11/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-800611, NUDOCS 8006240601 | |
| Download: ML19318B037 (32) | |
Text
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
2 1ll 5
June 11, 1980 For:
The Commissioners From:
T. A.Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 6,1980 A sumary 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
Standards Development C
Nuclear Material Safety and Safeguards D
Inspection and Enforcement E
Nuclear Regulatory Research F
Executive Legal Director G
International Programs H
State Programs I
Management and Program Analysis J
Controller K
Analysi's and Evaluation of Operational Data L*
Items Approved by the Comission M **
Calendar of Speaking Engagements N
fs u w
, T. A. Rehm, Assistant for Operations Office of Executive Director for Operations
- No input this week.
- Deleted from Commissioners and PDR copy.
Contact:
THIS DOCUMENT CONTAINS T. A. Rehn POOR QUAUTY PAGES 27781~
8006240 60].'
,=
Summary of Weekly Information Report Week Ending June 6, 1930 North Anna Unit 1 The NA-1 Loose Parts Monitoring System detected a loose part object located in Steam Generator "B," approximately 1-1/2 inches long and 3/8 inches in diameter and weighing about 4 ounces or less. The licensee will retrieve the object and attempt to determine its origin.
In addition, VEPC0 has discovered that the seismic piping analyses performed by Stone & Webster for piping systems which run between buildings may not be con-se rva tive. VEPC0 halted plant startup, which was otherwise scheduled for June 1, and agreed to keep the plant shut down until the matter is resolved to NRR's satis faction.
Calvert Cliffs Unit No.1 In the afternoon of June 1 a small amount of radiation leakage occurred, resulting from a control valve packing leak in the volume control system letdown line. The auxiliary building was evacuated. The CVCS system was isolated manually, and the leak was identified. The system was returned to operation by placing a backup valve into service.
The total release (about 10 minutes in duration) was less than 65 of the Technical Specification limit.
Hatch Unit No. 2 On June 2 the staff issued, orally, a temporary, one-time Technical Specification change for Unit 2.
The change authorized startup of the unit with an inoperable High Pressure Coolant Injection System for the purpose of conducting a test of the turbine-generator.
Surry Unit 1 On June 3 a failure of a capacitor in the transformer caused a small fire in the emergency switch gear room. The fire brigade responded in two minutes and extinguished the fire in one minute. The failure of this transformer resulted in the automatic shutdown of the plant.
Haddam Neck Plant While the plant was shutdown for refueling, a small, unplanned release of radioactive gas occurred. While venting the Volume Control Tank to the waste gas system, the relief valve on the Waste Gas Surge Tank lifted for 2 to 5 minutes, resulting in an uncontrolled release which was 26% greater than permitted by station technical specifications.
FY 1982 Budget Formulation The major program offices have met the requirement of submitting their budgets to the Office of.the Controller by June 2, with the exception of NRR.
OFFICE OF ADMINISTRATION Week Ending June 6, 1980 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS In1tial Appeal of Request Initial Decision Received 374 24 Granted 263 6
Denied 59 10 Pending 52 8
ACTIONS THIS WEEK Received William Hegarty, Requests information regarding evaluation of the Self-Powered Lighting facilities of United States Radium Corporation since Limited January, 1978.
(80-285)
(An individual requesting Requests information concerning his Reactor Operator information about himself)
License exam results.
(80-286)
(An individual requesting Requests information concerning his Reactor Operator information about himself)
License exam results.
(80-287)
Donna Warnock Requests records pertaining to the Coalition for a (80-288)
Non-Nuclear World.
John F. Doherty Requests a copy of 18 listed documents.
(80-289)
(NRC employee)-
Requests information concerning the selection process (80-290) used in filling openings for the NRC Senior Executive Service Candidate Development Program.
Ellyn R. Weiss, Requests a copy of all testimony, letters, memoranda and Sheldon, Harmon responses to questions by Dr. Joseph Hendrie to the
& Weiss, on behalf U.S. Senate, House of Representatives and Congressional of UCS Comittees during his tenure as Chairman and Commissioner (80-291)
CONTACT:
J. M. Felton 492-7211 ENCLOSURE A
2 Received, Cont'd Dean Hansell, Requests all documents pertaining to the decision of the State of Illinois NRC to issue a Supplement to the Final Environmental (80-292)
Statement for the Pe';ble Springs Nuclear Plant.
James T. Wiedenhorn, Requests a copy of 7 categories of NRC Distribution Nucleonics Week Lists.
(80-293)
Clarence Johnson, Requests a copy of SECY-78-137.
TexPIRG (80-294)
Kay Treakle, Requests information relating to the French nuclear Greenpeace weapons testing at Moruroa Atoll, French Polynesia (80-295) since 1966.
R. Warren Kearney Requests copies of all indemnity agreements relating (80-296) to Three Mile Island Units 1 and 2 and copies of the insurance policies pursuant to the Price-Anderson Act on Three Mile Island Units 1 and 2.
Rodney D. Ice, Requests information on medical radiation exposure data University of Oklahoma that led the NRC to adopt "as low as reasonably (80-297) achievable" as 0.1 the maximum permissable dose.
Katherine A. Meyer, Requests, on behalf of the Virginia Sunshine Alliance, Attorney-At-Law five categories of documents pertaining to the (80-298) transportation of spent nuclear fuel from Portsmouth, Virginia to the Savannah River Plant in Aiken, South Carolina.
(NRCemployee)
Requests a copy of the CERT for Vacancy Announcement (80-299) 80-1483.
Granted
' David F. Montoya, In response to a request for eight categories of National Image Inc.
personnel inf0rmation regarding Hispanic Employment, (80-177) made available 10 documents.
William H. Button, In response to a request for records pertaining to Radiological Control Hittman Nuclear and Development Corporation, RAD Consultants Services, Inc., and Radiation Management Corporation,
_(80-244) made available t'is information.
Evelyn P. Davis, In response to a request for a list of the Region IV General Services Life employees, including their grades and departments and/or Insurance Company offices, made available this list.
(80-249)
ENCLOSURE A
3 Granted, Cont'd-(An individual requesting In response to a request for documents pertaining to information about himself) himself in the NRC, informed the requester the NRC has (80-272) no-information pertaining to him in its personnel, security, or radiation exposure records.
Tnomas A. Miller In response to a request for documents pertaining to (80-276)-
the NRC inspection of Atomics International and the allegations of Stanley Schecter, made available three documents.
Eugene R. Fidell, In response to a request for all correspondence from Attorney-At-Law Mr. Robert Martin to Mr. Victor Stello, or vice versa (80-281) since April 1,1980, Mr. Stello's telephone logs since April 1, 1980 and all travel claims submitted by Mr.
Martin since April 1,1980, informed the requester that no documents exists pertaining to his request.
(Zndividuals' requesting Made available information concerning their Reactor informationaboutthemselves)
Operator License exam results.
(80-286 & 80-287)
Clarence Johnson, In response to a request for a copy of SECY-78-137, TexPIRG informed the requester he may obtain a copy of this (80-294) document at the PDR.
Denied Debra D. Mcdonald, In response to a request for copies of applications for Nuclear Pharmacy, Inc.
licensure and actual licenses issued to Pharmaco-Nuclear, (80-252) made available 160 documents.
Denied portions of three documents, the disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
ENCLOSURE A
DIVISION OF RULES AND RECORDS OFFICE OF ADMINISTRATION The Acting Executive Director for Operations has issued a minor amendment to Parts 95 and 140 of the Commission's regulations. The amendment modifies these parts of the Commission's regulations to reflect the revised status of the Panama Canal Zone resulting from the provisions of the Panama Canal Treaty of 1977 and the Panama Canal Defense Act of 1979. The amendment becomes effective immediately upon publication in the FEDERAL REGISTER.
il ENCLOSURE A J
DIVISION OF CONTRACTS Week Ending June 6, 1980 PENDING COMPETITIVE REQUIREMENTS 1.
IFB RS-ADM-80-669 Title - Periodical Subscription Service Description - The contractor will be required to fulfill all agency requests for periodical subscriptions.
The contractor will be a central focal point to (1) acquire subscriptions from the publishers, (2) maintain shipping, claims, payment lists, etc., and (3) provide administrative services to assume timely receipt of technical and popular journals by the NRC.
Period of Performance - One year with two one-year options Sponsor - Office of Administration Status - IFB to print pending release date of June 16, 1980.
2.
RFP RS-NRR-80-101 Title - Advanced Reactor Accident Delineation and Assessment Description - Performance of analyses and assessment of specific safety-related issues for advanced nuclear reactor types under serious consideration by the Department of Energy.
Period of Performance - Thirty-six months Sponsor - Office of. Nuclear Reactor Regulation Status - Solicitation being developed.
PROPOSALS UNDER EVALUATION RFP RS-0IE-80-253 Title - Development of an Automated Vendor Selection System (AVSS)
Description - Develop AVSS to enable OIE to make the most cost effective use of its limited resources to inspect a meaningful range of vendors of equipment and services to NRC licensees.
Period of Performance - Two years Sponsor - Office of Inspection and Enforcement Status - Best and final offers received June 3,1980, and have been forwarded to Source Evaluation Panel for evaluation.
Meeting to select con-tractor scheduled for June 9, 1980.
CONTRACT AWARDS 1.
NRC-02-80-035 Title - Licensing Technical Assistance I
Description - Assist the NRC in conducting safety and/or environmentai reviews of license applications for the construction, operation, or decommissioning of fuel cycle facilities.
Period of Performance - One year Sponsor - Office of Nuclear Material Safety and Safeguards Status - Basic Ordering Agreement awarded to Science Applications, Inc., on
.May 23, 1980 ENCLOSURE A
2 2.
NRC-10-80-390 Title - Conversion, Programming, Implementation and Documentation of NRC Automated Pers inel System Description - The contractor shall provide all necessary personnel and facilities / equipment,as specified, required to accomplish the system analysis, design, programming, implementation and documentation for the remainder of the development effort on the NRC Automated Personnel System.
Period of Performance - Seventy-two weeks Sponsor - Office of Administration Status - Cost-plus-fixed-fee contract in the amount of $486,648 awarded on May 28, 1980, to SBA/Rehab Group, Inc., Falls Church, Va.
ADMINISTRATIVE MATTERS Contract No. NRC-10-80-382 with the Small Business Administration (SBA) and subcontract No. SB3-4-0-8(a)-80-C-598 for project entitled " Evaluation of Cost / Benefits of Policy for Placement of Documents in the Public Document Room (PDR)." Sponsor - Office of Administration.
On April 14, 1980, SBA was awarded a contract to perform the above project.
SBA then subcontracted the effort to Norman Hodges and Associates (NHA) an eligible 8(a) concern, pursuant to Section 8(a) of the Small Business Act.
SBA granted NRC the authority tc administer the subcontract with NHA.
Task II of the contract's statement of work requires that NHA recommend alternatives to NRC's proposed policy for placement of documents in the PDR as set forth in SECY-79-276.
Subsequent to entering into this contractual arrangement, NHA entered into contract No. AA-80-SAC-Q5232 with the Department of Commerce for production of microfiche from NRC documents which are made available to the public through the National Technical Information Service (NTIS).
NRC's policy regarding placement of documents in the PDR will have a significant impact on the number of documents which NTIS makes available to the public under its sales program for NRC and, therefore, will impact the microfiche requirements under the NHA-Commerce contract.
As this situation presents a potential conflict of interest with respect to NHA's continuing performance under the NRC contract, a Cure Notice was issued to NHA on May 23, 1980.
This Cure Notice advised NHA that the potential conflict of interest situation was endangering satisfactory performance of the contract in accordance with its terms.
NHA has ten (10) calendar days to respond to the Cure Notice.
Upon receipt and review of NHA's response, ADM, ELD and DC will meet to determine the proper course of action with respect to this matter.
j ENCLOSURE A
DIVISION OF' SECURITY ITEMS OF INTEREST
' WEEK ENDING JUNE 6, 1930
- On June 3,;1980,- Calvin L. Burch, Chief, Facilities and Systems Security Branch, visited the General Atomic Company in San Diego, California,to give advisory assistance in physical a'nd ADP security relating to 10 CFR Parts 25 and 95.-
4 4
4 i
=
4 1
ENCLOSURE A
0FFICE OF NUCLEAR REACTOR REGULAT10N WEEKLY ITEMS OF INTEREST (Week Ending June 6,1980)
Grand Gulf ffuelear Station, Units 1 and 2 On'May 29, 1980 th~e Director, NRR issued a Notice of Violation to the Mississippi Power & Light Company with respect to violations of
~
thret antitrust license conditions in Grand Gulf Nuclear Station, Units 1 and 2 construction permits.
MP&L has twenty days to respond.
Turkey Point 3 & 4 Westinghause notified FPL of an input error in the SATAN code that invalicates the basis for the recent 22% and 25% steam generator tube plucging amendments.
The error is corrected by reducing F by 0.05 g
to 1.93 and Turkey Point 3 is being operated and such that this limit is not being exceeded on an interim basis. The calculations will be ccmpleted today and an amendment request will be in next week to correct the Technical Specifications.
IE Region II has,been notifi.d s
and an LER is-being issued.
North Anna, Unit 1 (NA-1)
Intermittent loose parts single event alarms have been recorded on the NA-1 Loose ~ Parts Monitoring Syste'ms (LPMS) since February 20, 1980.
The licensee, in a report to the NRC dated May 1, 1920, stated that acoustic analysis of the single event alarms indicated a loose part object located in Steam Generator (SG) "B" weighing 4 ounces or less.
A 12 day outage at NA-1 (May 24 to June 4) has allowed the licensee to open up SG "B" and inspect for loose parts. On May 29, 1980 the licensee found an object in SG "B" approximately Th inches long and 3/8 incher in diameter and estimated the weigh.t to be 4 ounces or less.
The licensee will retrieve the object and attempt to determine its origin.
The above events demonstrate the usefullness of a LPMS when properly calibrated, operated, and analy:ed with adequate diagnostic noise profiles.
ENCLOSURE B
North Anna 1 On Friday, May 30, 1980, Virginia Electric and Power Company discussed with NRR the need for a change to the Technical Specifications to delete the requirement for a snubber supporting the safety infection system for North Anna 1.
In response to staff questions, it was learned that one of the reasons for the request was the fact the seismic piping analyses performed by Stone & Webster for piping systems which run between buildings may not be conservative.' The piping analyses at NA-1 uses the center-of-gravity method to determine which floor response spectra should be used. This may not be conservative for buildings which have significantly different floor response spectra, depending on the piping natural frequencies in each building.
As a result of this discovery, VEPC0 halted plant startup, which was' other-wise scheduled to begin on Sunday, June 1, and agreed to keep the plant shut down until the matter is resolved to NRR's satisfaction.
TheNRCstaffhasrequestedthatseveral'affectedpipinhrunsbereanalyzed
~
using an appropriate method of analysis to assess the significance and differences between the analysis methods.
Stone & Uebster is investigating to what extent this problem may exist at other facilities.
A ceeting with VEPC0 and Stone & Webster is tentatively scheduled for Tuesday, June 3, to discuss this matter.
Zion Unit No.1 Zion Unit 1 was s' hut down by the licensee at 6:00 a.m. on June 2,1980 based on results of hydraulic snubber tests at Bergen-Paterson (vendor of snubber).
Test results for the snub 5er control element showed a bleed rate significantly slower than required.
Relaxing of the spring force at elevated temperatures appears to be the cause of the problem.
A design change increasing the control element operating spring force is being made following successful tests.
Similar control elements in use on the Surry plants have a different design application.
However, Inspection and Enforcement Region 2 office is advising that licensee of the potential problem.
Estimated startup for Zion Unit 1 is June 3,1980.
Calvert Cliffs, Unit No. 1 In the afternoon of June 1,19S0, a small amount of radiation leakage occurred.
The leakage resulted from a control valve packing leak in the volume control system letdown line.
In accordance to the emergency plan, the auxiliary building was evacuated.
The CVCS system was isolated manually, and the leak was identified.
Ihe system was returned to operation by placing a backup valve into service.
The total release (about 10 minutes in duration) was less than 6% of the Technical Specification limit.
BGLE issued press' relcase.
ENCLOSURE B
Hatch Unit No. 2 On June 2,1980 the staff issued, orally, a temporary, one-time Technical Specification change for Hatch Unit No. 2.
The change authorized startup of the unit with 'an, inoperable High Pressure Coolant Injection System for purpose The temporary change is of conducting a test of the turbine-generator.
effective for 7 days (June 2-9) and includes a restriction of <10:; power with The circumstances surrounding this action hourly surveillance on power level.
are discussed below.
On June 2,1980 Hatch 2 tripped on high bearing vibration on the exciter of the The cause of the trip was identified as either a faulty sensor main ce.erator.
During discussions with the staff, the licensee stated that or a failed bearing.
diagnosis of the exact cause, in order to determine necessary repairs, requires that ths reacter be restarted in order to produce sufficient steam to roll the main turbine.
At the tice of the trip, the HPCI system had been inoperable for two days to repair the noter cierator to the system's injection valve.
The current, standard Technical Specifice_ ions for Hatch 2 authorizes continued operation with an inoperable HPCI
- However, for up "o 14 days to provide for such maintenance and repair activities.
the specifications do not permit startup with an inoperable HPCI.
L'e conducted an expedited review of the licensee's request to include a written safety evaluation.
The amandment was concurred in by the Eranch Chief and Assistant Director in acccrdance with 00p, Memo No., 5._
Surry Unit 1 At 12:04 am on June 3,1980, a failure of a capacitor in the transformer caused a small fire in the emergency switch gear room.
The fire brigade responded in two minutes and extinguished the fire in one minute.
The failure of this transformer, however, resulted in the automatic shutdown o f the plant.
This transformer powered instrument bus number 4.
When the failure occurred, c3:illations were observed on the instruments followed by a turbine runback, a turbine trip, a reactor trip and a safety injection.
The reactor trip was caused by a coincident steam flow / feed flow mismatch and low steam gsnerator water level.
The safety infection was caused by a coincident high main steam flow and low T;yg.
The high main steam flow signal was caused by the loss of' instrument bus number 4 ehich caused the main steam flow instruments t0 fail upscale.
No relief valves opened during this transient and all safety systems performed as designed. There was an ir. crease in radioactive gaseous activity in the auxiliary which'resulted from draining and refilling the boron injection tank. The aui.iliary building was evacuated fcr about 1-1/2 hours.
No releases above allowable limits uere mkde.
ENCLOSURE B
Haddam Neck Plant On May 28, 1980 a small, unplanned release of radicactive gas occurred at the Madd:m Neck Plant (Connecticut Yankee).
While venting the Volume Control Tank (VCT) to the waste gas system the relief valve on the Waste Gas Surge Tank (WGST) lifted fo'r 2 to 5 minutes, resulting in an uncontrolled release which was 26% greater thaa permitted by station technical specifications.
The plant was shut down fcr refueling at the time and was using the VCT to cleanup the water in the refueling pit.
The relief valve lifted because one of the two waste gas compressors located downstream of the WGST was tagced out for electrical preventative maintenance without the knowledge of the plant operator.
The maximum estimated dose at the site boundary from the release was calculated to be.005 mrem.
Beaver Valley Seismic Picestress On May 28, 1980, the Duquesne Light Company notified the NRC of a potential problem in the analysis of the pressurizer safety relief line for seismic pipestress.
This line may not have been properly analyzed in that the upset or high thrust leads occurring on relief valve opening and closing may not have been adequately considered or included in the load combinations for determining stresses.
Beaver Valley is presently analyzing their systems for the operating basis earthquake.
This notification was made since it affects the already completed analysis for the design basis earthquake.
Eeaver Valley is presently shut down for modifications. 'The revised ar.alysis and any necessary modifications will be completed before startup. A more complete definition of the problem has been requested from the utility and is expected in the near future.
ENCLOSURE B
NRC TMI PROGRAM 0FFICE BEEKLY STAiUS REPORT Week of: May 31-June 6, 1980 Plant Status Core Cooling Mode:
Cyclic natural circulation in the "A" reactor coolant system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to reactor building ambient.
Available Core Cooling Modes:
OTSG "B" to the main condenser; long tenn cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: Makeup system in conjunction with letdown flow
(, Emergency use only due to suspected leaks in the seal injection system).
Ma;or Parameters _(As of 0500, June 6,1980) (approximate values)
Average Incore Thennoccuplet: 156*F Maximum Incore Thermocouple:
194*F RCS Loop Temperatures:
A B
Hot Leg 150 F 154 F Colc Leg (1) 103*F 98 F (2) 95"F 94 F RCS Pressure:
82 psig (Heise) 94 psig (DVM controlling)
Pressurizer Temperature:
95*F Reactor Building:
Temperature:
80 F Pressure:
-0.8 psig (Heise)
W'ater level:
Elevation 290.3 ft. (7.8 ft.
from floor) via penetration 401 manometer Environmental & Effluent Information 1.
Liquio effluents from TMI-l released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
-2.
No liquid effluents were discharged from TMI-2.
3.
Results from EPA monitoring of the environment around the TMI site were:
ENCLOSURE B
2 EPA environmental stations registered background levels for air particulate and water samples. Gamma scan results for all sampling locations were negative.
Gas / Air (Kr-85) sample results during the period May 16 through J TMI Observation May 23, 1960 werei Goldsboro - 24 pCi/M Center 320 pCi/M3, Middletown - 19 pCi/M$ and Bainbridge -
20 pCi/M. The EPA states that the Kr-85 background concentration 3
in the vicinity of TMI to be in the range of 20 and 40 pCi/M,
Instantaneous: direct radiation readings showed an average level of 0.014 mrem /hr at the 17 monitoring stations.
The measurements are all attributed to naturally occurring radio-activity.
4.
NRC Environmental Data The West Screen House continuous air sample (HP-218) for the sampling period May 28 through June 4,1980, has been delivered tc tne EPA Coordination Center for analysis.
Ine following are the NRC air sample analytical results for the onsite continuous air sampler:
Samole Period I-131 Cs-137 (uCi/cc)
(uCi/cc)
HP-216 May 15-May 21, 1980
<5.4E-14
<5.4E-14 HP-217 May 21-May.28, 1980
<4.9E-14
<4.9E-14 No reactor-related raoicactivity was detected.
The licensee provided the following monthly inventory of Kr-85 releases for 1980:
January-80Ci, February-00 C1, March 63 Ci, April-69 C1, and May 85 Ci.
Total = 377 Ci.
Results of the environmental TLD measurements for the period March 18 to April 30, 1980, indicate no gamma levels above natural background.
Fifty-eight TLD's registered-doses ranging frca 0.09 mR/ day to 0.18 mR/ day. Average iose was 0.13 mR/ day.
These cose rates are consistent with natural background radiation in the TMI area.
On June 5 and 6, 1980, the NRC and the licensee obtained separate air sam:les of the reactor builcing atmosphere.
These samples we e #irst analyzed independently to determine the concentration of Kr-85 present.
Subsequently, the licensee's sample was then analy:ec by the NRC to determine the degree of correlation.
Ine licensee's results were'in agreement with those of the NRC.
Af roorne -Kr-85 concentration in the reactor building was verified to oe about 0.8 uCi/ml.
ENCLOSURE B
3 5.
Radioactive Material and Radwaste Shipments offsite.were as follows:
On Monday, June 2,1980, a Unit 2 reactor coolant sample was sent to the Sabcock and Wilcox (B&W) facility, Lynchburg, Virginia for chemical and radiochemical analysis.
On Thursday, June 5,1980, a Unit 2 LSA resin liner (type B) was shipped to NECO, Richland, Washington.
On Thursday, June 5,1980, a Unit I LSA resin liner (type B) was shipped to CNSI, Barwell, South Carolina.
On Friday, June 6,1980, compacted and solidified waste from Unit II was shipped to NECO, Richland, Washington.
6.
EPICOR II Processing Status:
(auxiliary buiiding approximate quantities)
Amount processed this week:
20,000 gallons Amount processed to date:
331,000 gallons Amount to be processed:
la5,000 gallons (This value increased from last week due to tank flushing using EPICOR II processed water.)
Major Activities (Past and Prerent) 1.
Reactor Building Purge.
On June 2, 1980, the NRC staff recommended approval by the Ccmmission of the decontamination of the reactor building atmosphere by controlled purging to the environment.
The recommendation was contained in the Final Environmental Assessment
' issued this week and discussed in a Commission meeting on June 5,1980.
The Comission will meet again on Tuesday, June 10 to consider the staff's recommendations.
2.
Unit 2 Exit Interview. An exit interview was conducted on June 4,1980, witn Unit 2 management to discuss findings from the inspection period April 27 - May 31,1980.
Three items of noncor.pliance were discussed.
Details of these findings will be documented ir the Office of Inspection and Enforcement Inspection Report No. 50-320/8;-09.
3.
Reactor Buildino Entry. No further progress was made in resolving the failure of tne inner door for personnel airicck (Nc. 2) to open.
A jammed safety lock is one of several possible causes so far identified.
The safety lock was probably activated, as cesignec, during the accident but is jammed into place because of a ralfunction.
Other possibilities continue to be corrosien, as previously identified, and other malfunctions associated with the door closure mechanism.
ENCLOSURE B
r 4
All possible causes are being examined. A new schedule for manned entry will not be established until the licensee makes a final detemination of the causes, which is expected to take about three weeks.
The licensee has not submitted a fomal proposal on the next course of action since several plans are'being reviewed.
The TMI Program Office staff is continuing to monitor the licensee's progress in this regard.
4.
Plant Vent (Stack)Uncaoping.
Plans are underway for removing the metal plate installe: on ^Fe 160 ft. plant stack in May 1979, (termed
" uncapping tne stack").
(ne cap ensured that all ventilation air.
passed through the supplementary filters installed on the auxiliary cuilding roof af ter the March 28 event.
These filters are no longer needed cue to the efficient operation of the filters located inside the auxiliary and fuel handling buildings.
Uncapping the stack is scheduled for June 10, 1980, based on a proposal by the licensee and this proposal is being reviewed by the TMI Program Office staff.
5.
_on; Term Stent Resin Storage Facility.
Fifty eight (58) of the sixty (tiO) spent resin storage cells in tne Module "A" Long Term 4aste Storage Facility contain 17 (6 x 6) liners and 42 (4 x 4) liners.
Tne Module 5 is still schedulec for completion on August 5, 1980.
Based on current liner generation rate and liner stacking procedure, it coes not appear the EPICOR II operations will :e interrupted for lack of spent resin storage space.
6.
EPICOR II Processinc Status.
Effective June 9 through June 15, 1980, EPICOR II system,wil.1 De in an unscheduled outage for system maintenance.
The major maintenance items include replacement of a control valve (ALC-242),
installation of hard line piping between the EPICOR II sump and the system inlet header, and resetting of the liner water level controllers.
The licensee-has completed draining of the TMI-2 condensate storage tank water anc the required modifications to isolate tne tank from the concensate storage system to receive EPICOR II processed water.
7.
'Temocrary) Nuclear Sampling System (SNS).
0: era: ion of this system was
- elayeo cue to calibration not yet performed cn certain instruments for the associatec ventilation system.
~ ne operational prcbisn (RCS guage isolation) repcrted last week was
- orrectec by acpropriate changes to the cpera:ing crocedure.
This even: was also the sucject of last week's exit interview.
ENCLOSURE B
5 8.-
-Gaseous Effluent Monitor Calibration.
In preparation for the Unit 2 reactor building purge, the supplemental ventilation system, which was installed on the top of Unit 2 auxiliary building after the accident, will be taken out of service.
During the Unit 2 reactor building purge, gaseous effluent will be discharged through the Unit 2 vent stack.
The gaseous effluent monitors at the modified ventilation system will be calibrated by the licensee.
The licensee's calculations indicate that about five to ten curies of krypton will be discharged during the monitor calibration.
The monitor calibration procedures are currently being reviewed by the NRC TMI Program Office staff.
Meetings Attended with Public Officials and Interested Groups 1.
On June 5,1980, H. Denton, B. Snyder and J. Collins attended a meeting helc by the NRC Commissioners on the Final Environmental Assessment on the cleanup of the TMI-2 reactor building.
Future Meetings 1.
On June 11, 1980, J. Collins will address the Appleton Papers Management Club at 6:30 p.m. at Hardings Restaurant in Camp Hill.
2.
On June 10, 1980, H. Denton, B. Snyder and J. Collins will attend a meeting to be held by the NRC Commissioners on the issue of purging the TMI-2 reactor building.
ENCLOSURE B
r OFFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING JUNE 6,1980 Regulatory Guides to be Issued in the Near Future
Title:
Guide for the Preparation of Applications for Medical Programs Reg. Guide 10.8, Rev.1 Expected Issuance Date: July 1980 Descriotion : This is the primary guide for telling applicants for licenses to use radioactive materials in or on humans what infonnation must be submitted to the NRC, and what are some of the NRC guides and practices that may be acceptable.
Contact:
A. Brodsky 443-5970 Publications Issued During the Week of May 26-May 30,1980 Reg. Guide 5.7, Rev.1 - Entry / Exit Control for Protected Areas, Vital Areas, and Material Access Areas [ Issued to Reflect Comments]
Draft Regulatory Guide and Value/ Impact Statement: Proposed Revision 1 to Reg. Guide 8.12, Criticality Accident Alarm Systems, Task OH-015-4
.[ Comments requested by July 25, 1980]
Publications Issued During the Week of June 2-June 6,1980 Reg. Guide 5.44, Rev. 2 - Perimeter Intrusion Alarm Systems [ Issued to Reflect Comments]
ENCLOSURE C m
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending June 6,1980 Design Guidance for MC&A System Design The Lawrence Livermore Laboratory (LLL) has delivered a report entitled,
" Design Guidance. Logic Tree for the MC&A Upgrade Ruh." This report provides the major components that the Division of Safeguards will utilize to construct the logic tree to be incorporated into the MC&A Upgrade Rule Guidance Compendium.
100 rem / hour Self-Protection Exemption Criterion The DOE proposal of work for a study which will investigate the technical basis of the 100 rem / hour self-protection exemption criterion has been received. The proposal was reviewed by NRC staff and found to be acceptable This study is being performed at Los Alamos Scientific Laboratory which will provide a draft report by September 30, 1980.
Physical Protection of Transient Shioments and Federal Register Notice are being prepared which A draft Commission Paper,f a final rule for Physical Protection of Transient recommends publication o Shipments. No changes are being made to the amendments, however, the guidance is being revised slightly to _ incorporate public comments. When the final rule is published, which will become effective at that time, the guidance will serve as a regulatory guide in draft form.
UNC - Wood River Junction
'On May 29, 1980, representatives of United Nuclear Corporation's Recovery Sy, stems Division met with Safeguards and Fuel Cycle personnel to discuss plans for decommissioning the Wood River Junction Scrap Recovery facility. UNC's decommissioning schedule has a target date of April 1,1981, for release of the facility for unrestricted use.
GE Morris Spent Fuel Storage An Environmental _. Impact Appraisal (EIA) for General Electric's Morris Operation (spent fuel storage) was issued on June 5, 1980. The EIA is related to GE's request to renew its license for Morris for a 20-year period. The staff concludes in the EIA that an Environmental Impact Statement need not be prepared and the issuance of a negative declaration to that effect is appropriate.
4 Inasmuch that an EIS is not being prepared, it is a point of contention in
)
the forthcoming hearing on the Morris Operation.
ENCLOSURE D
Items of Interest 2
-Biomedical Research Waste A Fuel Cycle' Division representative visited the Beltsville Maryland facility of the U.S. Department of Agriculture on May 30, 1980. The purpose of the visit was to-discuss the disposal of animal carcasses resulting from their biomedical research.in connection with a report NMSS is preparing on disp'osal
~
of anical carcasses (radioactive) used in institutional research. This type of waste is generated at approximately 250 facilities under the Department of Agriculture.
ENCLOSURE D
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending June 6, 1980 1.
Vermont Yankee Nuclear Corporation - Civil Penalty Action - On June 2, 1980, the Comission received a check from the subject licensee in the amount of $4,000 in full payment of proposed civil penalty issued on May 7, 1980.
2.
Preliminary Notifications relating to the following actions were dispatched during the past week:
a.
PNO-I-80-85 Calvert Cliffs Unit 1 - Unplanned Gaseous Release b.
PNO-I-80-86 Beaver Valley Unit 1, Calvert Cliffs Units 1 & 2 -
Tornado Watch c.
PNO-I-80-87 Millstone Unit 1 - Unscheduled Extended Outage d.
PNO-I-80-88 Babcock & Wilcox, Apollo and Parks Township, PA - Tornado Causes Loss of Off-Site Power at Parks Township Facility e.
PNO-I-80-89 Indian Point Unit 2 - Loss of Offsite Power and Plant Trip f.
PNO-II-80-96 Turkey Point Units 3 & 4 - Error in Emergency Core Cooling System Analysis
-g.
PN0-II-80-97 Crystal River Unit 3 - Once Through Steam Generator (OTSG)
Safety / Relief Valve Guide Bushing Cracking h.
PN0-II-80-98 Surry Unit 1 - Electrical Fire and Resultant Safety Injection 1.
PNO-II-80-99 Turkey Point Units 3 & 3 - Potential 5.8 Rems Whole Body Exposure J.
PNO-II-80-100 Hatch Units 1 & 2 - Confirmation of Action Letter ca Mechanical Snubbers 1.
PNO-II-80-101 General Electric Co., Wilmington, NC - State Inquiry on An Anonymous Allegation n.
PNO-III-80-104 Kewaunee - Short Bolts on Steam Generator Support Columns n; PNO-III-80-105 Kewaunee - Crack in Low Pressure Turbine Disc o.
PN0-III-80-106 Midland Units 1 & 2 - Inconsistencies in Engineering Drawings p.
PNO-III-80-107 Fermi Unit 2 - Allegations Received From News Media (WXYZ, Channci 7, Detroit) q.
PNO-III-80-108-University of Wisconsin, Madison, WI - Apparent 8.63 Rems Whole Body Exposure ENCLOSURE E
. r.
PN0-III-80-109 Zion Unit 1 - Unplanned Maintenance Outage - Steam Generator Snubber Control Valve Assembly Modification s.
PNO-III-80-110 ' Abbott Laboratories, North Chicago, IL - Package Containing One Microcurie of Iodine-125 Crushed at O' Hare Airport t.
PNO-V-80-43 Nuclear Engineering Co., Richland, Washington Burial Site -
Planned Tour by Governor Dixie Lee Ray and Party u.
PNO-V-80-44 Nuclear Engineering Co., Richland, Washington Burial Site -
Banning of Research Triangle Institute, Research Triangle Park, North Carolina (State Licensee) for Radioactive Waste Shipments v.
PNO-V-80-45 Nuclear Engineering Co., Richland, Washington Burial Site -
Banning of National Jewish Hospital, Denver, Colorado (State Licensee) for Radioactive Waste Shipments w.
PNO-V-80-46 Nuclear Engineering Co., Richland, Washington Burial Site -
Banning of Atomic Disposal Company, Tinley Park, Illinois (NRC Licensee) for Radioactive Waste Shipments x.
PNO-V-80-47 Nuclear Engineering Co., Richland, Washington Burial Site -
Banning of Nuclear Diagnostics Company, Peekskill, New York (State Licensee) for Radioactive Waste Shipments y.
PN0-TMI-80-33 Three Mile Island Unit 1 - Ambulance Leaves Site z.
PNS-I-80-13 Indian Point Units 2 & 3 - Bomb Threats aa.
PNS-I-80-14 Indian Point Units 2 & 3 - Bomb Threat bb.
PNS-I-80-15 Indian Point Units 2 & 3 - Bomb Threat cc.
PNS-V-80-05 Diablo Canyon Units 1 & 2 - Bomb Threat 3.
The following IE Information Notices were issued:
a.
IE Information Notice 80-24, " Low Level Radioactive Waste Burial Criteria,"
was issued on May 30, 1980 to all NRC and Agreement State licensees.
b.
IE Information Notice 80-25, " Transportation of Pyrophoric Uranium," was issued on May 30, 1980 to all NRC materials licensees authorized for operations with special nuclear material or source material (except fuel cycle facilities), waste collection and waste disposal, and to Agreement State licensees authorized for similar activities.
ENCLOSUP.E E
0FFICE OF NUCLEAR REGULATORY RESEARCH Important Items-Week Ending Dune 6, 1980
/
..I SAFER s.
A firal review of the program " Plutonium Dicxide Leakage Through Small Apertures" was held on May 28.
The three major reports issued under the prcgram (NUREG/CR-0745. -0958, and -1099) were discussed in detail with the Research Review Grcup.
LOFT The fir:- ir the :crics of operatic.el transion: tes: en '. ort, IF-5. was run cr Paj 25, 1530.
The loss-of-feedwater test was initiated from 37 MW:, a-d ncemal syster, c:erating pressure, temperature, snd flow cer:itions.
Reacter trip occurred manually at 25 second: cae to low steam generatcr level.
Following the reacter trip, the primary coolant systen response was similar to that Observed in the trip from 751 power during the po,ter range test series t.tc yea 1 ago.
Both the hot leg and ccid leg ccolan-temperatures showed a s* f gnt de:rease af ter reacter trip fcilowed by an increase cf 3 to 7' F before again decreasing.
Duri.ng tne period between stepping the steam generater fee: water and. the reacter trip the primary system pressure increased about 60 osi.
Following trip the pressure decreased about 90 psi and then began a slce re:csery of about 80 psi.
The primary system pressurc never reached the pressure re*ief valve set point.
Pressure in the secondary system rcse core slcwly than predicted by the RETRAN cc:e because the steam valve continued to leak a snail flow. L'hile this behavice was expected, the value of the leakage could net be predicted and the efere was assunad zero. As a result of this difference the seccndary relief valve coened at 600 seconds instead of 150 seconcs.
All d1fferences between ;redictions and results appear to be relatec to this steam valve leak.
Feedaater injection was begun 18 minutes after being stcpecd.
Approximately 30 -iretes ir.to the test the operators open2d the s eca bypass va've to ce:riise the sec:ndary side pressure and aid reffi'ir; ef tre ste r generator wai:n nac em:tiec o tns top of the U-tube scris.
Ait.:.';n re test was mild compared o most tests performat a: LG~T
't pr:-idt: irfctmation necded to plcr, the firs'
- ?' S tt:t.
C l
EN LcSL':.E F
b 0FFICE OF NUCLEAR REdutATORY RESEARCH Important Items - Week Ending June 6,1950 (Continued)
_Internatiensi Procrams The research agreement between NRC an: the Netherlands Energy Research Foundation (ECN) covering the NRC-fundec HSST and ART programs and the ECN BROS-I-II/EPOSS/ AEROSOL programs came into force on June 6,1980, with the signin; of the agreement by Professor Geedhoc; of the ECN.
The agreemen: ha: earlier been signed en behalf of HRC by W. J. Dircks en April 21, 1520.
ECLOSUP.E F l
OFFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST Week of June 6, 1980 Atlantic Research Corocration (Byproduct License)
On June 2,1980, the Appeal Board issued a Decision (ALAB-594) relating to the mitigation of the amount of the monetary penalty to be assessed against the licensee.
The matter came before the Appeal Board on a
. remand by the Conmission of ALAB-542.
The Appeal Board ruled that there was reason to reduce the penalty assessed against the licensee fron $8,600 to $2,000..In a partial dissent from ALAB-594, Dr. Buck, a member of the Appeal Board. rendered the opinion that he would have remitted the monetary penalty in its entirety.
J E
i
)
ENC'_05URE G l-
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JUNE 6, 1980 EXPORT / IMPORT AND INTERNATIONAL SAFEGUARDS Analysis of Health, Safety, and Environmental Imos ts of Reactor Exports J. Shea, J. Lafleur, and H. Schechter of IP met on June 2 with H. Denton, E. Case, W. Kreger and W. Russell to discuss NRR calculations of the health, safety and environmental impacts on the global commons resulting from a postulated accident at the proposed site for Korea reactor units 7 and 8.
- NRR will prepare a report on this subject, essentially along the lines developed earlier by the staff in connection with the Philippine reactor case, supplemented as appropriate by material drawn from the Commission order on the Philippine reactor export. This report would be provided to the Commission as part of the staff's analysis and recommendations on the export of these reactors.
If any further guidance or comments on the scope of this report is provided by the Commission prior to completion of the staff analysis, this will be incorporate).
GAO Export Study Two GAO staff members currently are reviewing export licensing files in IP as a part of the three year study being carried out by GA0 to determine the effects the Nuclear Non-Proliferation Act of 1978 has had on U.S. exports of nuclear material and equipment.
State Department Meeting on Export Matters.
IP and NMSS staff met with State Department representatives on June 2 to discuss physical security questions relevant to exports.
INTERNATIONAL COOPERATION NRC-PAEC Exchange Arrangement In fulfillment of Case Act requirements, IP this week forwarded to the Department of State a ceritified copy of, with accompanying background statement on, the NRC-Philippine AEC information exchange Arrangement, which became effective upon PAEC signature April 28, 1980.
EUCLOSUoE H
2 FOREIGN VISITORS:
On Tuesday, Dr. William Hannum, Deputy Director General of the Nuclear Energy Agency (NEA) of the OECD, met separately with Commissioners Gilinsky, Kennedy, and Hendrie to discuss U.S. nuclear policy and prospects.
On Tuesday, Mr. Glyn England, Chairman, and Mr. John Baker, Secretary, of the U.K. Central Electricity Generating Board (CEGB), met separately with Comnissioners Gilinsky, Kennedy, and H]ndrie, W. J. Dircks, Actino EDO, and J. D. Lafleur, Jr., IP, to discuss (1) nuclear oower in general, [2) public perceptions of nuclear power, (3) NRC's response to TMI, and (4) post-INFCE actions.
On Tuesday, Dr. D. G. Thackrah, Superintending Inspector of the U.K. Nuclear Installations Inspectorate (NII) met with J. Bunting, M. Bell, J. Braun, and P. Lohaus, of WM/NMSS to discuss the regulatory and technical problems associated with the management of radioactive wastes.
On Thursday, Mr. Bruce Webb, Director-General of Mines and Energy for the State of South Australia and Deputy Chairman of the South Australian Uranium Enrichment Committee met with H. Miller, J. Bunting, and J.,'Braun of WM/NMSS to discuss codes of practice and legislative controls on uranium mining, milling and transportation.
On Wednesday, Commissioner Hideo Uchida from the Japanese Nuclear Safety Commis-sion (NSC), Mr. Sato, TMI Specialist with the Japanese Atomic Energy Research Institute (JAERI) and a reresentative of the Embassy of Japan met with J. R. Shea, IP Director, and J. D.'Lafleur, Jr. of IP, tc discuss items of mutual concern. On Thursday the visitors met with senior staff representatives of NRR to discuss siting policy, and on Friday the visitors met separately with Chairman Ahearne, Commissioners Gilinsky, Kennedy, Hendrie, and Bradford, and senior staff representatives of NRR to discuss safety analysis and NRC action plans.
On Friday, Mr. Ralf Ahlstrand of the Finnish utility Imatran Voima Oy (IV0),
Messrs. Klaus Rahka and Seppo Salonen of the Technical Research Center of Finland, and Mr. Sakari Innonen of the Erobassy of Finland met with C. Z. Serpan and M. Vagins. of RES, and W. J. Hazelton of NRR to discuss fracture mechanics and surveillance of NSSS-components.
ACRS Visits to Germany and France Under the provisions of NRC regulatory exchange arrangements with France and Germany, during the period May 13-29 members of the ACRS visited nuclear facilities in these countries and participated in technical discussions with the Reactor Safety Commission of the FRG and the Group Permanent Reacteur in France. The visited facilities included power reactors, control room simulators, reprocessing plants, waste treatment and storage facilities and various nuclear safety research test facilities.
In connection with these visits, H. Faulkner, IP, _caducted the annual Arrange-ment Administrators' meetings with representatives of the FRG Ministry of Interior and the French Central Service for the Safety of Nuclear Installations.
ENCLOSURE H
O OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JUNE 6, 1980 Tom Elsasser, Region I SLO, appeared before the Maryland Commission on Intergovernmental Cooperation on June 3 accompanied by Monte Conner, OR/NRR.
The Maryland Commission requested NRC participation in this hearing to discuss spent fuel storage at Calvert Cliffs.
Other witnesses included DOE,.the State of Maryland, and Baltimore Gas and Electric.
In addition to questions on spent fuel storage at Calvert Cliffs, there were other broader questions relating to low-level waste storage capacity as well as the transportation of radioactive materials.
Under current law, Maryland forbids the disposal of low-level waste.
A second hearing is scheduled for June 17 on emergency planning activities.
NRC has not been asked to participate in that hearing.
Robert Troj anowski, Region II SLO, attended a Regional Advisory Committee meeting in Atlanta on May 28.
This meeting constitutes the final Committee review meeting on the Tennessee emergency i
plan.
The plan will be transmitted to FEMA for approval af ter a
~
public meeting, scheduled for June 10 in Chattanooga has been conducted and an exercise has been completed.
William B. Menczer, Region III SLO, attended the Regional Advisory Committee meetings in Homewood, Illinois, on June 4 to review the Illinois radiological emergency response plan.
On June 6, Mr. Menczer met with local officials in Madison, Indiana, to discuss the resident inspection program at the Marble Hill Nuclear Power Station.
On June 3, 1980, Dean Kunihiro, Region V State Liaison Officer, attended a meeting of the Washington Energy Facility Site Evaluation Council's '(EFSEC) Emergency Response Task Force chaired by Nick Lewis.
The purpose' of the meeting was to discuss the status of the development program for the proposed fixed nuclear site emergency response plan.
While in Olympia, Dean met with Mr. Lewis, who is also the Washington State Liaison Officer, and other members of the Council to discuss a range of issues of mutual concern to NRC and Washington State.
- NRC has 'been invited to participate in a briefing of Washington State officials ' by, Met Ed regarding the low-level waste shipments from TMI to Hanford.
The meeting will take place in Governor Ray's office on June 17.
ENCLOSURE I
j 0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS Items of Interest WEEK ENDING JUNE 6,1980 Manoower System Developed and implemented System to report and track AE0D manpower expended on planned accomplishments for the new Office of Analysis and Evaluation of Operational Data.
Management Information Prepared " Power Reactor Events Report", Vol. 3, No. 2, dated May 1980 for the period March-April. Sent to OCA for Congressional Committees.
Program Area Review Attended bfiefings by offices on proposed FY 82-86 programs.
Begin reviewing programs for consistency with PPPG.
ENCLOSUP.E J
u-Office of the Controller-Items of Interest Week Ending June 6,1980 FY 1982 Budget Formulation
-The major program offices have met the requirement of submitting their budgets to the Office of the Controller by June 2, 1930, with the exception of NRR.
EDO briefings by the Office Directors are scheduled to take place on June 4, 6 and 9,-1980.
9 Enclosure K
CALENDAR OF SPEAKING ENGAGEMEtlTS June 15 L. Beratan, SD, will lecture to the IE inspectors on construction failures at the Portland Cement Association training program 1
ENCLOSURE N