ML20004D999

Weekly Info Rept for Wk Ending 810529

ML20004D999
Person / Time
Issue date:	06/04/1981
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-810529, NUDOCS 8106100525
Download: ML20004D999 (29)

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June 4,1981 For:

The Comissioners i

From:

T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING MAY 29, 1981 A sumary of key events is included as a convenience to those Cocnissioners who may prefer a condensed version of this report.

Contents Enclosure i

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

Management and Program Analysis I

Controller J*

Aralysis and Evaluation of Operational Data K

Small & Disadvantaged Business Utilization L*

Items Approved by the Commission M

o T. A. Rehm, ss n nt for Operations Office of the Executive Director for Operations m

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• No input this week.

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Contact:

T. A. Rehm EDO 2j JUll 05198; u 49-27781

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SUffiARY OF WEEKLY INFORMATION REPORT WEEK ENDING MAY 29, 1981 4

D.C. Cook Unit 2 & Indian Point 2 Both plants commenced operations on May 20 and May 23, respectively, following refueling outages.

Modifications were also made.

Maine Yankee On May 22, the licensee requested and was granted a Technical Specification change i

that would allow refueling to continue with the reactor building purge charcoal 55sorbers by-passed until the completion of either the Low Pressure Safety l

Injection check valve installation or the refueling operation, whichever comes first. This is to avoid poisoning of the charcoal absorbers while cutting and welding the check valves, l

Salem 2 Salem 2 received its full power license on May 20. The license contained a number of license conditions, related primarily to fire protection, which required completion of specified actions prior to exceeding five percent power.

The Office of Inspection and Enforcement verified the satisfactnry completion of all five t

percent license conditions on May 24, and Salem 2 was placed in Mode 1 operation for power ascension testing on May 26.

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Dresden 2 On May 24, the MG set on one of the recirculation loops failed. The licensee requested a Technical Specification change to permit the plant to continue operation (at.

i reduced power) beyond the specification limit of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, while the damaged MG set is rewound.

Based upon the staff's review of a G.E. Single Loop Analysis, it granted I

the licensee authorization to continue plant operation for seven days with one recirculation loop out of service, with conservative limits imposed.

i Dry Spent Fuel Storage Cask Designs i

The Office of Nuclear Materials Safety and Safeguards received two letters of intent to sumbit Topical Reports on dry spent fuel storage cask designs for review.

i Cooperative Arrangement with INP0/NSAC I

On May 26, the Executive Director for Operations signed the proposed Memorandum l

of Agreement with INP0/NSAC on a cooperative relationship for the collection and feedback of operational data.

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OFFICE OF ADMINISTRATION Week Ending May 29, 1981 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 249 8

Granted 173.

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Denied 28 5

Pending 48 2

ACTIONS THIS WEEK 1

Received (NRC employee)

Requests a copy of a letter of resignation by a (81-206) named individual.

Michael 'napik, Requests a copy of SECY-81-233 " Prospective Changes McGraw-Hill Publications to U.S. Non-Proliferation Policy" and a copy of a Company letter from the NRC to the State Department following (81-207) up on this SECY paper.

Granted Jatnes A. McLellan, In response to a request for the-names of all Pro-Tech Support licensed reactor operator and senior reactor operators.

Services, Inc.

made available a printout of this information.

(81-166)

Lynn Connor, In response to a request for specific information Doc-Se' arch Associates on personnel in the Offices of Standards Development,

- (81-180)

Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, and.

Inspection and Enforcement, made available infonnation.

Steven C. Shelly, In response to a request for copies of coments made Union of Concerned by Messrs. Dale F. Thatcher and Rodney M. Satterfield SciGntists on the draft ORNL review of BAW-1564 along with any (81-181) other coments which are in the Comission's possession, informed the requester there are no coments on this draft ORNL review.

1 CONTACT; J. M. Felton 492-7211 ENCLOSURE A

2 Granted. Cont'd Don Wilson, In response to a request for a list of the NRC's The Equitable Life Region I employees to include their names, positions, Assurance Society of salaries, GS levels, and duty stations, made the United States available this information.

(81-189)

James Wagner.

In response to a request for a copy of the non-Technassociates Incorporated proprietary version of the winning technical (81 -1 94) proposal under NRC Contract No. NRC-10-81-379, made available a copy of this document.

Denied None O

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l ENCLOSURE A

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DIVISION OF CONTRACTS y'

Week Ending May 30, 1981 1

RFP ISSU_E_D_

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RFP-RS-81-204 Title - Task Analysis of Nuclear Power Plant Control Room Crews Description - The purpose of this research is to obtain detailed task analysis information on control-room operating crews during transient and accident conditions.

The results will provide information needed for an improved technical basis for require-ments related to staffing qualifications, training, procedures, l

and control room design.

Period of Performance - 17~ months Sponsor - Office of Nuclear Regulatory Research i

Status RFP Issued May 26, 1981.

Proposals are due June 25, 1981.-

PROPOSALS UNDER EVALUATION 4

1.

RFP-RS-RES-81-178 Title - The Degraded Piping Program Description

.The contractor will plan a comprehensive experimental program to demonstrate the capacity of cracked piping to withstand postulated accident and transient loading and to evaluate the validity of tearing instability fracture mechanics analysis as

'a technique for predicting the loading capacity and failure made of piping that has or is postulated to have significant cre.cking.

Period of Performance - 9 months Sponsor - Office of Nuclear Regulatory Research Status - RFP closed May 8, 1981.

Proposals are under evaluation.

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2.

RFP-RS-RES-81-179-l Title - A study of Earthquake Hazards in N.Y. State and Adjacent Areas.

Description - The objective of this work is to continue monitoring N.Y. State and adjacent areas as an integral part of the program for the Northeastern U.S. and to obtain pertinent analytical information i

based on the collected data.with the broad objective of providing j

better criteria for hazard evaluations.

4 Period of Performance - 3 years with options for two (2) one (1) year periods.

l Sponsor - Office of Nuclear Regulatory Research Status - Awaiting audit and subcontracting plan being negotiated.

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i ENCLOSURE A 4

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r CONTRACTS CLOSED OUT (All administrative action completed and final payment made)

Contract No.

Contractor Closeout Date NRC-0?-78-038 NLI, Incorporated 5/21/81 NRC-03-78-159 Nationa'l Bureau of Standards 5/26/81

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NPr.-11-80-402 Battelle Columbus Labs 5/28/81 NRC-03-81-096 Franklin Research

- 5/22/81 I

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ENCLOSURE A r

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OFFICE OF NUCLEAR REACTOR REGULATION WEEKLY HIGHLIGHTS - MAY 29, 1981 D3NA.LD C. COOK NUCLEAR PLANT, UNIT NO. 2 D. C. Cook Un'it No. 2 corsnenced its third cyclei of operations 'on Ney 20, 1981.

Actions included in the refueling outage were (1) fuel loading for a 18 month cycle, (2) inspection of seals in all four R.C. pumps, (3) installation of new blades and ~ replacement seals in the high pressure turbine, (4) performance of a containment leak test, (5) ins

tion,

. eighing the ice and adding water to the ice condenser, (6) pecinspection w

. of the steam generators, and (7) replacement of steam generator feedwater tibows. with themal sleeves.

Other plant modifications based on NRC requirements included (1) TMI mods.,

(2) installation of the Nuclear Evacuation Alam, and (3) installation of Hydrogen Distributed Ignition System.

The next refueling cutage is scheduled to comente in October,1982.

9.1.1:;E TMEE ATOM!C P0b'ER STATION j

l Cn ay 22,1981, the licensee requested and was granted a Technical Specification change thet would allow refueling to continue with the reactor building purge charcoal absprhers by-passed until either the completion of the Low Pressure

, Safety injection (LPSI) check valve installation or completion of the refueling coert:icn, whichever is earlier.

The request was made because the current Tech.ical Specification requires purging of the reactor building through the l

cparc al absorbers whenever irradiated fuel is being handled.

However, purging i

thecu;h the charcoal absorbers while cutting and welding the LPSI check valves veil'. ;;isen the absorbers and can render them inoperable.

The emergency Technical

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Specifications would allow the licensee to place the charcoal absorbers in the by-pass mcde while cutting and welding on the LPSI check valve installation.

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On :>.sy 2i,1981 the licensee shutdown the plant for refueling thus providing a...

decay eriod greater than the 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> found acceptable in our evaluation of -

the Fuel :-:andling Accident Inside Containment.

l SA'_EM 2 A full power license was issued for Salem Unit 2 on May 20,1981.

The full p:ce'r license contained a number of license conditions, related primarily

fire prctection, which required completion of specified actions prior

.:. uceeding five percent power.

The Office of Inspection and Enforcement et.-ified the satisfactory completion of all' five percent license ccnditions c.:'ay 24, 1951.

On May 25,19E1, Salem 2 was placed in Mode 1 operation

.% r ;c.<er as cer.sion testing.

ENCLOSURE B

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NRR,WEEKLYkIGHLIGHTS.

t DRESDEN 2 the MG set on one of the recirculation loops at Dresden 2 On May 24,1981, Commonwealth Edison requested technical specification change to failed.

permit the plant to continue operation (at reduced power) beyond the existino technical. specification limit of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, while the damaged MG set is rewound.

. Ceco telecopied a summary of a G.E. Single Loop Analysis applicable to Dresden and the Operating Reactors Assessrent Branch i scussed the analysis The analysis is similar to earlier analyses used with. CECO representative.

in support of technical specification changes at Duane Arnold and Peach Bottom.

Based upon its review the staff granted authorization to continue operatio6 for seven d5ys with one recirculation loop out of service with conservative limits ieposed.

r ICIAN FOII;T 2 (I.P. 2) 1.F. 2 ccamenced its fifth cycle of pc.ler operations on !!ay 23, 1951 after beir.g shutdcwn since October 17, 1981, the day water was found inside containment.

Acticns incluied in this cutace were:

(1) F.eplacegynt of the fan coolers and other modifications to preclude recurrence of the ficoding incident; (2) F.efueling; (2) Installation cf reactor coolant pipe restraints to nitigi e effects of asymmetric LOCA ' cads; (4) Cor. trol room human engi-r.eering nodificaticr.s; (5) fire protection and TMI didifications.

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i ENCLOSURE B

4 NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT h

p Week ef May 23 - 30 1 981 0

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l Plant _ Status _

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Con Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to Reactor Building ambient.

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I Available Core Coolin3 Modes:

Long-term cooling "B" (once through I

steam generator-B); decay heat removal systems.

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l ItCS Pressure Control Mode:

Standby Pressure' Control (SPC) System.

I ckup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System.

Il Decay Heat Removal (DHR) System.

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]t Major Parameters (as of 0400, May 29,1981) (approximate values)

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Average Incore Thernocouples: ll?*F

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Maximum Incore Thermocouple:

144 F

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RCS Loop Temperaturcs:

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A B

Hot Leg il3*F ll6*F ColdLeg(1) 67*F 67*F (2) 68*F 67'F t

1 RCS Pressure: 98 psig l

Reactor Building: Temperature:

72"F

}3 Water level:

Elevation 290.8 ft. (8.3 ft, t rom floor) b' via penetration 401 manometer

j Pressure

-0.5 psig h

Concentration: 2.3 x 10-5 uCi/ml Kr-85 (Sample taken l

5/25/81) 6 Effluent and Environmental (Radioloaical) Information

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1 Liquid effluents from the TMI site released to the Susquehanna River

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after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.

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During the' period May 22, 1981, through May 28. 1981, the effluents a

contained no detectable radioactivity at the discharge point although r

individual effluent sources which originated within Unit 2 contained

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minute amounts of radioactivity.

Calculations indicate that less than 1 millionth (0.000001) of a curie of Cs-137 was discharged. This-o

'y represents less than 0.00001% of the pennissable total liquid activity i

as specified in Technical Specifications for operational commercial

]; reactors.

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24 Airborn' e Gffluents are rcpsrt;d en a monthly basis.

3,p( Environmental Protection Agency _(EPA) Environmental Data.

i Results' j f rom EPA monitoring of the environment around the TMI site were as n

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The EPA measured Kr-85 concentrations (pCi/m ) at several l

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environmental monitoring stations and reported the following l

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results:

t Location May 15 - May 22.1981 I

(pCi/m3) i 1

Goldsboro 25 4

Observation Center 29

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Middletown 28 l

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Yorkhaven 22 t

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t All of the above levels of Kr-85 are considered to be back-

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ground levels.

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U Th'e installation of tritium (H ) monitoring devices has been 3

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cgapletedattheabovelistedlocations.

It is expected that H environmental results will be routinely reported by EPA in j

about three to five weeks.

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No radiation above normally occurring background levels was f

,P detected in any of the samples collected from the EPA's air

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b and gagna rate networks during the period from May 21, 1981

'h through May 28, 1981.

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4. 3 NRC Environmenta_1_ Data.

Results from NRC monitoring of the environ-E

% ment around tt.e TMI site were as follows:

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The following are the NRC Rir Sample analytical results for E

the onstte continuous air samp1dr:

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I-131 Cs-137

.-.i Sample Period 1

_(uCi/cc)

(uCi/cc)

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I, iHP-?69 May 20,1981 - May 27,1981

<8.2 E-14 <8. 2 E-14 f 1.icpnsee Radioactive Material and Radwaste Shipments _

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On Friday, May 22,1981, one 4' x 4' EPICOR-II dewatered resin h

l liner (liner DF-15) from Unit 2 was shipped to U.S. Ecology, j

]i Richland, Washington.

This shipment was not reported in the j

status report for the period of May 17-22, 1981.

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On Tuesd,ay, May 26,1981, a 40 ml Unit 2 reactor coolant i

j sample was sent to Babi;ock and Wilcox (B&W) Lynchburg, Virginia.

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l ENCLOSURE B

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On Thursday, May 28, 1981, 54 drums and 8 scatal boxes cf compacted and non-compacted Unit I low specific activity (LSA) l j

l waste were shipped to the Chem-Nuclear Site, Barnwell, South Carolina, e

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h On Thursday, May 28, 1981, an empty shipping cask used in Unit 2 was shipped to the Chem-Nuclear Site, Barnwell, South Carolina.

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Major Activities i;

hl 1.

Submerged Domineralizer System (SDS).

Preparation of the Safety Evaluation Report (5t.8) by the TMI Program Office is in progress although some necessary information has not yet been received.

On

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j May 13, 1981, the licensee submitted a revised schedule for providing

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j the needed information. The outstanding information will be provided in early June 1981.

h Functional tests are complete with the exception of a few items I

which are undergoing engineering evaluation and further testing.

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Operator training on components not involved with the outstanding

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j functional testing has been initiated.

The operator training does J

not involve processing of contaminated water.

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2.

Reactor Building _(RB) Purge and Entry.

The eleventh entry into the l

y Unit 2 RB was completed on Thursday, May 28, 1981.

All the tasks i

h scheduled for the entry were completed.

The entry tasks included 1

the following:

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!j Polar crane personnel safety equipinent installation, Sump survey with portable gama spectrometer, l,

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Lighting relay repair, j

j Replacement of an inoperable radiation monitor.

l Repair on the RB intercom system, Surveillance, servicing. photography, and radiation surveys of l

H components in the vicinity of the pressurizer, l!.

Floating sump pump discharge hose connection to the SDS.

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The radiation survey of the area near the pressurizer indicated that the ambient radiation levels on top of the pressurizer was j,

approximately 3 R/hr (gamma).

Radiation hot spots were detected at

,j boron deposits under valves on top of the pressurizer which apparently leaked at one time. There was no indication of recent leakage (the primary system is depressurized to less than 100 psig).

The radiation f

levels at the hot spots were 8 to 10 R/hr (gamma) and approximately j

30 Rad /hr (beta).

Ambient radiation levels below the plane of the

h pressurizer top were a' proximately 1 R/hr. A contact reading of p

the insulation on the tope of the "A" steam generator was approximately

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1 R/hr.

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i ENCLOSURE B c

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_y u-i dli A cursory radiation survey on the polar crane indicated 80 mr/hr (gama) and 80 mrad /hr (beta).

An electrical / mechanical inspection li and a thorough radiation survey of the polar crane is planned for ll the next entry.

The next R8 entry is tentatively scheduled for f

June 26, 1981 uj.

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h Future M,ing t!i un Thursday, June 4,1981, the Advisory Panel for the Decontamination of IMI Unit 2 Will meet from 7:00 p.m. to 10:00 p.m. in the City Council Chambers, Kendig C. Bare Public Safety Building, 208 North Duke Street,

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Lancaster.

At this meeting, which is open for public observance, the Panel will discuss Radiation Worker Exposure and Health Effects.

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ENCLOSURE B

0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 29, 1981 Dry Spent Fuel Storage Cask Designs NMSS has received two letters of intent to submit Topical Reports on dry spent fuel storage cask designs'for review.

Gesellschaft fuer Nuklear Service mbH (GNS) intends to submit its report in July of 1981, and Ridihalgh, Eggers, and Associates intends to submit its report in September of 1981.

TASTEX Steering Committee Meeting During the week of May 25, 1981, Mr. C. N. Smith, Material Control and Accountability Licensing Branch, is representing the NRC on the U.S. team at the final TASTEX Steering Committee meeting in Tokyo, Japan.

Mr. Smith is also participating in bilateral and trilateral consultations on estab-lishing safeguards cooperative programs.

NRC Incident Response Exercise i

On May 27, 1981, HMSS participated in an exercise concerning a simulated incident at a power reactor site. The scenario provided for play between the FBI, DOE, FEMA, and various other Federal and State agencies.

It pro-vided valuable training for the participants on interagency coordination.

h ENCLOSURE C

4 Meetings Division of Fuel Cycle and Material Safety Discussion regarding current status of nuclear 1.

Subject:

pacemakers.

Date/ Time:

May 28 - 9:b0 Location:

Room 428, Willste Attendees:

B. Si,nger (FC), P. Vacca (FC), Jessica Gamon (Washington Radiology Reports) 2.

Subject:

Discussion of Radiological Contingency Planning Requirements with General Electric, Wilmington, North Carolina.

Date/ Time:

May 28 - 10:00 Location:

Room 517, Willste Attendees:

F. D. Fisher (FC), R. G. Page (FC), Charles Vaughn (GE, Wilmington) 3.

Subject:

Draft NRC/ EPA Memrandum of Understanding - Control of Areas Contaminated with Radioactive Materials.

Date/ Time:

May 28 - 2:00 Location:

Room 517, Willste Attendees:

R. E. Cunningham (FC), D. Mausshardt (NMSS), R. G. Page (FC),

F. Chanania (NRC), Ray Johnson and Jay Silhanic (EPA) 4.

Subject:

To work with Sandia Laboratory on.the'. application review process for material licensees.

Date/ Time:

June 1-4 Location:

Albuquerque, New Mexico Attendees:

T. F. Carter (FC), IEAL personn.el, Bruce Varnado (Sandia Lab)

Exxon - Status of Renewal, Handling of. Waste, and 5.

Subject:

Status of New Part 20.

Date/ Time:

June 2 - 1:30 Location:

Room 400, Willste Attendees:

W. T. Crow (FC), R. G. Page (FC), E. Y. Shum (FC),

R. Nilson and Mr. Malady (Exxon) 6.

Subject:

A Joint Meeting of ANS Standards Subcomittee 8, National Standards Committee N16, and Working Group of ANS-8 to further the development and issuance of several standards concerning Nuclear Criticality Safety.

Date/ Time:

June 2-5 St. Petersburg,) Floridan. Ketzlach (FC, R. L. Stevenson (FC Location:

Attendees:

as Representatives to ANS-8 and N-16, respectively ABSENCES OF DIRECTOR OR DEPUTY DIRECTOR Thomas F. Carter, Jr. - June 1-4, Albuquerque, New Mexico ENCLOSURE C

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Division of Safeguards Planned Meetings 1.

Subject:

DOE Non-Proliferation Workshop " International Safeguards with an Example of Application to Light Water Reactors" Date:

June'2-4, 1981 l

Location:

DOE, Washington, D. C.

ATTENDEES:

Kenneth Sanders, Speaker, SGMD i

Employees of NRC, DOE, State, ACDA, CIA, NSA 2.

Subject:

. Committee on Foreign Relations, U.S. Senate, testimony of Secretary of State Haig concerning treaty on Convention on the Physical Protection of Nuclear Material (chaired by Chas. Percy.j Date:

June 10, 1981 - 10:00 a.m.

Location:

U. S. Senate 1

Attendees:

Robert F. Burnett, NRC Representative @ ConvE" tion Ronald Bettauer, State Dept, representative l

DOE representative NOTE: No testimony required of Robert F. Burnett J

ABSENCES OF DIRECTOR AND DEPUTY DIRECTOR i

Donald R. Chapell - June 1, 1981 i

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Planned Meetings - Division of Waste Management 1.

Subject:

Meet with J. Tracy, Ertech Western to discuss technical capabilities of that firm.

Date:

June 1, 1981 Location:

Willste Bld.g., 6th floor conference room Attendees:

Edward F. Hawkins, David siefken, John Starmer,

' Derik Widmayer 2.

Subject:

Meet with Water Resources Council Date:

June 2, 1981 Location:

Water Resource Council Building, Washington, DC Attendees:

Edward F. Hawkins 3.

Subject:

Conoco on pre-op monitoring on in-situ mines.

Date:

June 3,1981 Location:

Willste Building 4.

Subject:

Utah Intn'l Shirley Basin on 40 CFR 190 nrder Date:

June 9, 1981 Location:

Willste Building 5.

Subject:

Barnwell License Meeting with state of South Carolina, Department of Public Health to discuss NRC License renewal of Barnwell license.

Location:

Columbia, SC Date:

June 10, 1981 Attendees: NRC Attendees - Edward F. Hawkins, George C. Pangburn So. Carolina - Heyward Shealy and others 6.

Subject:

Draft NRC License for the Barnwell Disposal Site Date:

June 11, 1981 Location:

Chem-Nuclear Barnwell SC Attendees:

Edward F. Hawkins, George C. Pangburn 7.

Subject:

Union Energy - New R&D Solution Mining Proje ct Date:

June 11, 1981 Location:

Willste Building j

ENCLOSURE C

7 OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending May 29, 1981 1.

The following Not'ifications of Significant Enforcement Action were dispatched during the past week:

a.

EN-81-17 Isotope Measurements Laboratories, Inc. - A Notice of Violation and a Notice of Proposed Imposition of a Civil Penalty in the amount of

$5,700 was issued to subject licensee on May 28, 1981.

This action was based on an alleged item of noncompliance relating to the licensee receiving byproduct material from client hospitals which were not authorized to manu-facture and distribute radiopharmaceuticals and in turn distributing these materials to other of the' licensee's. client hospitals.

In addition to the proposed civil penalty, an Order is being issued to the licensee to show cause*why all activities under this license should not be suspended, b.

EN-81-18 Grandview Hospital, Dayton, Ohio - A Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $1,000 will be issued to i

subject licensee on or about June 1,1981.

This action is based on alleged items of noncompliance involving failure to administer radiopharmaceuticals to patients in a manner approved by the manufacturer and the NRC.

2.

Preliminary Notifications relating to the following actions were dispatched during the past week:

a.

PNO-I 31-64 Salem Nuclear Generating Station - Unit 1 - Unit Shutdown Due to High Turbine Vibration b.

PNO-I-81-65 Westinghouse Electric Corporation - Transportation Incident c.

PNO-II-81-37 Browns Ferry 3 - Site Alert Declared Due to High Leakage Into Drywell d.

PN0-III-81-51 Zion, Unit 1 - Zion Unit 1 Safety Injection e'.

PN0-V-81-29 Palo Verde Nuclear Generating Station, Unit 2 - Construction Worker Fatality f.

PNO-V-81-30 San Onofre Nuclear Generating Station, Unit 1 - Conuminated Sand Identified on Beach g.

PN0-V-81-31 Rancho Seco Nuclear Power Plant - Arrest of Persons Employed at Rancho Seco Nuclear Generating Station for Violation of Narcotics Laws h.

PNS-I-81-09 Connecticut Yankee Atomic Power Co., Haddam Neck Unit 1 -

Haddam Neck Plant Bomb Threat i.

PNS-I-81-10 Salem Nuclear Generating Station, Units 1 & 2 - Contract Security i

Force Walkout l

ENCLOSURE D l

OFFICE OF NUCLEAR REGULATORY RESEARCH IMPORTANT EVENTS FOR THE WEEK ENDING MAY 29, 1981 A.

EXPERIttENTAL PROGRAMS BRANCH 1.

Semiscale Facility modification for the natural circulation (NC) test series is generally slightly ahead of schedule.

The vessel heater system installation is complete and work on the reflux meter is irf progress.

RES anticipates system operational testing approximately June 22 with the first NC test about a week after that, both ahead of the promised dates.

The NC test operational specification report will be issued the week of June 26.

RES received the draft report of the Westinghouse liquid level device installation and initial testing results.

Westinghouse comments, particularly in regard to any proprietary information, are to be received before release of the report.

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Review Group Meetinas 2.

There will be a Review Group Meeting to discuss the final results of the Blowdown Heat Transfer tests performed by Oak Ridge National Laboratory.

The meeting is scheduled for June 16, 1981, at the Phillips Building.

There will be a Review Group Meeting to discuss the final results and research information letter of the CREARE/BCL Refill Effects Program.

The meeting is scheduled for June 30, 1981, at the Willste Building.

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3.

BWR Refill /Reflood program Preliminary results from 300 SSTF testing have shown almost immediate CCFL breakdown in peripheral bundles and complete draining of the upper plenum within 30 seconds.

Upper plenum liquid drains immediately into the bypass (area between bundles) with no CCFL occurring at the t

top of the bypass.

1 A meeting of the Refill /Reflood Program Management Group will be held j

on June 1-2 in San Jose.

A meeting of GE and INEL staff working on BWR-TRAC qualification will be held June 4 in San Jose.

4.

BWR Full Integral Simulation Test (FIST)

A meeting of the FIST Program Management Group will be held on June 3 in San Jose.

ENCLOSURE E

. 5.

2D/3D Program The 2D/3D project managers from U.S., Germany and Japan are holding a two-day project meeting this week at the Willste Building to develop a fomal program plan,as called for by the 2D/3D International Agreement.

Any significant changes in workscope and schedule,since signing of the formal Agreement in April 1980, will be documented iy the project managers and present for approval to the 2D/3D Ste ring Comittee this June in the Federal Republic of Gemany. Mr. Robert Minogue,

- RES Director, will represent the U.S. for the 2D/3D Steering Comittee.

6.

FLECHT SEASET

. A meeting was held on May21-22, 1981, to negotiate the cost increase among contract officers and PMG members from NRC, W and EPRI. The agreement was reached that W will increase its share from 25 percent to 40 percent on the second $1M needed to complete the program, while

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the first $1M will be showed at the existing cost ratio.

Various measures to prevent future cost increases were also agreed on. The contract modification is the process pending Comission approval. A comission paper is being prepared by RES and Contracts.

B.

FUEL BEHAVIOR BRA!!CH On Wednesday, June 3, the test results from the first NRU reactor clad ballooning and rupture test MT-1 will be presented at an all day meeting in room P-110. The meeting will start at 0900.

This was a LOCA heatup and reflood reactor test with a full length 32 rod cluster of commercial enrichment fuel rods.

Rog ruptures apparentp occurred at cladding tempera-tures between 1090K (1500 F) and 1145K (1600 F) as expected, with clad ballooning of 30% - 50%.

Plans for late summer and fall follow on clad balloon tests will also be discussed.

(Contact R. Van Houten for more infoma-tion).

i On Friday, June 5 (Willste Building, lith Floor) the status of preparations for the ESSOR severe fuel damage test program will be reviewed with EEC representatives (contact A. Spano or R. Var. Houten).

C.

SE'/ERE ' ACCIDENT ASSESSMENT;BPMCH 1.

Large M_elt Facility Status as of May 26, 1981 1

The pressing of the titanium oxide charge has been initiated by LASL for the simulant test.

Furthermore, LASL has agreed to press the uranium oxide charge imediately following the simulant charge.

The susceptor support has been refined to eliminate graphite ring support and substitute peg support to further limit heat loss from the bottom of the susceptor. The themal analysis of the UO melt has been completed in its initial draft form.

2 l

ENCLOSURE E

3 2.

Summary of ACRS MARCH Review Meetino On May 21-22, 1981, the ACRS subcommittee on Class-9 Accidents conducted a review of the MARCH computer code.

The MARCH code was originally written to implement the WASH-1400 Reactor Safety Study and has been recently used in conjunction with the Zion / Indian Point work as well as a number of current reactor safety issues. The adequacy of MARCH in the evaluation of engineered safety facilities and in support of degraded-core rule making were some of the issues of concern.

The hearing opened with a presentation by NRR to outline the relationship of accident-analysis codes such as MARCH to the needs of the licensing office.

A detailed description of the code itself was presented by staff members from Battelle Columbus Laboratories where the code was originated. Two NRC-sponsored independent studies have been underway during the past year intended to assess the potential scope of applicability of MARCH, as well as to deliniate its strengths and weaknesses. One such study was carried out at BNL under NRR auspices while the other, sponsored by RES, was carried out at Sandia.

Pre-liminary reports of the findings of these two studies were presented by the staffs of these laboratories respectively. Testimony was also given by repre-sentatives from Westinghouse. EPRI, and by members of the NRC research staff.

D.

PROGRAM AND ADMINISTRATIVE SERVICES' BRANCH

~

Robert B. Minogue and RES staff members met with Messrs. G. H. Kinchin, E. Gilby, H. Teague and J. Stephenson of the UKAEA Safety and Reliability Directorate on May 28, 1981 for the annual review of the status of the safety research arrangement between the NRC and the UKAEA.

British and U.S. safety research programs of common interest were discussed against the background of UK developments relating to the introduction of the LWR into Great Britain and NRC efforts on rulemakings on siting and degraded core cooling, Class 9 accidents and quantitative safety goals. The British expressed strong. technical interest in the NRC LOFT and severe core damage pmgrams and gave indication that their participation on a substantive basis t

is being explored, Publications Issued Recently Reg. Guide 1.133, Rev.1 - Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors Reg. Guide 1.149 - Nuclear Power Plant Simulators for Use in Operating Training Draft Regulatory Guide and Value/ Impact Statement: Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material, Task FP 027-5, Proposed Rev.1 to Reg. Guide 3.1.

Comments requested by July 15, 1981.

ENCLOSURE E

0FFICE OF THE EXECUTIVE LEGAL DIRECTOR ITEMS OF INTEREST WEEK ENDING MAY 29, 1981 William B. McGuire Nuclear Station, Units 1 and 2 (reopened OL proceeding)

On May 26,1981, the presiding ASLB issued a Supplemental Initial Decision with respect to four intervenor contentions relating to hydrogen control.

The ASLB concluded that there was reasonable assurance that in the event of a TMI type accident at McGuire substantial quantities of hydrogen will not be generated. Accordingly, the ASLB ordered that its stay of the Initial Decision in this proceeding be lifted and authorized the issuance of full term, full power operating licenses.

William B. McGuire Nuclear Station, Units 1 and 2 (reopened OL proceeding)

On May 28,1981, the Commission issued an Order in which it applied its new Appendix B to 10 CFR Part 2 procedures to the Initial Decision issued in this proceeding on May 26, 1981.

Under the procedures the Commission will complete its review of effectiveness of the ASLB decision within 30 days afte-cc.nsidering any comments filed by the parties.

Turkey Point Nuclear Generating, Units 3 and 4 (Amendment of OL permit steam generator repairs)

On May 28,1981, the presiding ASLB issued a Memorandum and Order granting i

summary disposition of all contentions of intervenor and canceling the evidentiary hearing.

The ASLB directed the parties to file with it detailed infonnation regarding the handling, storage, transportation and disposition to

, be made of low level solid waste that may be produced as a result of the proposed steam generator repairs and to state their positions as to whether i

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the ASLB should take any action regarding the solid waste including imposition of license conditions.

l ENCLOSURE F

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MAY 29, 1981 RERO Course For anternational Emergency Response Employees Notification of the second NRC-sponsored international RERO training course has been sent to contacts in the countries with which we have Exchange Arrangements. The course will be held from September 30 through October 9, 1981, in Las Vegas, Nevada, and at the Department of Energy's Nevada Dst Site, 80 miles north of the city. The NRC will be reimbursed for the costs of the course by the foreign agencies sending participants.

Foreign Visits to NRC On Tudsday Mr. R. Dragulev, a Computer Specialist with the IAEA, met with F. Hebdon, AE00, and C. Montserrate, MPA, to discuss the establishment of a computerized power reactor infomation system comprising power reactorsgeneral data and power reactor operating 4xperience. -

On Tuesday Mr. Kim of the Korea Advanced Energy Research Institute met with D. Chenier of IP to discuss the exchange of infomation between NRC and KAERI.

On Wednesday Mr. M. Gregoric, a Research Assistant with the "ugoslav Josef Stefan Institute, met with R. Senseney, IP, and B. Sheron, RSB/NRR, to discuss post-TMI requirements for Westinghouse PWRs.

On Wednesday, Mr. Miyabayashi of the Japanese Embassy and Mr. Kamimura of the Overseas Electrical Survey Institute met with J. Lafleur, D. Chenier, W. Lavine, and R. Sensency, all of IP, to discuss incoming' reports on the Tsuruga incident.

Review of Franklin Research Center Report The Franklin Research Center has completed its report entitled An Analysis of U.S.

Nuclear Health and Safety Infomation Dissemination to Selected Foreign Countries.

This report is the result of a contract study approved by the Comission as one of the recomendations of SECY-78-365, " Health and Safety Considerations in NRC Reactor Export Licensing and Nuclear Assistance Programs." Copies of the r.eport are available as NUREG/CR-1986. The study was an analysis of information

. dissemination to six countries which are developing a regulatory structure to control accelerating comercial nuclear power programs.

The general finding of the report was that there is a widely shared opinion among the regulatory and foreign safety personnel who were interviewed that U.S.

industrial firms, the NRC, and comercial services in the U.S. do a very good job of supplying safety information.

In response to several of the report recom-mendations, IP has decided to prepare an informational outline or guide to be distributed to all present and future Arrangement Administrators. The guide will i

explain the various types of NRC infomation supplied under the terms of the Bilateral Arrangements and will offer advice on key ~ problem areas. Additionally, i

IP will continue to work actively with Administrators, especially within the Priority I countries and in those countries that are new to the Arrangement relation-ship, to ensure that we continue to meet the Comission's health and safety objectives with regard to these countries.

ENCLOSURE G

.., l OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MAY 29, 1981 The State of Washington is well along in its efforts to amend its Agreement with NRC to permit continued regulation of uranium mills in accordance with the Uranium Mill Tailings Radiation Control Act.

Representatives from OSP (State Agreements), ELD, and NMSS (Uranium Recovery) will meet with Washington representatives on June 3,1981 in Olympia to discuss the State's proposed uranium mill regulatory program.

Washington presently regulates two operating uranium mills.

The Director, OSP and representatives from NMSS (Waste Management), ELD and OGC attended a meeting of the New Mexico Radiation Technical Advisory Counc0 on May 28, 1981 in Sante Fe, NM.

The Council was considering New Mexico uranium milling and tailings regulations which are based on NRC regulations.

NRC representatives were present to discuss implementation of the Uranium Mill Tailings Radiation Control Act by New Mexico and to explain the technical basis of NRC regulations.

New Mexico is seeking an amended agreement to permit tne state to cor.tinue to regulate uranium milling and tailings.

j On May 27,1981 W. B. Menczer, RSLO, Region III was in Zion, Illinois meeting with the Zion City Attorney and detectives from the Zion Police Department regarding alleged activities of Zion Station employees.

He was accompanied by the Region III Enforcement and Investigation Staff Director.

On May 28, 1981, Mr. Menczer was in Jefferson City, Missouri meeting with officials of the Missouri Department of Natural Resources and the U.S. Department of Energy to discuss state and federal actions regarding radioactivity contaminated sites in Missouri.

~

The results of the second year of monitoring transportation of radioactive material in Georgia were publisehd as NUREG/CR-2033. This study was performed by the Georgia Institute of Technology and the Georgia Department of Human Resources under NRC/ DOT contract, and covers the period from October 1978 through September 1979.

Robert Wood presented a paper before the Iowa State Regulatory Conference on May 21,1981 on financial assurance for decommissioning.

P

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l ENCLOSURE H i

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OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS Ittms of Interest WEEK ENDING MAY 29, 1981 i

I Alternative Equipment for the Document Control System l

At the request of DEC0, prepared brief analysis of an alternative to the proposal that NRC buy TERA Corporation's computers and associated equipurent.

Caseload Forecast l

t Briefed DED0 on forecast to be used in FY 83 budget review.

e Authorization Bill Analyzed S.1207 which was reported from the Senate Committee on Environment and Public Works, for action items and requirements I

stemming from major provisions. Bill spans FY 82 and FY 83.

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t ENCLOSURE I

e' OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA s

ITEMS OF INTEREST WEEK ENDING MAY 29, 1981 Cooperative Arrangement with INP0/NSAC On May 26,1981, the E00 signed the proposed Memorandum of Agreement with INP0/NSAC on a cooperative relationship for the collection and feedback of operational data. After agreement by the other parties, a meeting with INP0/NSAC will be proposed in order to establish working procedures for implementing the agreement's provisions.

FY 1982 Activities at the Nuclear Safety Information Center Discussions were held with the Nuclear Safety Information Center (NSIC) regarding the FY 1982 activities to be funded by AE00. The discussions centered on obtaining a more focused effort on operational data, including analysis of selected trends or situations, initiation of reviews associated with experience from Ft. St. Vrain, and the development of a suitable publication devoted to the feedback of operational events and analysis.

The current status of the Sequence Coding a,nd Search Procedure was also discussed and the future activities defined.

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ENCLOSURE K

o,; *,'

ITEMS APPROVED BY THE COPHISSION - WEEK ENDING MAY 29, 1981 A.

SECY-81-261 - NRC REGULATION OF HIGHLY ENRICHED URANIUM OPERATIONS AT NUCLEAR FACILITY, ERWIN, TENNESSEE (NFS-ERWIN). Memo SECY to Dircks, dtd 5/27/81.

This is to advise you that the Commission (with three commissioners; approving and Commissioner Gilinsky disapproving) has approved l

your recommendation to take no further NRC action at this time i

other than continued vigorous inspection and enforcement as l

well as staff monitoring of progress and results.

In connection with his disapproval, Commissioner Gilinsky provided the following comment:

"I continue to believe this facility should be transferred to DOE oversight."

j The Office of Nuclear Material Safety and Safeguards was informed of this action by telephone on May 27, 1981.

[

l B.

STAFF REQUIREMENTS - AFFIRMATION SESSION 81-19, 4:00 P.M., THURSDAY, MAY 21, 1981, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE).

l Memo Chilk to Bickwit, dtd 5/27/81.

[

I.

SECY-81-276 - PETITIONS FOR STAY OF THE URANIUM MILL LICENSING REQUIREMENTS The Comission, by a vote of 4-0, approved a Memorandsn and Order denying the requests for a stay by New Mexico and the operators of three uranium mills.

(0GC) l (Subsequently, the Secretary signed the Order.)

II.

SECY-81-270 - CONFORMING CHANGE TO EMERGENCY PLANNING RULE The Cornission, by a vote of 4-0, approvbd a confornino change to the emergency, planning rule, l_0 CFR_50.54(5).

(0GC}

(Subsequently, the Federal Register Notice was signed by the S cretary.)

C.

SECY-81-322 - APPROVAL OF PROPOSED LICENSE TO EXPORT HEU OR U-233 TO CANADA (LICENSE NO. XSNM01805, SECY-81-289).

Memo SECY to Dircks, dtd 5/27/81.

This is to advise you that the Commissioners have reviewed the subject license to the Department of Energy.

The Commission (with all Commissioners approving) has accepted your recommendation to export to Canada 4.4 kilograms of uranium, enriched to 97.6 percent, in the form of uranium oxide fuel rods.

The Office of International Programs was informed of this action by telephone on May 27, 1981.

j ENCLOSURE M

D.

STAFF REQUIREMENTS - BRIEFING ON SECY-81-267 - 10 CFR 60, DISPOSAL OF HIGH-l LEVEL WASTES In GE0 LOGIC REPOSITORIES: TECHNICAL CRITERI A,10:05 A.M., WED-NESDAY, MAY 20, 1981, COMMISSIONERS' CONFERENCE RCOM, D.C. 0FFICE (OPEN TO PUBLIC ATTENDANCE). Memo SECY to Dircks, dtd 5/28/81.

The staff continued their briefing of the Comission on the proposed rule on i

Technical Criteria fer High-Level Waste Repositories.

[

The Comission asked the staff to review the definition of hig_h. level waste facility and the footnote on page.20 of the proposed rule to make sure that the definitions are consistent. The staff should also include in the State-ment of Consideration a review of the type of facility to be covered by the rule.

Chairman Hendrie requested the Staff to review the requirements in Subpart E to determine if some of the language (i.e., pg. 33, (2)(i) "...the waste package will contain all radionuclides for the first 1,000 years...") places an impossible standard of proof upon DOE.

The requirement should be a reasonable assurance (or other similar language) that all radionuclides will be contained.

The staff should provide a recommendation as to how this idea can be expressed in the rule.

Chairman Hendrie requested the staff to review their intent with regard to calculation of doses to members of the public and report back to the Commission with a recommendation as to whether "...and will not result in significant doses to any individual" can be eliminated from lines 7 and 8 of paragraph (3)(11) on page 34. The staff should also review the division of responsi-bilities between EPA and NRC with respect to dose standards to see if the NRC has the authority to act in this area.

Commissioner Bradford indicated he would prepare a remorandum to the other Commissioners to cover various points he wanted -to raise.

(This was subsequently issued on May 28,'1981.)

Comissioner Ahearne asked the staff to consider asking for public comment on how the EPA Standards for doses to the public from the HLW repository should be treated in the NRC rule.

The Comission reached no decision at the meeting. The Chairman indicated that further consideration would be given to the proposed rule at a meeting at a later date.

(Subsequently, a meeting was scheduled for Tuesday, June 2,1981.)

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ENCLOSURE M

E.

STAFF REQUIREMENTS - BRIEFING ON SECY-81-240 - DRAFT NUREG REPORTS 0771 'AND 0772 RELATING TO ACCIDENT SOURCE TERM ASSUMPTIONS, 2:05 P.M., THURSDAY, MAY 21, 1981, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE).

Memo SECY to Dircks, dtd 5/29/81.

i The Commission was briefed by staff on draft reports on accident source l

tern assumptions.

f those l

Commissioner Ahearne requested a response from staff'to id'entify(Append accident sequences and associated probabilities in Category III l

NUREG-0772) with sufficiently high probability that continue to dominate.

(RES)

(SECYSuspense:

6/15/81)

Chairman Hendrie recommended that staff also seek comments from knowledgeab'.e individuals outside NRC; sources would include the National Academy of Sciences and the American Institute of Chemical Engineers.

(RES)

(SECY Suspense: To Be Determined) l I

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ENCLOSURE M

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