ML19208B592
| ML19208B592 | |
| Person / Time | |
|---|---|
| Issue date: | 08/17/1979 |
| From: | Hendrie J NRC COMMISSION (OCM) |
| To: | Demlow D MICHIGAN, STATE OF |
| References | |
| NUDOCS 7909210046 | |
| Download: ML19208B592 (3) | |
Text
/
o UNITED STATES E
,( rt NUCLEAR REGULATORY COMMISSION 0 8 "'"
(g WASHINGTON, D. C. 20555 CO
+#
August 17, 1979 CHAIRMAN Mr. Daniel Demlow, Chairman Michigan Public Service Commission 6545 Mercantile Way P. O. Box 30221 Lansing, Michigan 48909
Dear Mr. Demlow:
We are pleased to respond to your letter of April 9, IF79 concerning those activities and investigations of the Three Mile Island accident which may affect nuclear power plants in Michigan.
We apologize for the delay in answering your questions. As you can appreciate, we have been occupied with Three Mile Island during the past few months.
You req: tested information on the following:
1.
sesults of NRC activities in determining whether 'etere is any significant potential for any such accident to occ;ur in Michigan.
Answer There are four operating nuclear power plants in Michigan. One of these, Big Rock Point, is a boiling water reactor and is not v:ulnerable to the same accident as that which occarred at Three Mile Island. The other three are pressurized water reactor plants. Two of these, Cook I' and Cook 2 are PWR plants designed by Westinghouse, while the other, Palisades, is a PWR plant oesigned by Combustion Engineering.
As you know, Three Mile Island Unit 2 (TMI-2) is also a. PWR plant but was designed by Babcock and Wilcox. The NRC is reviewing Vestinghouse and Com-bustion Engineering PWR designs to assess the relative reactor system dynamic behavior that these designs would be subjected to as a result of an accident similar to the type which occurred at TMI-2, that is, a complete loss of main feedwater. The NRC initiated action in this area with the issuance of two Bulletins which requested that licensees operating Westing-house or Combustion Engineering plants take certain specific action.
Copies of these bulletins are attached for your information.
In addition, the staff has been meeting with representatives of both firTns to discuss related analyses, tests, and plant features dealing with small break loss of coolant accidents, anticipated transients, operator training arid procedures, and reliability of the auxiliary feedwater systems includirtg associated controls and natural circulation capability.
The results of these staff reviews will be summarized in reports which will be made available to the public.
9009210 O g78261
Mr. Daniel Demlow 2.
NRC actions that might affect availability of nuclear power plants presently operating in this state (Michigan).
Answer At present, we do not anticipate changes or delays which would significantly impact upon'the availability of nuclear power plants in Michigan.
3.
NRC or other actions or plans that might affect the design or licensing ability of nuclear power plants presently under design or construction in this state.
Answer The Commission is engaged in a number of studies related to identifying changes that will be needed to prevent accidents like TMI-2.
A focal point for these studies is the Lessons Learned Task Force.
A report by this Task Force was recently completed and a copy has been attached for your information.
4.
Emergency activities surrounding the Three Mile incident that might be useful to our state during our present reexamination of Michigan's nuclear emergency planning.
Answer There are two task forces in NRC that are reviewing Emergency Plans in light of the Three Mile Island accident.
NRC met with officials of the State of Pennsylvania on July 11, 1979 to discuss state and local government activities during and after the Three Mile accident.
Some topics covered included warning, communications and protective responses that state and local govern-ments participated in.
A report will be prepared by the NRC and a copy will be transmitted to you concerning this meeting.
In addition, NRC staff members met on July 26 and 27 with Michigan officials from the Department of Public Health and the State police to discuss details of emergency plans.
Our Office of State Programs will continue to provide further guidance in this area, as necessary.
I would also like to point out that the Commission has recently published an Advance Notice of Rulemaking regarding the adoption of additional regula-tions which will establish, as conditions of power reactor operation, increased emergency readiness for public protection in the vicinity of nuclear power reactors on the part of both the licensee and the local and state authorities.
A copy of this Notice is enclosed.
sF
Mr. Daniel Demlow 5.
electric power that any of the activities reference on in-state power plants.
Answer by the NRC since many of the changes are not yet ide as a result of the recomendations of the NRC's i.essons Learned Task ForceT the Presidential Comission's Inquiry, the NRC's Inquiry and the other reviews of the TMI-2 accident.
those operating plants which have been ordered to be shut d TMI-2 accicant (none in Michigan), we do not know the masnitude of t e
that will be incurred at other facilities.
I trust that the above information is responsive to your needs Sincerely,
[.
A f m.. Sr
_/h nY' Joseph M. HIdrie O d ~,
Enclosures:
l.
Bulletins
/
c' 2.
NUMG-0578 3.
Advance Notice of Rulemaking
l UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No.79-06A Date:
April 14,1979 Page 1 of 5 REVIEW OF OPERATIONAL ERRORS AND SYSTEM MISALIGINENTS IDENTIFIED DURING THE THREE MILE ISLAND INCIDENT Description of Circumstances:
IE Bulletin 79-06 identified actions to be taken by the licensees of all pressurized water power reactors (except Babcock & Wilcox reactors) as a result of the Three Mile Island Unit 2 incident.
This Bulletin clarifies the actions of Bulletin 79-06 for reactors designed by Westinghouse, and the response to this bulletin will eliminate the need to respond to Bulletin 79-06.
Actions to be taken by Licensees:
For all Westinghouse pressurized water reactor facilities with an operating license (the actions specified below replace those identified in IE Bulletin 79-06 on an item by item basis):
1.
Review the desc.c iption of circumstances described in Enclosure 1 of IE Bulletin 79-05 and the preliminary chronology of the TMI-2 3/28/79 accident included in Enclosure 1 to IE Bulletin 79-05A.
a.
This review should be directed toward understanding: (1) the extreme seriousness and consequences of the simultaneous blocking of both auxiliary feedwater trains at the Three Mile Island Unit 2 plant and other actions taken during the early phases of the accident; (2) the apparent operational errors which led to the eventual core damage; (3) that the potential exists, under certain accident or transient conditions, to have a water le,el in the pressurizer simultaneously with the reactor vessel not full of water; and (4) the necessity to systematically analyze plant conditions and parameters and take appropriate corrective action.
i; b
F b.
Operational personnel should be instructed to: (1) not override automatic action of engineered safety features unless continued operation of engineered safety features will result in unsafe plant conditions (see Section 7a.); and (2) not make operational decisions based solely on a single plant parameter indication when one or more confirmatory indications are available.
'/fh U5QIS i
April 14,1979 Page 2 of 5 c.
All licensed operators and plant management and supervisors with operational responsibilities shall participate in this review and such participation shall be documerrted in plant records.
2.
Review the actions required by your operating procedures for coping with transients and accidents, with particular attention to:
a.
Recognition of the possibility of forming voics in the primary coolant system large enough to compromise the core cooling capability, especially natural circulation capability.
b.
Operator action required to prevent the formation of such voids.
c.
Operator action requiriit to enhance core coolirag in the event such voids are fonned.
(e.g., remote venting) 3.
For your facilities that use pressurizer water level coincident pressurizer pressure for automatic initiation of safety injection into the reactor coolant system, trip the low pressarizer level setpoint bistables such that, when the pressurizer pressure reaches the low setpoint, safety injection would be initiated regardless of the pr';ssurizer level.
In addition, instruct operators to manually initiate sa'ety injection when the cressurizer pressure indication reaches the actuation setpoint whether or not the level indication has dropped to the actuation setpoint.
4.
Review the containment isolation initiation design and procedures, and prepare and implement all changes necessary to permit contain-ment isolation whether manual or automatic, of all lines whose isolation does not degrade needed safety feateres or cooling capa-bility, upon automatic initiation of safety injection.
5.
For facilities for which the auxiliary feedwater system is not automatically initiated, prepare and implement imediately proce-dures which require the stationing of an individual (with no other assigned concurrent duties and in direct and continuous comunica-tion with the control room) to promptly initiate adequate auxiliary feeu
'.er to the steam generator (s) for those transients or acci-dents the consequences of which can be limited by such action.
S'/S'dG5
April 14, 1979 L
Page 3 of 5 6.
For your facilities, prepare and implement imediately procedures which:
Identify those plant indications (such as valve discharge a.
piping temperature, valve position indication, or valve discharge relief tank temperature or pressure indication) which plant operators may utilize to detemine that pres-surizer power operated relief valve (s) are open, and b.
Direct the plant operators to manually close the power operated relief block valve (s) when reactor coolant system pressure is reduced to below the set point for normal automatic closure of the power operated relief valve (s) and the valve (s) remain stuck open.
7.
Review the action directed by the operating procedures and training instructions to ensure that:
Operators do not override autoratic actions of engineered a.
safety features, unless continued operation of engineered safety features will result in unsafe plant conditions.
For example, if continued operation of engineered safety features would threaten reactor vessel integrity then the HPI should be secured (as noted in b(2) below).
b.
Operating procedures currently, or are revised to, specify that if the high pressure injection (HPI) system has been automatically actuated because of low pressure condition, it must remain in operation until either:
(1)
Both low pressure injection (LPI) pumps are in operation and flowing for 20 minutes or longer; at a rate which would assure stable plant behavior; or (2)
The HPI sys'.em has been in operation for 20 minutes, and all hot and ;old leg temperatures are at least 50 degrees below the saturation temperature for the existing RCS pressure.
If 50 degress subcooling cannot be maintained af ter HPI cutoff, the HPI shall be reactivated.
The degree of subcooling beyond 50 degrees F and the length of time HPI is in operation shall be limited by the pressure / temperature considerations for the vessel integrity.
97S266
April 14,1979 Page 4 of '-5 c.
Operating procedures currently, or are revised to, specify that in the event of HPI initiation with reactor coolant pumps (RCP) operating, at least one RCP shall remain operating for two loop plants and at least two RCPs shall remain operating for 3 or 4 loop plants as long as the pump (s) is providing forced flow.
d.
Operators are provided additional infomation and instructions to not rely upon pressurizer level indication alone, but to also examine pressurizer pressure and other plant parameter indications in evaluating plant conditions, e.g., water, inventory in the reactor primary system.
8.
Review all safety-related valve positions, positioning requirements and positive controls to assure that valves remain positioned (open or closed) in a manner to ensure the proper operaticn of engineered safety features.
Also review related procedures, such as those for maintenance, testing, plant and system startup, and supervisory periodic (e.g., daily / shift checks,) surveillance to ensure that such valves are returned to their correct positions following necessary manipulations and are maintained in their proper posi-tions during all operational modes.
9.
Review your operating modes and procedures for all systems designed to transfer potentially radioactive gases and liquias out of the primary containment to assure that undesired pumping, venting or other release of radioactive liquids and gases will not occur inadvertently.
In particular, ensure that such an occurrence would not be caused by the resetting of engineered safety features insrumentation.
List all such systems and indicate:
a.
Whether interlocks exist to prevent transfer when high radiation indication exists, and b.
Whether such systems are isolated by the containment isolatSn signal.
c.
The basis on which continued operability of the above features is assured.
10.
Review and modify as necessary your maintenance and test procedures to ensure that they require:
a.
Verification, by test or inspection, of the operability of redundant safety-related systems prior to the removal of any safety-related system from service.
April 14, 1979 Page 5 of 5 I
b.
Verification of the operability of all safety-related systems when they are returned to service following maintenance or testing.
c.
Explicit notification of involved reactor operational personnel whenever a safety-related system is removed from and returned to service.
11 Review 3 cur prompt reporting procedures for NRC notification to assure.nat NRC is notified within one hour of the time the reactor is not in a controlled or expected condition of operation.
- Further, at that time an open continuous communication channel shall be established and maintained with NRC.
12.
Review operating modes and procedures to deal with significant amounts of hydrogen gas that may be generated during a transient or other accident that would either remain inside the primary system or be released to the containment.
13.
Propose changes, as required, to those technical specifications which must be modified as a result of your inplementing the above items.
For all light water reactor facilities designed by Westinghouse with an operating license, respond to Items 1-12 within 10 days of the receipt of this Bulletin.
Respond to item 13 (Technical Specification Change proposals) in 30 days.
Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C.
20555.
For all other power reactors with an operating license er construction permit, this Bulletin is for information purposes and no written response is required.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
Enclosure:
List of IE Bulletins Issued in Last Twelve Months 078268 m
IE Bulletin No.79-06A Date: April 14,1979 Page 1 of 4 LISTING OF IT BULLETINS ISSUED IN LAST WELVE MONTHS Bulletin Su! ject Date Issued Issued To No.
78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Braaker Facilities with an Auxiliary Contact Operating License Mechanism - General (CL) or Construction Electric Model CR105X Permit (CP) 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78 Ali Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority I Material Licensees 78-08 Radiation Levels from 6/12/78 All Power, Test and Fuel Element Transfer Research Reactor Tubes Facilities with an OL having Fuel Element Transfer Tubes 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL (for action)
Closures or CP (for information) 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP Spring Coils pe
April 14,1979
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Page 2 of 4 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued To No.
78-11 Examination of Mark I 7/24/78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action:
Paach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee. All other BWR Power Reactor Facilities with an OL for information 78-12 Atypical Weld Mat frial-9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures In Source Heads 10/27/78 All General and of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 7050B, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B Ga'Jges 78-14 Deterioration of Buna-N 12/19/78 All GE BWR Faci-Components :.1 ASCO lities with an OL Solenoids (for action), and all other Power Reactor Facilities with an OL or CP (for information) 378270
April 14,1979 Page 3 of 4 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED)
Bulletin Subject Cate Issued Issued to No.
79-01 Environmental Qualifica-2/8/79 All Power Reactor tion of Class IE Equipment Facilities with an OL, except the 11 Systematic Evaluation Frogram Plants (for action), and all ether Power Reactor Facilities with an C'l or CP (for in-fbnrati on) 79-02 Pipe Support Base Plate 3/8/79 All 'ower Reactor Design Using Concrete Facilities with Expansion Anchor Bolts am OL or CP 79-03 Longitudinal Weld Defects 3/12/79 A?il Power Reactor in ASME SA-312 Type Facilities with 304 Stainless Steel Pipe aza OL or CP Spools Manufactured by Youngstown Welding and engineering Company 79-04 Incorrect Weights for 3/30/79 All Power Reactor saing Check Vaives rac11itles with an Manufactured by Velan
- 01. or CP Engineer ing Corpocation 79-05 Nuclear Incident at 4/1/79 Ail Babcock and Three Mile Island
'dilcox Power Faac:or Facilities with an OL, Except Three Mile Island I and 2 (For Action.),
amd All Other Power Reactor Facilities With an OL or CP (For Infortration) 79-C5A Nuclear Incident at 4/5/79 Same as 79-05 Three Mile Island -
Supplement 378' 71 J
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Date: April 14,1979 Page 4 of 4 LISTING 0F IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTIr4UED)
Bulletin Subject Date Issued Issued to No.
79-06 Review of Operational 4/11/79 All Pressurized Errors and System Mis-Water Power Reactor alignments Identified Facilities with an During the Three Mile OL Except B&W Incident Facilities (For Action), All Other Power Reactor Facilities With an OL or CP (For Infomation) 9TS272
t:
I l
ENCLOSURE 2 i
LIST OF LICENSEES RECEIVING IE BULLETIN NO.79-06A FOR ACTION Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN:
Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Edison Company of Docket: No. 50-247 New York, Inc.
ATTN: Mr. W. J. Cahill, Jr.
Vice President 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 ATTN:
Mr. C. N. Dunn Vice President Operations Division 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN:
Mr. J. P. Bayne Resident Manager P. O. Box 215 Buchanan, New York 10511 Public Service Electric and Gas Company Docket No. 50-272 ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Rochester Gas and Electric Company Docket No. 50-244 ATTN:
Mr. Leon D. White, Jr.
Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 378273
1-2 Yankee Atomic Electric Company Docket No. 50-29 ATTN: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581
- .e..
378274
i.
ENCLOSURE 3 SAMPLE LETTER (FOR ACTION)
Docket No(s).
Cate:
NAME AND ADDRESS Gentlemen:
Enclosed is IE Bulletin No.79-06A, which requires actic:n by you with regard to your Westinghouse designed pressurized water reactor facility (ies) with an operating license.
Based on our current understanding of the Three Mile Island accident sequence, and discussion with the designer of your presnarized water reactor, we have reason to believe that pressurizer leve'l indication in your facility may not provide reliable information regarding level in the reactor coolant system under certain transient or accident conditions.
You should immediately instruct your opera:-ing personnel accordingly.
In addition, you should consider this posr5bility in responding to the enclosed bulletin.
Should you have any questions regarding this bulletin or the' actions required by you, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosure:
IE Bulletin No.79-06A with Enclosures 378275
i ENCLOSURE 4 LIST OF LICENSEES AND CONSTRUCTION PERMIT HOLDERS RECEIVING IE BULLETIN 79-06A FOR INFORMATION Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN: Mr. A. E. Lundvall, Jr.
50-318 Vice President - Supply P. O. Box 1475 m
Baltimore, Maryland 21203 Boston Edison Company M/C Nuclear Docket No. 50-293 ATTN:
Mr. G. Carl Andognini, Manager Nuclear Operations Department 800 Boylston Street Boston, Massachusetts 02199 Consolidated Edison Company of Docket No. 50-03 New York, Inc.
ATTN:
Mr. W. J. Cahill, Jr.
Vice President 4 Irving Place New York, New York 10003 Jersey Central Power and Light Company Docket No. 50-219 ATTN; Mr. Ivan R. Finfrock, Jr.
v' ice Presi: lent Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Maine Yankee Atomic Power Company Docket No. 50-309 ATTN: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581
. Niagara Mohawk Power Corporation Docket No. 50-220 ATTN:
Mr. R. R. Schneider Vice President Electric Operations i
300 Erie Boulevard West Syracuse, New York 13202 978'476
2 Northeast Nuclear Energy Company Docket Nos. 50-336 ATTN: Mr. W. G. Counsil 50-245 Vice President - Nuclear 50-423 Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN: Mr. S. L. Daltroff 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket Tha. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. J. D. Leonard, Jr.
Resident Manager P. O. Box 41 Lycoming, New York 13093 Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Duquesne Light Company Docket No. 50-412 ATTN: Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power & Light Company Docket No. 50-363 ATTN: Mr. I. R. Finfrock, Jr.
Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 a
p Long Island Lighting Company Docket Nos. 50-322 F
ATTN:
Mr. Andrew W. Wofford 50-516 Vice President 50-517 175 East Old Country Road Hicksville, New York 11801 k
3 Niagara Mohawk Power Corporation Docket No. 50-410 ATTN: Mr. G. K. Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, New York 13202 Pennsylvania. Power & Light Company Docket Nos. 50-387 ATTN: Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction (N-4) 2 North Ninth Street Allentown, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352 ATTN: Mr. V. S. Boyer 50-353 Vice President Engineering and Research 2301 Market Str,!t Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50-354 ATTN:
Mr. T. J. Partin 50-355 Vice President 50-311 Engineering and Construction 80 Park Place Newark, New Jersey 07101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN:
Mr. W. C. Tallman 50-444 President 1000 Elm Street Manchester, New Hampshire 03105 Rochester Gas & Electric Corporation Docket No. 50-485 ATTN:
Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, New York 14649 Metropolitan Edison Company Docket No. 50-289 ATTN:
Mr. J. G. Herbein Vice President - Generation P. O. Box 542 Reading, Pennsylvania 19540 978278
ENCLOSURE 5 SAMPLE LETTER (FOR INFORMATION)
Docket No(s).
Date NAME AND ADDRESS Gentlemen:
The enclosed Bulletin 79-06A is forwarded to you for information.
No written response is required.
If you desire addittor.al informaticg,
regarding this matter, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosure:
Bulletin No.79-06A with Enclosures
\\
t 9
b 1 '
s 978'479 u
l UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-05 Date: April 1,1979 Page 1 of 3 NUCLEAR INCIDENT AT THREE MILE ISLAND Description of Circumstances:
On March 28, 1979 the Three Mile Island Nuclear Power Plant, Unit 2 experienced core damage which resulted from a <ssries of events which were initiated by a loss of feedwater transient. Several aspects of the incideit may have general applicability in addition to apparent generic applicability at operating Babcock and Wilcox reactors.
This bulletin is provided to infom you of the nuclear incident and to recuest certain actions.
Actions To Be Taken By Licensees:
(Although the specific causes have not been determined for individual sequences in the Three Mile Island event, some of the following may have contrbuted).
For Babcock and Wilcox pressurized water reactor facilities with an operating license:
1.
Review the description (Enclosure 1) of the initiating events and subsequent course of the incident. Also review the evaluation by the NRC staff of a postulated severe feedwater transient related co'Jabcock and Wilcox PWRs as described in Enclosure 2.
These reviews should be directed at assessing the adequacy of your reactor systems to safely sustain ecoldown transients such as these.
2.
Review any transients of a similar nature which have occurred at your facility and determine whether any significant deviations from expected performance occurred.
If any significant deviations are found, provide the details and an analysis of the significance and any corrective actions taken.
This material may be identified by reference if previously submitted to the NRC.
378280 s
7fmm7
IE Bulletin No. 79-05 Date:
April 1, 1979 Page 2 of 2 3.
Review the actions required by your operating procedures for coping with transients. The items that should be addressed include:
a.
Recognition of the ;,ossibility of foming voids in the primary coolant system large enough to compromise the core cooling capability.
b.
Operator action required to prevent the fomation of such voids.
c.
Operator action required to ensure continued core cooling in the event that such voids are fomed; 4.
Review the actions requested by the operating procedures and the training instructions to assure that operators do not override automatic actions of engineered safety features without sufficient cause for doing so.
5.
Review all. safety related valve positions and positioning require-ments to assure that engineered safety features and related equip-ment such as the auxiliary feedwater system, can perform their intended functions. Also review related procedures, such as those for maintenance and testing, to assure that such valves are returned to their correct positions following necessary manipulations.
6.
Review your operating modes and procedures for all systems designed to transfer potentially radioactive gases and liquids out of the containment to assure that undesired pumping of radioactive liquids and gases will not occur inadvertently.
In particular assure that such an occurrence would not be caused by the resetting of engineered safety features instrumentation.
List all such systems and indicate:
a.
Whether intericcks exist to prevent transfer when high radiation indication exists and, p
b.
Whether such systems are isolated by the containment isolation
['
signal.
7 Review your prompt reporting procedures for NRC notification to assure very early notification of serious events.
L i
978281 i
i i
IE Bulletin No. 79-05 Date: April 1,1979 Page 3 of 3 The detailed results of these reviews shall be submitted writhin ten (10) days of the receipt of this Bulletin.
Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C.
20555.
For all other operating reactors or reactors under constru. tion, this Bulletin is for information purposes and no report is requested.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80. Approval was given under a blanket clearance specifically for identified generic problems.
Enclosures:
1.
Preliminary Notifications Three Mile Island -
PNO-57 and 67A, B, C, D, E,F,G 2.
Evaluation of Feedwater Transients w/ attachment 3.
List of IE Bulletins issued in last 12 months 378262 i
2 IE Bulletin 79 05 ~ ^
~
PN No. 79-67 and Subsequent Revisions PRELIMINARY NOTIFICATION March 28, 1979 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL CCCURRENCE--?NO-79-67 This oreliminarv notification constitutes EARLY notice of event of POSSIBLE safety or ouclic interes si en ' <.ance.
ine 1nfermation
~
cresentec 1s as initially received witncut verification or evaluation anc is easically all tnat is known oy IE staff an :nis care.
Facility:
Three Mile Island Unit 2 Middletown, Pennsylvania (Docket No 50-320)
)
Subject:
RF. ACTOR SCRM FOLLCWED BY A SAr:.d INJECTION AT TriREE MILE 8
ISLAND - UNIT 2 sj Tne licensee notified Regicn I at approximately 7:45 AM of an incident at Tnree Mile Islar.a Unit 2 (TMI-2) which occurred a: ?croxi=stely 4:00 AM at 96% pcwer wnen the secondary feed pumps tripced due te a feedwater polishing system problem.
This resulted in a turbine trip and subse-quent reactor trip cn High Reactor Ccolant Pressure.
A ce=binct.icn of Feed Pump Operation and Pressurizer Relief - Steam Genera:=r relief valve operation caused a Reactor Ccolant System (RCS) c::cidown.
At 1500 psig, Emergency safeguards Actuation occurred.
All ECCS c=cconents started and operated properly.
Water level increased in the Pressurizer and Safety Injection was secured manually acproximately 5 :sinutes after actuation.
It was subsequently resumed.
The Reactor Ccolant Pum=s were secured when icw net positive sucticn head limits were approached.
About 7:00 AM, high activity was noted in the RCS c::alant Sample Lines (aperoximately 6C0 mr/hr contact readings).
A Site Emergeecy was then declared.
At approximately 7:30 AM, a General Smergency was declared based on High Radiation levels in the React::r Suilding.
At 8:30 AM site boundary radiation levels were reper ed to not be significant (less than 1 mr/hr). 'The source of activity was stated to be" failed f'uel as a result of the transient, and due to a known preyfoud"irimary t= seccndary leak in Steam Generator B.
The Region I Incident Respense Center was activated ad 8:10 AM and direct c::munications with the licensee and IE:Headcuarters was estab-lished.
The Response Team was dispatched at 8:45 AM and arrived at the sita at 10:05 AM.
At 10:45 A'i the Reactor Ccolant System Pressure was being held at 1950 psig with te=cerature at 2200F in the cold leg.
By 10:45 AM, radiatien levels of 3 =r/hr had been detected SCO yards offsite.
1 CCNTINUED 378263
Page 2 Ccntinued March 23,1979 FNO-79-67 There is significant media interest at the present ti:ne because of cencern about potential offsite radiation / contamination.
The Cc:r:enwealth of Pennsylvania and EPA have been informed.
mada. by the licensee and NRC.
Press contact.s are being Centact:
GX11ngler, IE x28019 FNolan,,IE x25019 SEBryan, IE x28019
?' M Distribution:
Transmitted H St 5? ^
Chairman hendrie Cecmissioner Bradford S. J. Chilk, SECY Cc::T::issioner Kennedy Ccamissicner Aheame C. C. Ka: merer, CA Cc::missioner Gilinsky (For Distribution)
Transmitted: MNBB '6 TU P. Bldg 3'. 40 J. G. Davis, IE _,
L. V. Gossick, EDO H. R. Denton, NRR Region J "1 $ q H. L. Ornstein, EDO R. C. DeYoung. NRR J. J. Fouchard, PA R. J. Mattsen, NRR N. M. Haller, MFA V. Stello, NRR (MAIL)
R. G. Ryan, OSF R. 5. Boyd, NRR J..J. CL.aa:ngs, DIA H. K. Shapar, ELD SS Bldg S*..S'2.
R. Minogue, SD W. J. Dircks NMSS PRELIMINARY NOTIFICATION 3
e S
PG 0Y l
PRELIMINARY NOTIFICATION March 29, 1979 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PHO-79-67A This oreliminary notification constitutes EARLY netice of event of POSSIBLE safety or public interes: sienificance.
Tne information presentec 1s as initially receiveo witnout "erification or evaluation and is basically all tna: 1s Known my IE staff on tnis caa.
Facility: Three Mile Island Unit 2 Middletown, Pennsylvania (DN 50-320)
Subject:
NUCLEAR INCIDENT AT THREE MILE ISLAND - UNIT 2 This supplements O!O-79-67 dated March 28, 1979.
As of 3:30 p.m., on March 28, 1979, the plant was being slowly cooled down with Reactor Coolant System (RCS) pressure at 450 psi, using nomal letdown and makeup ficw paths.
The bubble has been collapsed in the A Reactor C olant Loop hot leg, and some natural circulation ecoling has been established.
Pressurizer level has been decreased to the high range of visible indication, and some heaters are in operation.
The secondary plant was being aligned to draw a vacuum in the main condenser and use the A Steam Generator for heat removal.
The facility p'lans to continue a slew (30F/hr) cooldown, until the Cecay Heat Removal System can be placed in operation at 350 psi FQS pressure, 3500F RCS t'amperature in 15-18 hours.
As of 3:30 p.m., a plume approximately is mile wide.and reading generally 1 mr/hr was moving to the north of the plant.
The ARM's helicopter is being used to define the length of the plume.
Airborne iodine levels of up to 1 x 10-8 uCi/ml have been detected in Middleterm, Pennsylvania, which is located north of the site.
Media interest is continuing.
The Cerm:enwealth of Pennsylvania is being kept infor ned by plant personnel.
Centact:
GX11ngler, IE x28019 FNolan, IE x28019 SE3ryan, IE x28019 Distribution:
Transmitted H St M b 'h M '
cnairman hendrie Cemissioner Bradford S. J. Chilk, SECY Cc.nissioner Kennedy Commissioner Ahearne C. C. Kamerer, CA Ccccissioner Gilinsky g.Q (For Distribution)
MNSB h b P. Bldg h Transmitted:
J. G. Df.yis,IO G _,
IE L. V. Gossick, E00 ~
H. R. Denten, IN.
Region l-C H. L. Ornstein, EDO R. C. VI.'",, NRP.
J. J. Fouchard, PA R. J
' t.tsen, NRR N. M. Haller, MPA V. Stello, NRR (MAIL)
R. G. Ryan, OSP R. S. Boyd, NRR J. v. CunTninos, CIA H. K. Shapar, ELD SS Bldg 10*9 0 R. Minogue, SD W. J. Dircks, NMSS PRELIMINARY NOTIFICATICN q
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___-...-,,,,, e m e..n :
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1
{} PRELIMINARY NOTIFICATION '~ ~ Mar =h 30, 1979 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL CCCURRENCE--PNO-79-67B This oreliminary notification constitutes EARLY notice of event of P055 ELE safety or ouotic interest sien1ficance. Ine 1r.fornation cresented is as initialiv receiveo witnout verification or evaluation ~ ana is ::asically all tnat is itnown av IE staff on tnis e; ate. Facility: Three Mile Island Unit 2 g f-Middletown, Pennsyl vania (DN 50-320)
Subject:
Nuclear Incident at Three Mile Island /) Plant Status ' Three Mile Island Unit 2 is centinuing to remove decay hr.at through A-loop steam generater using cne reactor coolant pucp ir that loop for coolant circulation. The reactor coolant pressure and temperature were stable and under control throughout the night of March 29. There has been sore difficulty in maintaining coolant latdown flow due to resistance in the purification filters. The licensee notified IE at about 11:00 p.m. en March 29 that they expected to remain in this cccling mode for at least 24 hcurs. The licensee's engineering staff was requested by NRR to cbtain a better esticate of the volume of the noncondensible " bubbles" in the reactor ccolant system. There are apparently two such bubble; one in the pressurizer that has been intentionally established for centrol of ' pres ure and level, and one 1n the reactor vessel head enused by the accumulation of nonconcensible cases from failed fuel an:1 radiolytic W omposition or water. The estimate is to be obtained t;y correlating pressuri:cr pressure and level indications ever the past tours of stable creration. ,The volume of the bubble in the reactor vessF1 is of interest. in as:uring that sufficient volume rerains in the upper head for collecticn cf more noncendensible gases arising from continued cperrtion in the
- p. esent ccoling mode as well as to assess the pctential f:or movement of t.ne bubble during a switchover to decay heat removal operation.
% licensee believes it is prudent to remain in the present cooling
- S due to the potential for leakage of highly radioact-ive coolant frem
- .2 ducay heat removal system into the auxiliary building, covenant of et.ndensible gases inte the reactor coolant loop, and boiling in the
- rc wnan the reactor coolant pump is shut dcwn.,
= CMTINUED 376288
g. V ?- Page 2 March 30,1979 Continued PND-79-678 Fe1 Dae.aca Preliminary assessment of the extent of fuel damage from a reacto coolant sample taken at approximately 5:00 p.m. on March 29 indicates significant releases of iodine and noble gases frem the fuel. A 100 millilitar sanple taken from the primary coolant system via a letdown line was measured at about 1,000 R/nr on contact (70-80 R/hr at one foot and 10-30 R/hr at three feet). Pre 11minary analysis of a-diluted sagle in the IE m: bile laboratory indicated fission product concentrations of about 8 x 105 microcuries per milliliter. The sample will be flown to Eettis Laboratory for further analysis. Thermoccuple readings of ccolant temperature at the outlet of the instre,ented fuel assemblies indicate potential local core da:nage, possibly in one quarter of the total of 177 fuel assemblics and generally in the center of the core. Of the 52 readings at 5:00 a.~ on March 30, cne was above the coolant saturation temperature of about 5500F, 7 were above 3500F, and 2 were off-scale, indicating temperatures higher than 700cF. Upon request of NRR, Babcock and Wilcox is develeping a proce-dure fer use by the licensee in taking direct potenticmeter readings frem the off-scale ther::ccouples since the temperature scale limitation of 7000F is controlled by the process computer, not the ther:ccouple its el f. i Reacter Coolant System (RCS) Parameters The RCS parameters have remained relatively stable during the period. Gradual F.CS cooldown continued to about 1:30 a.m., March 30, when tempera-ture was slightly increased to allow additional margin between RCS c;; crating parameters and Technical Specification minimum pressurization limits. Following are the primary system parameters over this period: 10:00 a.m. 7:00 p.m.12:01 a.:n. 3:00 a.m. 5:00a.m. 3/29/79 3/29/79 3/30/79 3/30/79 _3/30/79 Pressuri:cr Level (inches) 348 321 325 342 354 945 1023 1055 1053 Fre:surizer Pressure (psi) 853 Prcssuri:er Temperature (OF) 529 542 551 556 557 Lc:p A Core Inlet Temperature (oF) 281 277 275 278 274 L :p B Core Inlet 7em::erature (oF) 281 277 275 278 274 ~ CONTINUED 378267
. Q.: .,a t 7:~: Page 3 March 30.1979 Continued PNO-79-678 Environmental Status Two aerial surveys were conducted during the evening of March first flight was made about 8:15 p.m. during which measurements were 4 taken in a circle around the site with a radius of about eitJht miles. No defined plume of radioactivity was detected, but residual pockets of ~ radioactivity were identified at various points where the measured levels ranged from.025 to.050 millircentgens per hours. (Natural backgrcund levels are about.005 to.015 millircentgens per hour.) During the second flight, at about 10:30 p.m., a plume was detected northwest of the plant with a width equal to and confined within the boundaries of the river. The plume was touching down about one mile fr:m the plant at Hill Island and then splitting into two part - one on each side of Hill Island. Measurements at the east shcreline of the river, opposite Hill Isalnd indicated about four millircentgens per hour and at the shoreline on mi7e north of Hill Island near Olmstead Air Fcree Base ebout one milliroentgen per hour. Additionai measurements at five miles from the plant were on the order t.f.010 millf roentgens per hour and are in agreecent with the earlier f1:ght. During the early mcening hours of March 30, an NRC monitoring. teem took radiaticn measurements frcm a vehicle traveling both sides of' the Susquehanna River frem 10 miles s:uth of Three Mile Island to 4 miles north. Radiation levels were highest near Cly, a comte.ity just south cf the facility on the west side cf the river. The level at Cly was 0.15 millircentgen per hour. All other locatiens had levels less than 0.05 millircentgens per hour. Other Information At a: proximately 4:00 p.m. en March 29, two employees of tietrcpolitan Ediscr. Co. received radiation expcsures in excess of the quarterly limit of 3 rems. The employees, an operator and a chemist, ent.cred the auxiliary building to collect a sample of primary coolant. Present estimates are that the operator received 3.1 rems and the chemist 3.4 rems. The licensee released less than 50,000 gallen: of slightly contamineted industrial wastes en March 29, 1979. This relese was terminated at NRC request at approximately 6:00 p.m., March 2g,1979, because of concerns excressed by state representatives. At about 12:15 a.m. on March 30, fi?.C gave the licensee permis:icn to resume releases of the slightly c:r.tamir.ated industrial wastes to the Susquehanna River. This action w1*, cc:rdinated with the of# ice of the Governce Of Pennsylvanic and a press riease was issued by the State. F.epresentatives cf the news radia ex:res:ed centern that they were n:t inforred of the planned resumption cf the release prier to per-i:sien having been grante:. T/8 % 8 CC.'?TI fiUED e
e. t Page 4 March 30, 1973 Centinued PNO-79-67B At 8:40 a.m., en March 30 the licensee began venting frem'the gaseous w:ste tanks. The impact of this operation is not yet known. r ~.
Contact:
DTncepsen. IE x28111; EJordan, IE x 28111 Distribution: Transmitted H St 980 Chatrn:n Hendrie Com.issioner Bradford S. J. Chilk, SECY Comissioner Xennedy Cem.issioner Ahearne C. C. Ka. merer, CA l Ccmissicner Gilinsky (For Distribution) Tr:nsmitted: MNSB /ofo 2 P Bldg /4 //f J. G. Davis. IE L. V. Gossick, ECO H. R. Denton, NRR Regien H. L. Ornstein, EDO R. C. DeYcung, NRR J. J. Feuchard, PA R. J. Mattson, NRR N. H. Haller, MPA V. Stello, NRR (MAIL) R. G. Pyan, OSP R. S. Boyd, NRR J. J. Cunni ngs, OIA H. K. Shapar, ELD (SS Bldg R. Mir.cgue, SD W. J. Di rcxs, t< MSS Attad=ents (7): Aerial Survey (6) Ground-Level Survey (1) PRELIMINARY NOTIFICATION 378289
,4- . (,.... ~ ) AERIAL SURVEY / ~'" "'" 900RORGNAL re
- v. -
- f. ' k.y
/- ~ l '. ',$'-. Palt:trra y f*;,\\N. 3,;V 't Y
- 2. Q:m %Ki 7
~ ~.s u m stcwn 2 .~. die own ,' h.'.,',.., oldsboro ~3-mile fizabethtown ~.f.' Island ','g, ' ' '.h. f. j " -= 10, e r.il e: 2, 1573 4:20 p.:. M T'!.in c H to NE direction, about 30* se: tor. jiy ye_132. At distance cf about 15 miles, ' OI$h.icn reasure:nents in the plume were about 0.1 cr/hr. r 3.78230
r8 ..h ~ PRELIMINARY NOTIFICATION a March 30,1979 PREi.IMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-79-67C This oreliminary notification constitutes EARLY notice of event of POSSISLE safety or ouolic interest s1cn1ficance. The infor nation Dresentec is as initially received witnout verification or evaluation and is cas1cally all tnat is kncwn oy It staff on tnis cate. ' Facility: Three Mile Island Unit 2 i Middletown, Pennsylvania (DN 50-520) 'Subje'et: NUCLEAR INCIDENT AT iHREE MILE ISLAND ~ . Plant Status There have been intemittent uncontrolled releases of radioactivity into the atmospnere from the primary coolant system of Unit 2 of the Three Mile Island Nuclear Power Plant near Harrisburg, Pennsylvania. The licensee is attempting to stop the intermittent gaseotts releases by -r transferring the radioactive coolant water into the primary containment building. The levels of radioactivity being measured have been as high as :20 to 2S millirem per hour in the immediate vicini?,y of the site at ground level. Off-site levels were a few milliroentgen. At!about 11:50 a.m. EST, the Chaiman of the NRC has suggested to Governce Thornburg of the Connonwealth of Pennsylvania that pregnant women and pre-school children in an area within five miles of the pla;nt site be evacuated. ' Members of the NRC technical staff are at the siite and efforts to reduce the temperatures of the reactor fuel are continuing. These temperatures have been enming down slowly and the final depres-surization of the reactar vessel has been delayed. There is evidence of severe damage to the nuclear fuel. Samples of primary coolant containing high-levels of radioiodine and instruments in the core indicate high fuel temperatures in some of the fuel bundles, and the presence of a large bubble of non-condensible gases in the top of the reactor vessel. Because of these non-cendensible gases, the possiblity exists of interrupting cociant ficw within the reactor when its pressure is further decreased and the contained gases expand. Several options to reach a final safe state for the fuel are under consideration. In the meantime, the reactor is being maintained in a stable condition.
Contact:
SEBryan, IE x28188 ELJordan, IE x28188 Distribution: TransmittedHSthlL3 Cnairnan Hendrie Comi~ssioner Bradford S. J. Chilk, SECY Comissioner Kennedy Comissioner Ahearne C. C. Karr,erer, CA (For Distribution) Comissioner Gilinsky P. Bldo /I 1 9 J. G. Davis. IE Transmitted: MNSBi . ~ L. V. Gossick, EDO H. R. Denton', 'NRR Region T d so H. L. Ornstein, ECO R. C. DeYoung, NRF. J. J. Fouchard, PA R. J. Mattson, NRR N. M. Haller, MPA . Stello, NRR (MIL) R. G. Ryan, OSP R. S. Boyd, NRn J. d. Cum.in gs 01 A H. K. Shapar, ELD SS Bldg R. Minocue, SC W. J. Circxs, HMSS PRFLIMINARY NOTIFICATION 97Md31
~., IK4EDIATE PRELIMINARY NOTIFICATION - - ~ ~ ,___,. = _ _ _ _ = March 30,1979 PRELIMICARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PMD-79-67D Tnis ersliminary notification constitutes EARLY notice of an event of POSSISLE safety or cublic interest sicnificance. Ine information r.resentcc is as init1 ally received without verification or evalut tien td is e sicativ all tna: 1s knc:en by IE staff on this cate ftcility: Three Mile Island Unit 2 Middletown, Pennsylvania (DN 50-320)
Subject:
NUCLEAR INCIDENT AT THREE MILE ISLAND J dj Tb nt Status G seous radioactivity frcm the primary coolant system letdown has been cr.ncained in v::.ste gas decay tanks since the last gasecus relea:e at t proximttely 2:50 p.m. March 30, 1979. At the present reac-tor coolant letdv.n rate of approximately 20 gpm it may be necessary to rde a plcnncd release of radioact1ve gas toniorrow to prevent gas ciecay r.ank r;-lisf valve operation at its setpoint of 100 psi. The lic:ensee has mste.lled a to:aporary line fron the gas decay system back to reactor etnttinment which is under evaluation before being placed in operation. Centainme,1t pressure is being maintained slightly negative (:-l psi) as a r;sult of fan cooler cperation. T.nctor coolant temperature measured at fif ty-two lccations tat the cutlet of the core have continued to come down slowly. Three Outlet t;.perature instruments continue to indicate above saturation temperature. The NRC sicff was inforr.ed by the licensee on Friday morning thtt ext.minatian cf centai:rr.:nt pressure data for March 28 indicates a pressure spii:e up M i.pproximately 30 psi occurred at approximately 1:50 p.m. NRC pctscr.nel uc evale-ting the possibility that a hydrogen er.plosion was the cr.use ci the conttir,mant internal pressure spike. Th? r:cetor coolant path is through one reactor coolant puro and cr.e st::m ccm rator. The stetm generator is being fed by an auxiliary feed-r.'. p. S:"cral options for d.= pressurizing the rea.ctor and continuing c :.ldr 1 via the residual heat removal system are under considsrati:n. l . _. _.,.,... =. - - -.,, - =- ~ = " - ~ ~ ~ ~ CChTINUED 4
s March 30,1979 Page 2 FNO-79-67D . _.. =.. - - = = Ccnti r.'.' 2d -. m... The volume of non-condensible ]ases in the reacter vessel has been cStimited to be approxir.ctely 1000 to 1500 cubic fast at 1000 ps,1. This vole.Se is estimated to result in a water level cf several feat over the tcp of the fuel. The rate of growth of the bubble in the r: actor vessel is estimated to be less than 50 cubic feet per day at 1000 psi. The Director of the Office of Nucicar P.eactor Regulation, the Director of the R ; ion I Office of Inspection and Enforcement and the Director of 1.he Division of Operating Reactors arrived at the site at cpproximately 2 p.m. tefcy to dir ct NRC activities at ti e site and site vicinity. I'. ;re:entatives of HEW and EPA are providing coordination and assistance to the KP.C at the Incidant P.esponse Center. i.; persennel assembled at the TMI site and vicinity in addition to the ~
- t. par man..gement personnel censist of the following:
RI RII RIII Hq T.:?.ctor Inspectors (IE) 8 5 4 12 12 10 Keslth Physicists (IE) 4
- cith Physicists (SP) 1 1
i f:.:blic Af airs 13 f... : tor System Analysts (:RR) 4 T..dition '.'c:te Specialists (NRR) 6 i:::lth Physicists (NRR) C, cr:tir.g Licer. sing (Mr,g) g enl j 2 U' N '1 J"I e Total Staff ..~.-- --~ _ _ = _ - -.:,,.-..-.-- - ~_ ....a-..,.. L..:T..;U ED
Page 3 Centine:d March 30,1979 PHO-79-67D The folle: ting ecuipment has been assembled at or near the site for support of HRC cperations: Ec;uipment Location i NRC Instruat.nt Van with 2 talephone-lines Observation Center 1 NRC Office Van 1 Office Trailer (Supplied by Licensee) 300 Fcnd-Hald Fortable Radios frem US Forest Service Portable Mealth Physics Instrumentation h)j(D 3 Halicopters from DOE for survey and Ilj(QQI f support aj 4 2 Laboratory Vans DOE /Bettis A sophistiented cc=unications pod from COE/ NEST will arrive tc:.:.:rrc.t. !"/:P.G::'ItGk STATUS: nt appiihimately 3 P.M. on f4 arch 30,1979, NRC analysis of eight vegetation samples from the offsite areas showed no detectable activity. At 5.30 P.M. the Fennsylvania State Radiaticn health Depart;;ent reported ther environnental "Ette.ind air samples collected in the vicinity of the Three Mite Isl:.nd .r..t sb.:2d no detectable activity except for some Xenon-133 arui Xenon-135 ". ilk srple analysis sho..ed no activity leve. above background. ':ffsite cr:und level gcr.na surveys in the Middletown and Goldsbero r.reas t.t. :: 3:00 and 6:00 P.M. on March 30, ranged from.01 to 1 mirlircentgans ':r h;.. An nrici survey was made by helicopter from 4:00 - 6:00 P.M. i a !' arch 30, the site vias surveyed in concentric cir<es at approx'mately one mile fitcrvals cnd at a height of 300 to 1,000 feet. The hichest ra:Mation v ; ding.; :2rc over the site and measured 8 to 10 millircent;:ns ;:er hour . i M.3 pl r:: t.hs highest radiation readings were 6 to S nilliroentgens
- r h:.r.
The pluma 'ollostad the river in a ncrthytesterly direction and (2'::.ctc.lu boycnd five to six miles frem the site. Site ground level .s r.:: y; : 'ucted bar:ctn 7:30 - 8:00 P.M. rangad frcm.01 to 1.8 . ili f r::n';;:ns per nour. .. - -. -. :--,.=---. s. -,,... - - _ - - - ~ CO:'TINJED SWZM
Page 4 March 30, 1979 - -- - - _ - -,9-67 D F?:0-7 ., _.. crtinue,d,_ _-. C -w --,c, - - - - -. At 4 P.!!. l' arch 30, upper level winds were from the southeast. Forecast indicates precipitation in the for.n of thunderstor::s coving in after 12 nidnight, March 30. At 5:00 P.M. winds onsite at Three Mile Isic.nd 1:cre reprted Lt 2 to 3 miles ; ar hour generally from east to 'tast. Cor.ttet: E;Gc.tard, IE x28111; EJordan, IE x23111 .i Di s tributi.?n: Transmitted H St /!/o = "5' t.'..s t r. sn Har.drie Ccenissioner Bradford S. J. Chi 1R, SECY Ccr.aissiencr Kennedy Co :nissioner Ahearne C. C. Kact:rer, CA Ccnnissicner Gilinsky (For Distribution) Trt.nsmitted: M GS /.'/ 7 P Sids /!2r J. G. Davis, It L. V. Gessick, EDO H. R. Centen, NRR Region
- n. L. Ornstein, EDO R. C. CeYeung, NRR J. J. Fcuchtrd, PA R. J. Mattson, NRR li. fi. Haller, MP
V. Stello, NRR (l'AII.) R. G.. 'an, OSP R. S. Scyd, fiRR J. J. Cu.=i ngs, 01 A t H. K. Sh: par, ELD (SS Bldg /.* 3.3 R. Minogue, SD W. J. Di rcks, HMSS L'hite House Situation Roc.n /2.'ffo ~. %//75 EPA iTl./ E h COE/EOC a : c:, a 4, .'.tuct.::nt (1 ) kdictica Scrvey Map -,.- ~ ~. n.,.n... - - - ~ ~ ~ ~. ~. - I; JEDI ATE . ?EL:I'I ;;,P.Y : 07IFICAT 05
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IbMEDIATE' PRELIMINARY NOTIFICATION Maren 31,1979 l PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL CCCURRENCE--FNO-79-6 t This icrnediate oreliminary notificatien constitutes an ucdate of event of stety ano ouolic interes: sicnificance. Tne infor-atien oresented 1cn cr evalua:1cn and is is as in1_tlaliv received witnout verifica basicaily all :nat is known oy NRC staff at tnis time. Three Mile Island dnit 2 Facility: Middletown, Pennsylvania (DN 50-320)
Subject:
NUCLEAR INCIDENT AT THREE MILE ISLAND Plant Status Reactor cooling continues usingf the l A main reactor cociant pum with Changes to this steam generator A steaming to the main condenser. An cperability status cooling method are not planned for the near term. cf equipment is being ccmpiled.for use as backup in the event of failure of existing operating equipment. The hydrogen recembiner is in an operable status; hcwever, shielding of its piping and ccmponents is not fully installed and is presently cen-Lead for shielding has been located and will be sidered inadequate. Calculations of hydrogen in moved to the site on an expedited basis. containment show that the present cencentration is less than 4%, the staff's limit on allowed concentration to ensure an explosive mixture is Attempts are being made to cotain a containment at::csphere not obtained. sample. l The waste gas decay tank pressures were 80 psi at 10:15 p.m. cn March 20 The tank is set and had been relatively ccnstant for about five hours.The radiaticn field (60 R/hr at to relieve pressure at 100 - 110 psi. contact) prevents resetting relief points. I Reactor coolant temperatures measured by incere ther-nncouples at 52 locations presently show only one locatien above saturaticn temperature. Temperatures in the core as measured from cutlet tnemoccupies areOt gradually decreasing. I Environmental Status 1 Three AFMS flights of one-hour length were conducted beginning at At a 9:30 p.m. on March 30, and at; midnight and 3:00 a.m. en March 31. ' CONTINUED I
ue th 31,1979 Page 2 PNO-79-67E distance of one mile from the plant, maximum readings ranged from 0.5 millircentgens per hour (mr/hr) to 1.5 mr/hr. At the 18 :: rile point, readings of 0.1 to 0.2 mr/hr were obtained during the two earlier surveys and 0.5 mr/hr during the latest. Flights are being made at approximately three hour intervals. Offsit.e ground level gam.a surveys in the Middletown area and north, between 9:30 p.m. on March 30 and 1:00 a.m. on March 31, indicated levels from 0.2 to 0.5 cr/hr. lThese measurements were taken in the general direction of the plume: measured in aerial surveys. At 3:00 p.m. on March 29, (priolr to the releases of March 30) the 1,1cense pulled thermoluminescent dosimeters from 17 fixed positions located within a 15 mile radius of the; site. The dosimeters had been in place for three months and had been exposed for about 32 hours after the incident. Only two dosimeters showed elevated exposures above nom.a1 levels. The highest reading observed was on Three Mile Island. 0.4 miles north of the reactor at the North Weather Station. At this location, the quarterly accumulated exposure was 81 mr, approximately 55 =r above the normal qucrterly exposure rate. The other high exposure was observed at North Bridge, 0.7 miles NNE of the reactor at the entrance to the site. At this ilocation, the total quarterly accumulated exposure was 37 mr or approximately 22 mr above the normal quarterly exposure rate. j During the evening milking hou$s on March 30, milk samples were collected by the Pennsylvania Department of Environmental Resources at the following locations: Harrisburg (2 sites) ' York il T)M)hg Middl etown Bainbridge $h {M Etters (UU Analyses showed no detectable radiciodine. The cows had been fed on stored feed but had been outside for exericse. l The Pennsylvania Depart::ent of Environmental Resources also collected water samoles at filtration plants at Columbia, PA (for the City of Lancaster) and Wrightsville on March 30 in the morning and early afterncen. Both sample points are downstream of Three Mile Island. No detectable activity was found. , CONTINUED
'. Continued darch 31,1979 Page 3 PNO-79-67E
Contact:
DThc=psen, IE x28111 NCMoseley, IE x28111 Distribution: Transmitted H St O: OL Chairman Hendrie Comissioner Bradferd S. J. Chil k, SECY Cocnissioner Xennedy . Connissioner Ahearne C. C. Kamerer, CA Coenissioner Gilinsky (For Distribution) Transmitted: HNBB O:O6 P. Bldg 9 I 6 J. G. Davis. IE L. V. Gossick - EDO , H. R. Denten. NRR Region l_ G : M H. L. Ornstein, EDO . R. C. DeYoung, NRR J. J. Fouchard, PA ! R. J. Mattson, NRR H. M. Haller, MPA ! V. Stello, NRR (!* AIL) R. G. Ryan, OSP
- R. S. Boyd, 90 J. a. Cunnings, CIA NRR H. K. Shapar,. ELD SS Bldg Cl.
R. Minogue,_SD
- W. J. Dircxs, NMSS l
s. khite House Situation Rcom EPA FDA/SRh l DOE /EOC Attachmnt (1) i Radiation Survey Map j IMMEDIATE PRELIMINARY NOTIFICATION f I i 378303 l
N ['Q s. 6,2, nA.4}Palmva ~ l ~- j. _ ~, ~. H <. 1sto "~ " - lt C ;#tM/M4 ' ' Nb 'h l f \\' Y :tefiand Cc {h?letof /. S m ie.p y k raWethtown f3 oldsboro T. .j ... ? I l N APPX SCALE Miles i Parch 31,1979 d:00 a.m. AERIAL!5URVEY plume direction ar d radiation readings shown above. i Fa-c.h 31, 1979 1:00 a.m. All ground level readings were less than 0.1 mr/hr. measurements rade in.venicle ter.velling route Ul from about ten miles scuth of p? ant to route 76 and south along roads on the wes.t side of the r-iver. i 378300
If0!EDIATE PRELIMINARY NOTIFICATION March 31, 1979 PRELIt'INARY NOTIFICATION OF EVENT OR UNUSUAL OCCURREfCE--Pl*0-79-67F This oreliminarv notification constitutes summary infer =ation of an event of safety or public interest sionificance. The infor= tton oresented is a sum.rv of information as of 5:30 pm date 3/31/79. Fccili tv: Three Mile Island Unit 2 Middletown, Pennsylvania (DH 50-320) Subiect: t<UCLEAR INCIDENT AT THREE MILE ISLAND I Plant Status There has been no change in the method of cooling the reactor since the previous report (PNO-79-67E). Reactor coolant temperatures measured by incore ther=occuples at 52 locations have continued to decrease. At present none of the temperature readings is above saturation temperature for this pressure (554*F). System parameters remain stable. There has been a slight drop in pressurizer level from 215 to 191 inches. Efforts continue to complete installation of ce=ponents and piping on the hydrog :n recombiner. Approximately 220 tens of lead shielding; in varicus shapcs and forms has arrived, or is on the way, to the site. Lead shielding is being installed around the recombiner. A decision to use t.ne recombiner has not yet been made. Two samples of containment at=osphere have been ontly.:ed sthich shew hydrogen concentrations of 1.7 and 1.0%. Ef forts continue to estimate the volume of the noncondensible gas bubble c5cvc the core. Licensee calculations of the sir.e of the bubble at 2: 40 pn s:.s E20 cubic feet at 875_psig. At about 4: 20 pm this was recalculatec by t' - licer see to c:: 621 cubic feet at 875 psig. Inis is being further evaluated. Environcental Stctus Three AR.S flichts were conducted at cbout 6:00 a.m., 9:00 a.ra., and 12:00 neo, ca 1~,crch 31. All flights reflected a rather stable situation. Maximum rccdings in the plume were from 1.5 to 2.5 millircentgens per hour (cr/hr) et a distance of one mile f eca the plant, from 0.5 to 1.0 mr/hr cut to 7 ciles, and 0.1 to 0.2 cr/hr beyond 10 miles. The plume width is about 1-1/2 1.e 2 miles. L radiciodines have been detected in the ple=e. Of fsite grcund lcvel gamma surveys performed in the predominsnt wind direction indic='.ed r ximum icycls of abcut 2 mr/hr at about 1/2 mile f r:,m the site r..- (.i rection o f the pl um2. The wind was frca th? SSW at the time of the CONTINUED <g3(jl rne u n wnr.1 nuiarn.n:Aun
Continued Rarch 31,1979 Page 2 PNO-79-67F ARMS flights. At about 1 PM the winds shifted and are now blowing in a south easterly direction. International Contacts NRC's Office of International Prcgrams (OIP) has prepared daily status reports, transmitted by Immediate Department of State telegracs to official NRC contacts in the 25 foreign countries with which NRC has regular official relations. OIP is also receiving many foreign telephone. calls. Two senior safety experts frca the Federal Republic of Ger::any (FRG) arrived icts M:.rch 30 and were briefed by NRC experts at the Oper ations Center, 1cte March 20 and during March 31. Two French experts will arrive April 1. V.'eshington Representatives or senior visitors of Japan, FRG, and Sweden clso have been briefed in the Operations Center. OIP also has been briefing the Presidcnt of the AECB of Canada, who offered to send any AECL or AECB cr.perts who could be of assistance. Contr.ct with Licensee NRC Regional Offices are transmitting to the utilities with cperating licenses sucr:ary information (in the form of Preliminary Notifications) as th:y are preparod.
Contact:
DThompson, IE x28111 EMHoward, IE x28111 Distribution: Transmitted H St 7.'oCc. Chairran Hendrie Corr:aissioner Bradford S. J. Chilk, SECY Co niscioner Kennedy Cor=icsioner Ahearne C. C. Ka=erer, CA Cc:=issioner Gilinsky (F:Dr Distribution) Tr:nsmitted: Mt:BB '/.'/dq_ P. Bldg 7.'/8e-J. G. Davis. IE L. V. Nssick, E00 H. R. Denton', NRR Region I 'h* CO H. L. Ornr.tein, EDO R. C. DeYoung, t!RR Region II J. J. Focchard, PA R. J. Mattson, NRR Region III t!. ii. E:.11er, MPA V. Stello, NRR Region IV r., G. ny::n, 0 P R. S. Bovd Region V-71cc SS Bldg 7,', NRR36p M. K. Shcpcr, ELD , fr.IL) ( U. J. Dircks,? CGS J. J. Cu=ings, OIA R. Minogue, SD !?.itt House Situction Room 7,'R[p E?A =. FD.'L,1 v 3 1 g /.t::.ctrar,t (1) }UE E:ci tien Survey M:p _r-- ,m,__ II..w m : PRELIMINARY NOTIFICATICli S78302
' l, Q-.,. d, f - C.1 W o 'N - l \\.? ? % anu kl i), J \\*H i ' ~$ - 'N 'umei town P; d f-/,0 ,,, -: N,[ - /. ,, ~ e'< New 2 ,\\, Cumbeliand /,' ,..x i in g d etc W h.. %. c /. C-2. 5* QI /(E132abethtown 3-mile toldsboro Island 1 N.... I r..- f k :~. N.. \\*. ..a APP 7. SCALE 9 '5 l9 1;iles ..,3 7:n 31, 197 9 AEP.! AL SUP.VEV piume cireccion an:: radia tion readir.cs shown above conducted at 6 :00 & 9 :00 AF'.. end 12iOO neen. ' 37bidd3 i
IE Bulletin No. 79- 05 Date: April 1, 1979 Page 1 of 3 EVALUATION OF FEEDWATER TRANSIENT A loss of offsite power occurred at Davis-Besse on November 29, 1977, which resulted in shrinkage of the primary coolant volume to the degree that pressurizer level indication was lost. A recommendation to convey this information to certain hearing boards resulted in the attached discussion and evaluation of the event. This discussion includes a review of a loss of feedwater safety analysis assuming fcrced fTow, which predicts dispersed primary system voiding, but no loss of core cooling. During the Three Mile Island event, however, the forced flow appears to have been terminated during the transient.
Attachment:
Discussion and Evaluation of Davis-Besse Transients O 378304
m. IE Bulletin No. 79-05 .F, Date: April 1,1979 -, Attachment ] Page 2 of 3 II.IZ?T TRCM XII'.CEANDUM IN--~~ " " COTE n.a., NT4 a.u C*CUJT ON TO I.1CINSISG 2 CAR 35. - DAVIS-3ESSI IntI S 2 & 3 AND M riAND Util S L & 2", D/JT3 ,-,,1, 8, is.,9, :.Cu_ S. C1. a,~-.,..s.--.u. .n.a 3 I=spectic: a > T #c ce=e== lap== = 30-346/75-06 de====ted da: pressurize level had gene effscale der appr x1=analy five- .=i=utes d=ing-the Nev -Q: 29, 1977 less of cff site Fever eve =. I There are s=e i= dica:1==s da: c:he: 3&W pla=:s =ay have p =b-
- le=s==1=- ' d g p:essurise: level indicati=== duri=g- :=a=sie=:s.
!= addiri =, u= der car sin c: 2d _1==s such as less cf f eedva:er-a: ICC: pcuer vid de raze::= ::=la== pu=;s - ' g ha pres-- s=1:e: =ay veid c==ple:ely. A special analysis has hee = per-f==ed.=== erming :his eve-- '" 's a alys'.s is a ::2---d_ as I==lesura 1.' 5ecause cf pressuri=e level ain:e :==ce ;;ch-le=s the sd '=g =f de pressurizar =sy r equire fu :he revie'. v . Als e =c r ed d uri=s :he ev e= : vas _h e f a : da:
- = d v e= = c f f-scale (less da: 520CF).
I= addizie=, i: uas :=.zd. tha:.:he .=akeup f1=====1:::1=g is li:1:ed :: less .z: 160 sp= and da: =akeup f1=u may be substantially g ea:e tha= dis val =a. ' This i=f =sc ie= sh=uld be :- ed i= lish: cf :he require-N O gI.j se=:s cf COC 13. h~nf1h4.iW .u_e - e m-.. J.,D _._ m... _ o. w. Neeve==a: Davis 3 esse vi.id esulted i= icss =f 7:e'ss= riser level indi=a:ic.= has bes: reviaved by hl.2 a=d :he conclus'e= vas . ached ha: =o u= reviewed safe y quest.i== existed. The pressurizer, :=gether vich the re.a:::: cocian: =akeup sys:e=, is designed :: =si=:ai: :he primary syst a= pressure a=d va=== level vi:~-'- heir eperati =al l'-d:s c=17 duri=g
- =al, cpera:1=g :==di:ic=s.
- 1d:
- re--ie=:s, such as 1 css Of c'fsite p=ver and 1=ss of feed-va:er, sc=e:1=es resul: i= p "-':r p assure a=d velu=e cha=ges da:
2:e bey==d :he abili:7 ef this sys:e= := ce=:.:1. ~he a=alyses of a:d e=perience vi:h such ::ansie=:s shev, h=vever, :ha: : hey c== be su::ai=cd vi:heur c=== :=isi=g the sr.de:7 c.f de reze = S e principal c=:c e. caused by such ::'-<1e=:s is~ da: they =igh: causa veid' g 1:i
- he pri=ary ecola=: syste= tha: sculd lead :
1: s s c f ah ' ' ' :7 to ada-qua:ely. ::cl_ :he reac::: core.
- e saf e:y evalua:ic= cf he icss of
~~ ef fsi:e pcuer. ::a=sie== shews that, though.leve' '-d'entie= is Icst, se=e va:er : r -'-= i= he pressurize: and the pressure d=es=== decrease belev abeu: 1600 psi. In c d.s;; f w '.' ww '41u3 'w uem, the pressure==s: decrease belev the sa:uratica pressure cc respending := nha syste
- c=perature.
1600 psi is :he satu a:icn pressure : - erpe= ding := 6C5'7, whid is also the =a=i=== allevdle c:re cu.le: :e:pera:ura. 7:_ ding in :he pri=ary syste: (e=:ep:i=g the 7:ess '-a-) 's precluded i: '.is case, since pressure does ec: decrease : saturacic. ym305
~ IE Bulletin.No. 79-05 5 Date: April.1, 1979 -, Attachment ' ~g. Page 3 of 3 ~ 4 ~he sr.facy a=alysis f c:==re severs cocidev: : =sie=:n, such as the ? icss of feedva:e even:, indies:es tha: he water velu=e ceu' d dacrease e e-t.s 4 ve c..s.e sst a... ,.. e. e .. s.s s .s... .w. sys ve u e.- ..~ such.an eve==, the e=p:ying cf :he pressurizer veuld be felleved by a p.esst....eA..'~ ' e1.~..r ^. e s.- ~.~... -. ' ~ o. c ' -. = 6. *. e'. ' c - ' ~ c ' n h o:.u.,..a a,.., g,g. -u.m...euza -. u. g._g,, ga >s u -. s .T.
- esult i the icss of core c= cling because the veids veuld be dispersed ever a'large volu=e a.=d fereed f1=v vculd preve=
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i +. g IE Bulletin No:. 79-05 Date: April 1,1979 Page 1 of 3 s,, ) LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS i Bulletin Subject Date Issued Issued To No. 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechanism - General (0:_) or Construction Electric Model CR105X Permit (CP) 78-06 Defective Cutler-5 /31 / 78 AIT Power Reactor Hamer, Type M Relays Facilities with an With DC Coils OL tor CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities; with an and Supplied-Air Hoods OL, all cliass E and F Research Rteactors with an OL, alli Fuel Cycle Facilities; with an OL, and all Priority I Maarial Licensees 78-08 Radiation Levels -from 6/12/78 All Power,, Test and ~ Fuel Element Transfer Research Reactor Tubes Facilities; with an OL having Fueil Element Tramsfer TTubes 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reettor Facilities Inadequate Drywell with an OU. (for action) Closures or IP (fotr information) 78-10 Bergen-Paterson 6/27/78 Ali BWR Power Reactor < Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP Spring Coils 5 .....e 1 T 378.307
i IE Bulletin No. 79-05 Date: April 1, 979 Page 2 of 3 p, } lj @Q,i LISTING OF IE BULLGINS L ISSUED IN LAST DIELVE MONTHS (CONTINUED) Bulletit: Subject Date Issued Issued To No. 78-11 Examination of Park I 7/24/78 BWR Power Reactor Containment Torus facilities with an OL Welds for action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, tbnti-cello and Vermont Yankee. All other BWR Power Reactor Facilities with an OL for information 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facili ties with an Vessel Welds OL or CP 78-12B Atypical Weld Paterial 3/19/79 All Power Reactor in Reactor Pressure Faci'li ties with an Vessel Welds OL or CP 78-13 Failures In Source Heads 10/27/78 All Seneral and of Kay-Ray, Inc., Gauges Spec ~if'ic Licensees Models 7050, 70508, 7051, with the subject 7C518, 7060, 70608, 7061 Kay-Ray, Inc. and 7061B Gauges 78-14 Deterioration of Buna-N 12/19/78 All GE BWR Faci-Components In ASCO lities with an OL Solenoids (for action), and all other Power Reactor u Facilities with an OL ,(_ or CP (for information) m T 1 l e f., J p
s IE Bulletin No. 79-05 Date: April 1, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED) Bulletin Subject Date Issued Issued to No. 79-01 . Environmental Qualifica-2/8/79 All Power Reactor tion of Class IE Equipment Facilities with an OL, except the 11 Systematic Evaluation Program Plants (for action), and all other Power Reactor Facilities with an OL or CP (for in-for: nation) 79-02 Pipe Support Base Pla.t 3/8/79 All Power Reactor Design Using Concrr.te Facilities with Expansion Anchor f>olts an OL or CP 79-03 Longitudinal Ltd Defects 3/ i?.'7is All Power Reactor in ASME SA-312 Type Fac ilities with d 304 Stain 1(ss Steel Pipe an OL or CP Spools Manu'actured by Youngstouc,W91 ding and Engineering company 79-04 Incorrect Wights for 3/30/79 All Power Reactor Swing CNck Valves Fac-flities with an Manufactured by Velan OL or CP Engineering Corporation I
ENCLOSURE 2 LIST OF LICENSEES AND CONSTRUCTION PERMIT HOLDERS RECEIVING IE BULLETIN 79-05 FOR INFORMATION Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN: Mr. A. E. Lundvall, Jr. 50-318 Vice President - Supply P. O. Box 1475 Baltimore, Maryland 21203 Boston Edison Company M/C Nuclear Docket No. 50-293 ATTN: Mr. G. Carl Andognini, Manager Nuclear Operations Department 800 Boylston Street Boston, Massachusetts 02199 Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN: Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Edison Company of Docket Nos. 50-03 New York, Inc. 50-247 ATTN: Mr. W. J. Cahill, Jr. Vice President 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 ATTN: Mr. C. N. Dunn Vice President Operations Division 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power and Light Company Docket No. 50-219 ATTN: Mr. Ivan R. Finfreck, Jr. Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 T/8310
2 Maine Yankee Atomic Power Company Docket No. 50-309 ATTN: Mr. Robert H. Grace Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN: Mr. R. R. Schneider Vice President Electric Operations 300 Erie Boulevard West Syracuse, New York 13202 Northeast Nuclear Energy Company Docket Mos. 50-336 ATTN: Mr. W. G. Counsil 50-245 Vice President - Nuclear 50-423 Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN: Mr. S. L. Daltroff 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN: Mr. J. P. Bayne Resident Manager P. O. Box 215 Buchanan, New York 10511 Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. J. D. Leonard, Jr. Resident Manager P. O. Box 41 Lycoming, New York 13093 O I. 3 Public Service Electric and Gas Company Docket Nu. 50-272 ATTN: Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Rochester Gas'and Electric Company Docket No. 50-244 ATTN: Mr. Leon D. White, Jr. Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Yankee Atcmic Electric Company Docket no. 50-29 ATTH: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Duquesne Light Company Docket No. 50-412 ATTN: Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power & Light Company Docket No. 50-363 ATTN: Mr. I. R. Finfrock, Jr. Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Long Island Lighting Company Docket Nos. 50-322 ATTN: Mr. Andrew W. Wofford 50-516 Vice President 50-517 175 East Old Country Road Hicksville, New York 11801 e = 4 Niagara Mohawk Power Corporation Docket No. 50-410 ATTH: Mr. G. K. Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, New York 13202 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN: Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction (N-4) 2 North Ninth Street Allentown, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352 ATTN: Mr. V. S. Boyer 50-353 Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Hos. 50-354 ATTN: Mr. T. J. Martin 50-355 Vice President 50-311 Engineering and Construction 80 Park Place Newark, New Jersey 07101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN: Mr. W. C. Tallman 50-444 President 1000 Elm Street Manchester, New Hampshire 03105 Rochester Gas & Electric Corporation Docket No. 50-485 ATTN: Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, New York 14649 Metropolitan Edison Company Docket Nos. 50-289 ATTN: Mr. J. G. Herbein 50-320 Vice President - Generation P. O. Box 542 Reading, Pennsylvania 19640 .I
ENCLOSURE 3 SAMPLE LETTER DocketNo(s). Date NAfiE AND ADDRESS Gentlemen: The enclosed Bulletin 79-05 is forwarded to you for infont.ation. No written response is required. If you desire additional information regarding this matter, please contact this office. The Preliminary Notification of the subject incident (Enclosure 1) will c:.utinue to be issued periodically. These will be forwarded to you as t.Sey are issued. Sincerely, Boyce H. Grier Director
Enclosure:
IE Bulletin ?!o. 79-05 with Enclosures fr/8314
UNITED STATES NUCLEAR REGULATORY C0!EISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, DC 20555 APRIL 5, 1979 IE Bulletin 79-05A NUCLEAR INCIDENT AT THREE MILE ISLAND - SUPPLEMENT Description of Circumstances: Preliminary information received by the NRC s',n:e issuance of IE Bulletin 79-05 on April 1,1979 has identified six potential human, design and mec. unical failures which resulted in the core damage and radiation releases at the Three Mile Island Unit 2 nuclear plant. The infonnation and actions in this supplement clarify and extend the original Bulletin and transmit a preliminary chronology of the TMI accident through the first 16 hours (Enclosure 1). 1. At the time of the initiating event, loss of feedwater, both of the auxiliary feedwater trains were valved out of service. 2. The pressurizer electromatic relief valve, which opened during the initial pressure surge, failed to close when the pressure decreased below the actuation level. 3. Following rapid depressurization of the pressurizer, the pressurizer level indication may have led to erroneous inferences of high Nvel in the reactor coolant system. The pressurizer level indication apparently led the operators to prematurely terminate high pressure inje tion flow, even though substantial voids existed in the reactor coolnit system. 4. Because the containment does not isolate on high pressure injection (HPI) initiation, the highly radioactive water from the relief valve discharge was pumped out of the containment by the automatic initiation of a transfer pump. This water entered the radioactive waste treatment system in the auxiliary building where some of it overflowed to the floor. Outgassing from this water and discharge through the auxiliary building ventilation system and filters was the principal source of the offsite release of radioactive noble gases. 5. Subsequently, the high pressure injection system was intermittently operated attempting to control primary coolant inventory losses through the electromatic relief valve, apparently based on pressurizer level indication. Due to the presence of steam and/or noncondensible voids elsewhere in the reactor coolant system, this led to a further reduction in primary coolar:t inventory. 978315 7g g:lc
IE Bulletin 79-05A April 5, 1979 Page 2 of 5 6. Tripping of reactor coolant pumps during the course of the transient, to protect against pump damage due to pump vibration, led to fuel damage since voids in the reacter coolant system prevented natural circulation. Actions To Be Taken by Licensees: For all Babcock and Wilcox pressurized water reactor facil ties with an operating license (the act'ons specified below replace those specified in IE Bulletin 79-05): 1. (This item clarifies and expands upon item 1. of IE Sulletin 79-05.) In addition to the review of circumstances described in Enclosure 1 of IE Bulletin 79-05, review the enclosed preliminary chronology of the TMI-2 3/28/79 accident. This review should be directed toward understanding the sequence of events to ensure against such an accident at your facility (ies). 2. (This item clarifies and expands upon item 2. of IE Eulletin 79-05.) Review any transients similar to the Davis Besse event (Enclosure 2 of IE Bulletin 79-05) and any others which contain similar elenents from the enclosed chronology (Enclosure 1) which have occurred at yourfacility(ies). If any significant deviations frem expected performance are identified in your review, provide details and an analysis of the safety significance together with a description of any corrective actions taken. Reference may be made to previous information provided to the NRC, if appropriate, in responding to this item. 3. (This item clarifies item 3. of IE Bulletin 79-05.) Review the actions required by your operating procedures for ca ing r with transients and accidents, with particular attention to: Recognition of the possibility of forming voids in the primary a. coolant system large enough to compromise the core cooling capability, especially natural circulation capability. b. Operator action required to prevent the formation of such voids. c. Operator action required to enhance core cooling in the event such voids are fomed. 9783.1.G 9
IE Bulletin 79-05A April 5, 1979 Page 3 of 5 4. (This item clarifies and expands upon item 4. of IE Sulletin 79-05.) Review the actions directed by the operating procedures and training instructions to ensure that: a. Operators do not override automatic actions of engineered safety features. b. Operating procedures currently, or are revised to, specify that if the high pressure injection (HPI) system has been automatically actuated because of low pressure condition, it must remain in operation until either: (1) Both 1cw pressure injection (LPI) pumps are in operation and flowing at a rate in excess of 1000 gpm each and the situation has been stable for 20 minutes, or (2) The HPI system has been in operation for 20 minutes, and all hot and cold leg temperatures are nt least 50 degrees below the saturation temperature for the existing RCS pressure. If 50 degree subcooling cannot be maintained after HPI cutoff, the HPI shall be reactivated. c. Operating procedures currently, or are revised to, specify that in the event of HPI initiation, with reactor coolant pumps (RCP) operating, at least one RCP per lcco shall remain operating. d. Operators are provided additional information and instructions to not rely upon pressurizer level indication alone, but to also examine pressurizer pressure and other plant parameter indications in evaluating plant conditions, e.g., weter inventory in the reactor primary system. 5. (This item revises item 5. of IE Bulletin 79 95.) Verify that emergency feedwater valves are in the open position in accordance with item 8 below. Also, review all safety-related valve positions and positioning requirements to assure that valves are positioned (open or closed) in a manner to ensure the proper operation of engineered safety features. Also review related procedures, such as those for maintenance and testing, to ensure that such valves are returned to their correct positions following necessary manipulations. D'iS3 r? i
IE Bulletin 79-05A April 5, 1979 Page 4 of 5 6. Review the containment isolation initiation design and procedures, and prepare and implement all changes necessary to cause containment isolation of all lines whose isolation does not degr ade core cooling capability upon automatic initiation of safety injection. 7. For manual valves or manually-operated motor-driven valves which could defeat or compromise the flow of auxiliary feedwater to the steam generators, prepare and implement procedures which: a. require that such valves be locked in their correct position; or b. require other similar positive position controls. 8. Prepare and implement immediately procedures which assure that two independent steam generator auxiliary feedwater flow paths, each with 100% flow capacity, are operable at any time when heat removal from the primary system is through the steam generators. When two inde-pendent 100% capacity flow paths are not available, the capacity shall be restored within 72 hours or the plant shall be placed in a cooling mode which does not rely on steam generators for cooling within the next 12 hours. When at least one 100% capacity flow path is not available, the reactor shall be made subcritical within one hour and the facility placed in a shutdown cooling mode which does not rel.y on steam generators for cooling within 12 hours or at the marimum safe shutdown rate. 9. (This item revises item 6 of IE Bulletin 79-05.) Review your operating modes and procedures for all systems designed to transfer potentially radioactive gases and liquids out of the primary containment to assure that undesired pumping of radioactive liquids and gases will not occur inadvertently. In p cular, ensure that such an occurrence would not be caused ~ by t esetting of engineered safety features instrumentation. List all s systems and indicate: a. Whether interlocks exist to prevent transfer when high radiation indication exists, and b. Whether such systems are isolated by the containment isolation signal. Eris318
IE Bulletin 79-05A April 5, 1979 Page 5 of 5 10. Review and modify as necessary your maintenance and test procedures to ensure that they require: a. Verification, by inspection, of the operability of redundant safety-related systems prior to the removal of any safety-related system from service. b. Verification of the operability of all safety-related systems when they are returned to service following maintenance or testing. c. A means of notifying involved reactor operating personnel whenever a safety-related system is removed from and returned to service. 11. All operating and maintenance personnel should be made aware of the extreme seriousness and consequences of the simultaneous biccking of both auxiliary feedwater trains at the Three Mile Island Unit 2 plant and other actions taken during the early phases of the accident. 12. Review your prompt reporting procedures for NRC notification to assure very early notification of serious events. For Babcock and Wilcox pressurized water reactor facilities with an operating license, respond to Items 1, 2, 3, 4.a and 5 by April 11, 1979. Since these items are substantially the same as those specified in IE Bulletin 79-05, the required date for response has not been changed. Respond to Items 4.b through 4.d, and 6 through 12 by April 16, 1979. Reports should be submitted to the Director of the appropriate NPC Regional Office and a copy should be forwarded M the NRC Office of Inspection and Enforcement, Division of Reactor Oparations Inspection, Washington, DC 20555. For all other reactors with an operating license or construction permit, this Bulletin is for information purposes and no written response is required. Approved by GAO, B 180225 (R0072); clearance expires 7-31-80. Approval was given under a blanket clearance specifically for identified generic problems. Enclosures : 1. Preliminary Chronology of TMI-2 3/38/79 Accident Until Core Cooling Restored. 2. List of IE Bulletins issued in last 12 months. 378319 to IE Bulletin 79-05A Apr-il 5,1979 PRELIMINARY CHRONOLOGY OF TMI-2 3/28/79 ACCIDENT UNTIL CORE COOLING RESTORED TIME (Approximate) EVENT about 4 #1 Loss of Condensate Pump (t = 0) Loss of Feedwater Turbine Trip t = 3-6 sec. Electromatic relief valve opens (2255 psi) to relieve pressure in RCS t = 9-12 sec. Reactor trip on high RCS pressure (2355 psi) t = 12-15 sec. RCS pressure decays to 2205 psi (relief valve should have closed) t = 15 sec. RCS hot leg temperature peaks at 611 degrees F, 2147 psi (450 psi over saturation) t = 30 sec. All three auxiliary feedwater pumps running at pressure (Pumps 2A and 2B started at turbine trip). No flow was injected since discharge valves were closed. t = 1 min. Pressurizer level indication begins to rise rapidly t = 1 min. Steam Generators A and B secondary level very low - drying out over next couple of minutes. t = 2 min. ECCS initiation (HPI) at 1600 psi t = 4 - 11 min. Pressurizer level off scale ,igh - one HPI pump manually tripped at about 4 min. 30 sec. Second pump tripped at about 10 min. 30 sec. t = 6 min. RCS flashes as pressure bcttoms out at 1350 psig (Hot leg temperature of 584 degrees F) t = 7 min., 30 sec. Reactor building sump nump came on. &M3'do TIME EVENT t = 8 min. Auxiliary feedwater flow is initiated by opening closed valves t = 8 min. 18 sec. Steam Generator B pressure reached minimum t = 8 min. 21 sec. Steam Generator A pressure starts to recover t = 11 min. Pressurizer level indication cornes back on scale and decreases t = 11-12 min. Makeup Pump (ECCS HPI flow) restarted by operators t = 15 mi n. RC Drain / Quench Tank rupture disk blows at 190 p.cig (setpoint 200 psig) due to continued discharge of electromatic relief' valve t = 20 - 60 min. System parameters stabilized in saturated condition at about 1015 psig and about 550 degrees F. t = 1 hour, 15 min. Operator trips RC pumps in loop B t = 1 hour, 40 min. Operator trips RC pumps in Loop A t = 1-3/4 - 2 hours CORE BEGINS HEAT UP TRANSIENT - liot leg temperature begins to rise to 620 degrees F (off scale within 14 minutes) and cold le, temperature drops to 150 degrees F. (HPI water) t = 2.3 hour Electromatic relief valve isolated by cperator after S.G.-B isolated to prevent leakage t = 3 hours RCS pressure increases to 2150 psi and electromatic relief valve opened t = 3.25 hours RC drain tank pressure spike of 5 psig t = 3.8 hours RC drain tank pressure spike of 11 psi - RCS pressure 1750; containment pressure increases from 1 to 3 psig t = 5 hours Peak containment pressure of 4.5 psig t = 5 - 6 hours RCS pressure increased from 1250 psi to to 2100 psi !1/83%1 TIME EVENT t = 7.5 hours Operator opens electromatic relief valve to depressurize RCS to attempt initiation of RHR at 400 psi t = 8 - 9 hours RCS pressure decreaus to about 500 psi Core Flood Tanks partially discharge t = 10 hour 28 psig containment pressure spike, containment sprays initiated and stopped after 500 gal. of Na0H injected (about 2 minutes of operation) t = 13.5 hours Electromatic relief valve closed to repressurize RCS, collapse voids, and. start RC pump t = 13.5 - 16 hours RCS pressure increased frxrn 650 psi to 2300 psi t = 16 hours RC pump in Loop A started., hot leg temperature decreases to 560 degrees F, and cold leg temperature increases to 400 degrees F. indicating flow through s-team generator Thereafter S/G "A" steaming to condemser Condenser vacuum re-established RCS cooled to about 280 cegrees F., 1000 psi Now (4/4) high radiation in contaimment All core thermocouples less than 460 degrees F. Using pressurizer vent valve with small makeup flow Slow cooldown RS pressure negative 378322
IE Bulletin No. 79-05A Date: April 5,1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No. 78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact Operating License Mechanism - General (OL) or Construction Electric Model CR105X Permit (CP) 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority I Material Licensees 78-08 Radiation Levels from 6/12/78 All Power, Test and Fuel Element Transfer Research Reactor Tubes Facilities with an OL having Fuel Element Transfer Tubes 78-09 BWR Drywell Leakage 6/14/78 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL (for action) Closures or CP (for information) 78-10 Bergen-Paterson 6/27/78 All BWR Power Reactor Hydraulic Shock Facilities with Suppressor Accumulator an OL or CP Spring Coils 3783&3 4
IE Bulletin No. 79-OSA Date: April 5,1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED) Bulletin Subject Date Issued Issued To No. 78-11 Examination of Mark I 7/24/78 BWR Power Reactor Containment Torus Facilities with an OL Welds for action: Peach Bottom 2 and 3, Quad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee. All other BWR Power Reactor Facilities with an OL for infonnation 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds
- 01. or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures In Source Heads 10/27/78 All General and of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 7050B, 7051, with the subject 70518, 7060, 70608, 7061 Kay-Ray, Inc.
and 7061B Gauges 14 Deterioration of Buna-N 12/19/78 All GE BWR Faci-Components In ASCO lities with an OL Solenoids (for action), and all other Power Reactor Facilities with an OL or CP (for informationT 976324
IE Bulletin No. 79-05A Date: April 5, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS (CONTINUED) Bulletin Subject Date Issued Issued to No. 79-01 Environmental Qualifica-2/8/79 All Power Reactor tion of Class IE Equipment Facilities with an OL, except the 11 Systematic Evaluation Program Plants (for action), and all other Power Reactor Facilities with an OL or CP (for in-formation) 79-02 Pipe Support Base Plate 3/8/79 All Power Reactor Design Using Concrete Facilities with Expansion Anchor Bolts an OL or CP 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type Facilities with 304 Stainless Steel Pipe a.n OL or CP Spools Manufactured by Youngstown Welding and Engineering Company 79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 79-05 Nuclear Incident at 4/1/79 All Babcock and Three Mile Island Wilcox Power Reactor Facilities with an OL, Except Three Mile Island I and 2 (For Action), and All Other Power Reactor Facilities With an OL or CP (For Information) 3W3325
ENCLOSURE 2 LIST OF LICENSEES AND CONSTRUCTION PERMIT Hr)LDERS RECEIVING IE BULLETIN 79-05A FOR INFORMATION Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN: 'Mr. A. E. Lundvall, Jr. 50-318 Vice. President - Supply P. O. Box 1475 Baltimore, Maryland 21203 Boston Edison Company M/C Nuclear Docket No. 50-293 ATTN: Mr. G. Carl Andognini, Manager Nuclear Operations Department 800 Boylston Street Boston, Massachusetts 02199 Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN: Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Edison Company of Docket Nos. 50-03 New York, Inc. 50-247 ATTN: Mr. W. J. Cahill, Jr. Vice President 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 ATTN: Mr. C. N. Dunn Vice President Operations Division 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power and Light Company Docket No. 50-219 ATTN: Mr. Ivan R. Finfrock, Jr. Vice President Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 3"/ti.326
enclosare 2 2 Maine Yankee Atomic Power Company Docket No. 50-309 ATTN: Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN: Mr. R. R. Schneider Vice President Electric Operations 300 Erie Boulevard West Syracuse, New York 13202 Northeast Nuclear Energy Company Docket Nos. 50-336 ATTN: Mr. W. G. Counsil 50-245 Vice President - Nuclear 50-423 Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN: Mr. S. L. Daltroff 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN: Mr. J. P. Bayne Resident Manager P. O. Box 215 Buchanan, New York 10511 Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. J. D. Leonard, Jr. Resident Manager P. O. Box 41 Lycoming, New York 13093 T/tiO27 3 Public Service Electric and Gas Company Docket No. 50-272 ATTN: Mr. F. W. Schneider Vice Pres 1 dent - Production 80 Park Place Newark, New Jersey 07101 Rochester Gas and Electric Company Docket No. 50-244 ATTN: Mr. Leon D. White, Jr. Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket: No. 50-271 ATTN: Mr. Robert H. Grace Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Yankee Atomic Electric Company Docked: No. 50-29 ATTN: Mr. Robert H. Grace Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Duquesne Light Company Docket No. 50-412 ATTN: Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power & Light Company Docket No. 50-363 ATTN: Mr. I. R. Finfrock, Jr. Vice President 2c0 Cherry Hill Road Parsippany, New Jersey 07054 Long Island Lighting Company Docket Nos. 50-322 ATTN: Mr. Andrew W. Wofford 50-516 Vice President 50-517 175 East Old Country Road Hicksville, New York 11801 y/ti328 4 Niagara Mohawk Power Corporation Docket No. 50-410 ATTN: Mr. G. K. Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, New York 13202 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN: Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction (N-4) 2 North Ninth Street Allertown, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352 ATTN: Mr. V. S. Boyer 50-353 Vice President Engineering and Re:earch 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50-354 ATTN: Mr. T. J. Martin 50-355 Vice President 50-311 Engineering and Construction 80 Park Place Newark, New Jersey 07101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN: Mr. W. C. Tallman 50-444 President 1000 Elm Street Manchester, New Hampshire 03105 Rochester Gas & Electric Corporation Docket No. 50-485 ATTN: Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, New York 14649 Metropolitan Edison Company Docket No. 50-289 ATTN: Mr. J. G. Herbein Vice President - Generation P. O. Box 542 Reading, Pennsylvania 19640 378.329
ENCLOSURE 3 SAMPLE LETTER Docket No(s). Date NAME AND ADDRESS Gentlemen: The enclosed Bulletin 79-05A is forwarded to you for information. Nowrittenresponseisrekuired. If you desire additional infomation regarding this matter, please contact this office. Sincerely, Boyce H. Grier Director
Enclosure:
IE Bulletin No. 79-05A with Enclosures 378330
. Federal Register / Vol. 44.'No.138 / S uesday July 17, id79 / Proposed Ruleav -, A1.g3,. installation bionnation shall be ' ~ for continued operation of a nuclear b Support of Light Wateir Maclear, -- submitted as soon as possible and the facility, and coordbation between the Power Piants." NUREG-c3st:5/ EPA 5::cf. [ sppheant shall permit verification by the licensee plan and State and local plans. 1-78-016. December Isra.See 43 Fed. Intemational Atc=ic Energy Agency - %e Commission seeks wntten. , Reg. 5882 (December 15. Is:78), see also. ~ and take such other action as may be - comments on what items should be 44 Fed. Reg. 23137 (Apeil ta.1979). ' ~ Furthermere, a rumher.cf om=*=tzons.
- _
necessary to implement the US/lAEA included in the rule. Safeguards Agreement.in the manner ^ giTrs: Comments a5e'd' e' nota't'er'than including CriticalMasa and Public u set icrth in il 75A 75.11-75.14 cf'this ' - Interest Re search Geoaps. Inerve renewed, chepter.The Commission will grant an ~ August 31.1979.- - - ~ - - and suppte.mented a petituirm for rul"" Prenously densr d by the b l - ~, exemption from this imi-ent, upon '- conceming 6, en es s -. Commissicm. rmremmg the opershrmm1 i ;. application, if it determmes that the -'" submined to the SeWay of the',- >~ details of evacuation edan-See 44 installation wfIl not be included on the
- g#
CommIalon, muclear Regulaton... FR 32486 Uune a 1s7s).]Q.g, - eJ United States eligible list. ( .. r-mtalan Washington DC::0555. .gg c ,u g Part 170-Fees for FacfDt$es and ron runneE3t D6FOftMATION CONTACTt ' initiate an Wm1=umar W m 1 [ Ltaterials Ucerises and C2her, a w Patricia A. Comella. Site Designation procedure en the & af h adJ~ i-Regulatory Services Undar the Atomic. B*anch. Office of Stanrineds. ^, local emw e % M - Energy Act of 1954, as Arnended Development. Nuclear RegulatorT' - those oflicensees.The ir===d= h is - ~- r Commiuion. Washington, DC :D555, soliciting psblic rr=n=ents ica this area. ~
- 12. Section 170.11is amended by 3-0081' Particularly on the foDowagl: issues:
adding a new paragraph (a)(10) to read supptzastxTARY INPonuAnoec ne NRC
- 1. What s2hould be the h===6 objectrves as follows:
requires that power reactor license cf emergency pl=nn=gt i 170.11 Eaemptona, applicants plan for radiolog' cal
- a. To rec.uce pubbe erh=tmon (a) No application fees, licensee fees, emergencies within their plant sites and exposure?
renewal fees, or inspection fees shall be make arrangemeau with State and local
- b. To pre vent pubBc r=^=+%
required fo. orEa"intions to respond to accidents exposun? 2 that might have consequences be and c.To be & to mb & @- ~ si e boundary, b tMs way o de To what sextent shrumIA themw (10) Act2vities of the Com=ission 8 objectives ide quantir=-f7 - undertaken. pursuant to Part 75 of this th n de p chepter, solely for the purpose of CFR Part 50. Appendix E (1979), see also
- 2. What c:anstituten an eGe ctIve implementation of the US/1AEA additional guidance in U.S. NRC, emergency response plan foc-State and" Safeguards Agnement.
Regulato y Guide 1.101. " Emergency local agencdes? For '- - T What are the essenti.al elements that ret be-
- ~
- Pianning for Nuclear Power Plants."
Dated at Washi:gton. DC this 12th day of (p,y, 3, 3g77), included int an effectrve pine? Do To aid State and local governments in existing hT4C requir==ent= fear hern=ees N' " For the Nudear Regulatory Commission. the development and implementation of (10 CFR Prert 5C. Appenth E3) and _ 5*"I I E adequate emergency plans, the NRC in guidance fear States (hM5/114) s ~ Secreto yofde Co:-on. conjunction with seven other Federal lack any W these emmential eDements? ' m S ar m w-r=te =1 agencies, has attempted, on a
- 3. Should NRC e<==rencra in the sas.o cooe mo-a cooperative and voluntary basis, to associated State andlocal annegj provide for trnmmg and instruction of response pdans be a serpur==*nt for State and local govemment personnel continued caperation of any runclear Adequacy and Acceptance of and to establish criteria to guide the Power platit with an -idntmpt operating Emergency Planning Around Nuciear preparation of emergency plans.
License? If no, when abrmld trais general Facilities However, the NRC has not made NRC requirement bemme eHectme? approval of State and local emergency
- 4. Should prior NRC remr n:rrence in
[10 CFR Part 50] plans a condition of nuclear power plant the associaated State and tr= an) ~ AcEN0Y: U.S. Nudear Regulatory operation. emergency response plans bee a Co=missica. ne accident at nree Mile Island has requiremerat for the===n=nr.. of any rsew acnow: Advance Notice of Proposed raised a number of questions about the operating License fora nec3erar power. Ruiemaking. adequacy of radiological emergency. - plant? If sci. when abould thiis general c. response plans. Even before the . requireme:2t beconne e%ehwre?
SUMMARY
- The Nuclear Regulatory accident the GAO had recommended
- 5. Shound h=~4 1==-4-+-me= be --.. '-
Co=missio::is censidering the adoption that NRC not license new power plants provided tto State andlocalgove nmen+n of additional regulations which will for operation unless off-site emergency for radioicvgical emergency 2 %=----7 lP arminf und prepar+i-S if so,go;- estabhsh as conditions of power reactcr plans have been approved by the NR". operanon increased emergency - GAO. Report to the Congress. " Areas what extrut and by whai mmans? What V - r-sdmess for pubhc protectics in the - Around Nuolear Facilities Should Be should be the source of the i~unrint.. _- ? -. ~ nr.nity of nuclect power reactors on the ' Better Np r.d ForRadiological-
- 6. Shoci d rahla=,-=1 mgp - a
..a response t:irills be a requeurnentf E set 4'l part of both the beensee and lacel and. EmerFencies." March 30,1972.% - under whose anthrwity:Fedc= rat State ar' # i~
- ate authe-ities. he PW" ion is N--widm is also considering new '
itterested L3 receivLng public comment guidsnee to State and local evemments local gove mment? To what.extsat <- F en objectives for effect:ve plans. ' on emerFency pin' -tnf. based on an should Federal. State, sad bcal-. -l ecce;:an::e entenain State / local analysis of a }oint NRC-EPA Task Force governme sts, and L- - i be required <, - - emergen y plans. NRC concurrence in Report. " Pin mMg Basis for Development to partic=wite? J M u-- Mate and local plans as a requirement of State and Local Govemment. - ~ 7.How.ssd to whalrrinerrt should the 2 " 2 io.-issuunce of en operatmg 1. cense or. Radiolog: cal Emergency Respo:.se Plans public_be Enfo:med,piticeio any ..oi 0}L, m .p- - v M 7331 .7 .~,q, .~ --~, = wQs-... -. ..g 2:t :... ~ g,
Retdstar ues ay, y ,g emergency, coocerning eme=Tency M the re- - - Under
- M actions it might be caBed upon to take?
Am<=8 3.OE. Service M @ M E "JyMM,
- 8. What actrons should be taken in Seasbry of the t'amissiaa.
.. Vah M h & W or. response to the recommendations of the tra om. were ps.a s.es.= e,s emi e@any in hh ann"=ne ammig ;, be li-A and m'e1 certazn =+ =-ideds t joint NRC/ EPA Task Form Report es.a.se oaostsa
- e (NUREG. C3G6/ EPA 53)/1-78 416)?
- that ensrcre its couthm=1 safety, p=ntyg.] Potency. and ehw-== W -".n"r, esc r P
- 9. Under what anannstances and w; 3 mqmrments far*IyphcncLVaerme usmg what citeria should a lan=,,
DEPAPTntENT OF HEA!.TH, ' first e:W*W cs1.h=A-E.1953. I [ D . EDUCAT m A W ARE- ~ and revuned out 5 .dtw.,..N k F -enautJ ne41909(3w -~ ww. bo to whai extent.-d ay whom should the pubbe be notified of... Food and w.tmtico the Feducalf ; - a 4 FR 8914) ands--whhi as EI a m in. $y these incidents? C - (21 CFR Part $20] - -- through erttis (21 CFR n=n sn umg,,g { g,,,.,,,,rts momed wiu be. .s 83L15). om NoemmebermLss2taa PR Q I conected and evalaated by the NRC _. - (Docket Mo.7eeW251 *.'# ,M
- v 3 X ) "* I et n ?.a{ct of the : s..c.,g,[
... n 4.ia. wiD. in tum. :=b=it ' - ~ ~ - Em,menciations onrM rules to. Bacterial Products; Additional adAsr==u2 =*==d= da (21 CFR sm1.14(ct).-tg }; the Ce==i=* Raaid on the r=rmts Standards for Typhoid Vaccine Typhoid?Faccasus abn3 mcd be insamd by ;3, J the mannetumsd Wen it receives from the p=hlic and the Aost:rr: Food and Drug Adm%tration. ,,,y, analysu of the problem pmsected by the ~** ~ Ac Proposed Rule. NRC Staff. the Cwi== ion will received &om the Directar. Bureau ofi 2 S. I determine whether to proceed with a suuuAstr:%e Food and Drug Biologics SBOB). Offir,=1 written release ' proposed rule for notia and enmm.-at Administrrition (FDA) is proposing to is issef mly h the Dumcsae has.,, p and/or whether to make such rule amend the biolopes Typhoid Vaccine revied:he W and tested immediately efective. The Ceduton reguistions to ensure fusther the samples ta ensure the con 6nned safety. _, * [ anticipates completion of this expedited antige tic integrity of the Ty 2 strain of purity, pernency,and efEectivenema of rulemalnng in approximately six ba eter a.used in vaa:ine production and TyphoidWaccm. - y months. to reqdre that licenscd manufacturers On the.h of new scientific ne NRC staffis presently conducting obtain the U.S. Opacity Standard from knowledp d M imi product release a comprehensive review of allaspects of the Bare u of Biologics.h FDA ts also data ac=:nanlated azadassalyzed by BOB ~ the NRC eme'Fency pla*2 and proposing to ame.,d these regulations by for the pa st several years. FDA is 3 preparedness program.hrefore, the establishirg new standards for the Propos2na; ament-ments to the additional i Commission is also interested in performant.e and results of the potency standarms:s for Typhend V =mn. 1 receivmg co=ments on all other aspacts test for ead. lot of manufactured includict.^ 2he foliawms:: t of emergency plann!ng. indning issues Typhoid Vaccine. (1) Strwi=s Ty 2 of E J. mBa typhorcr raised in the Critical Mass /PIRG DATES:Co= ment by September 17,1979. is used in.the "-"#*"e of Typhoid ? petition for rulemaking and questions Vacx:me_*To ensa:re the a4 such as the followmg. AD REss rines comments to the
- 10. How and to what extent should the Hearicg Clerk (IFA-305) Food and integritya:f the Ty 2 strazn. FDA Es a:
concems of State and local orernments D g Ahatraen. Rm. W EO propo,qo,,,,,,,# g e rm m m F 6':0.11) tes require that azztzgenic izztegrsty be inecaporated into Federal Fishers Izne, Rodmile, MD ::0837, t be veriSsd by tne& urin of W radiolopcal emergency response FOR RATHER &MFORAAATION col (TACT: hacteria huf a TyO. -- '- plamung? MichaelI.Hootue.B zreau ofBiologies (2) To cuarify the source for obemmne [
- 11. How should Federal agendes (HFB-620). Food and Dru8 necessaryreference 46ds. FDA '
interface with State and local Admimatration. Department of Heali. proposen..m ame.nd $ stmva m CFR Fevernments and the licensee durmg Education. and Welfare,8800 Rockville 6':0.12) ter require that the U.S. Stazrdard i emergencies? Pike. Be AaaA a, hO 20014. 301-443-1306-Typhoid var r-rne and the U.S. Opa. city a
- 10. Should the licensees be required to supet.asaEXTARY 9tFORWATrote The Standartf he obt=hd_ from the Bureau provide radiological emergency Commissioner is proposing to amend the of Biolocras.
response traicing for State andlocal bioiopes regulations for manufactunng dilutionsumf the r=m= and eb-hn=e.. - t( (3) SaE:rne is Wmmifor use ha government personnel? If so, to what Typhoid Vamne by setting potency extent? Should the Federal govemment standards for the Ty 2 strain of doses n=ed in the potency test. nae" nae -~ [ provide such trammg? If so, to what Salmonella typhosa used in the of phoeptuate-b=Kered==1.ns-(PBS)b the BOB iaas une wa==ha 9 in any-( extentf mannfar*rre of Typhold Vamna and by
- 13. To what extent should rehant e be, revising the potency test under i n;:0.13 de w = W -A-
-ist the potency test. - I placed on licensees for the asaaermant (::1 CFR a n1.1) en-aiatent with new Accordirr.g:ly. FDA is porpassag to a,n.nA 1 cf the actual cr potential r-arp-scientific knowledge denved from past i a'n 12rbd(1) and (cX2) an ymnr the use of an amA-t with regard to imtiatica experianc= with the product. of PBS fer rMnt>=mtr. the==.cr a.w time of protective action? To what extent in the Umted States, typhoid disease challeapr.and vandance erweir,.i= of e ' '! should this responsibility be bome by - has been in abelma in rece=1 years and Stram T f 2 ofhb % g,g _ f Federal, State oc local gm..- ? routme typhoid va:cination is no locger (4) Basresi on *=+i-eur=1 a __ :. need - U
- 14. Wocid public partidpaticein recocunended. However, im=*= tion - in, and 2v salts amoved fruen.
r 6 elopes) emerFeney m.w dMs. is indacated if a person has come into . Vaccme ;xxency testa pairfr-W3 at tbs _ indudmg evacuatacc. serve a useful contact witn a known typhoid camer. if BOB. FD.A is > 5-J o manned ' purpose? If so, what aooald be tne there ts an octbreak of typhoid feverin i a:0.130e) to recparra that new s:catastical extent of the pubbe panacpatum? the cootmedty, or if a person plans to methoda oe==ar' fnr deter ***ig tne i] Dated at Wastaapac. D.C. tha 11 tin day of travel to an area waere typhoid fever is validity czi tne 9 - 7 assi. Fa- -s' jury.ts E
- eDorcuc, mneintmeir 7.FDA peoposes so u --
t. D ~ -N ..s 4 100RORIGWR "?" - i ~ f
t STATE OF MICHIGAN DUBUC SERVICE COMMISSION M.) 6545 MERCANTILE WAY Dan +ei J. Comlow. Chairman p.s} P.O BOX 30221 Lt toa. G Scultmorp b,- LANSING. MICHIGAN 48909 Was Vae King WILLIAM G. MILLIKEN, Governor DEPARTMENT OF COMMERCE WILLIAM F. McLAUGHUN. Director April 9,1979 Mr. Joseph R. Hendrie, Chairman U. S. Nuclear Regulatory Commission 1717 8th Street Wa shin gton, D.C. 20545
Dear Mr. Hendrie:
The Three Mile Island Nuclcar Power Plant accident is cf vital interest to the nichigan Public Service Commission, as well as of interest to many other agencies and indiv13::als. Although your agency has primary responsibility in this matter, future decisions may affect plan t design, avail ability, and cost of electric service. These are issues which are at least in part under the jurisdiction of my Commission. I, therefore, request that you provide me and/or members of my sta!! the opportunity to receive information on the cause and control of the accident, on the con-duct of emergency actions, and on activities of your agency in investigating and modifying accident potential at other plants. Please provide information on the following:
- 1) Results of NRC activities in determining whether there is any significant potential for any such accident to occur in Michigan;
- 2) NRC actions that might affect avai1abi1ity af nuclear power plants presently operating in this state;
- 3) NRC or other actions or plans that might affect the design or licensing ability of nuclear power plants presently under design or under construction in this state;
- 4) Emergency activities surrounding the Three Mile incident that might be useful to our state during our present re-examination of Michigan's nuclear emergency planning;
- 5) Calculations or estimates that you might have of the change in cost of electric power that any of the activities refer-enced above might have a:; in-state power plants.
I understand that some of the activities referenced above may not he under the jurisdiction of your agency; however, I will be most apprecia ti ve c! any assistance your agency can provide us. e-..-s-(,_ Dani el Damlow, Chairman nichigan E-ublic Ecrvice Commission /8,333}}