NRC Generic Letter 1980-37
| ML031350386 | |
| Person / Time | |
|---|---|
| Issue date: | 05/07/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| GL-80-037, NUDOCS 8006090165 | |
| Download: ML031350386 (150) | |
UNITED STATES
A 32 NUCLEAR REGULATORY COMMISSION
a IWASHINGTON, D. C. 20555 May 7, 1980
TO ALL OPERATING REACTOR LICENSEES
SUBJECT: FIVE ADDITIONAL TMI-2 RELATED REQUIREMENTS TO OPERATING REACTORS
Gentlemen:
Over the past few months, the NRC has been developing its requirements that flow from various reviews following the TMI accident of March 28, 1979.
All TMI-related issues are being included in the NRC's TMI Action Plan.
On September 13, 1979, you were informed of the first set of TMI-related actions based upon Lessons Learned that were required for operating reactors.
On February 8, 1980, the Commission preliminarily approved the Near-Term Operating License requirements of the TMI Action Plan. There are five items that are applicable to operating reactors and constitute a second set of requirements for operating reactors. They are as follows: (1) I.A.1.3- Shift Manning; (2) I.A.3.1 - Licensing Examinations: (3) I.C.5 - Licensee Dissemination of Operating Experiences; (4) II.K.3 - LOFW and Small Break LOCA Generic Review Matters; and (5) III.D.3.4 - Control Room Habitability.
These matters are specified in the Task Action Plan (NUREG 0660, May 1980).
Items 1, 2, 3 and 5 involve actions for all reactor plants whereas item 4 concerns only specific light water reactor types. Item 4 involves 28 separate actions; i.e., 15 for BWR plants (including 1 for Big Rock); 7 for PWR plants (including 3 for Westinghouse designs); and 6 for all light water reactor plants. Five of the items are applicable to Fort St. Vrain.
Requirements for the implementation of each of these actions are provided in this letter, except for items (1) and (2). Item (1) will be provided shortly through separate correspondence and Item (2) was provided to you by letter dated March 28, 1980.
The implementation schedule for the five action items as they apply to the various operating reactor designs is given in Enclosure (1). Enclosure
(2); (3) and (4) are specific with regard to the three remaining items as they apply to any specific plant design. Each enclosure consists of two parts; i.e., the first part is the staff requirement and the second part is a copy of the applicable section of the plan. The NUREG reports referenced in these enclosures will be provided to you shortly through separate correspondence.
g0 06 9 /667
-2- I;.
Each of the specific actions includes an implementation schedule as to how and when the particular action is to be carried out. Three classes are indicated; i.e., Class 1 involves no hardware changes and requires that the action is to be implemented by the specified date; Class 2 involves possible hardware changes that may be effected without prior staff review;
and Class 3 involves hardware changes that would be made subsequent to staff revfiew and approval.
You are requested to reply within 30 days stating your commitment to meet these requirements and associated schedules.
incerely, Darrell G. Eienhut, Director Division of L censing Enclosures:
Additional Operating Requirements as Stated
ENCLOSURE 1 IMPLEMENTATION SCHEDULE & SUMMARY
CLASS OF,
ITEM TITLE APPLICABILITY ACTION%'J IMPLEMENTATION SCHEDULE
I.A.1.3 Shift Manning LWRs* I Personnel Requirements: July 1, 1982 Overtime Procedures: August 1, 1980
I.A.3.1 Revise Scope and Criteria for Licensing Examinations LWRs* I May 1, 1980
Procedures for Feedback of Operating Experience to Plant Staff LWRs* I January 1, 1981 II.K.3 Final Recommendations of B&O
Task Force [Measures to Mitigate Small Break. Loss-of-Coolant Accidents and Loss of Feed- Water Accidents]
II.K.3.1 PWRs III Proposed design: July 1, 1981 Test: First refuel II.K.3.2 PWRs I January 1, 1981 II.K.3.3 LWRs I January 1, 1981 II.K.3.5 PWRs I Study: January 1, 1981 Modify: January 1, 1982 II.K.3.9 W PWRs II July 1, 1980
II.K.3.10 W PWRs III Plant by Plant as requested by licensees II.K.3.12 W PWRs III July 1, 1980
II.K.3.13 BWRs II Analysis: October 1, 1980
Implementation Date: April 1, 1981 II.K.3.14 BWRs II January 1, 1981
Page 2 CLASS ?F
TITLE APPLICABILITY ACTION?' ) IMPLEMENTATION SCHEDULE
ITEM
II.K.3 II.K.3.15 BWRs II January 1, 1981 II.K.3.16 BWRs III Feasibility Study: January 1, 1981 Proposed System Mod: January 1, 1982 II.K.3.17 LWRs* I January 1, 1981
.II.K.3.18 BWRs III Feasibility Study: January 1, 1981 Proposed Modifications: January 1, 1982 II.K.3.19 BWRs II January 1, 1981 II .K.3.20 Big Rock Pt. I January 1, 1981 II .K.3.21 BWRs III Design: January 1, 1981 Modify: Refueling II .K.3.22 BWRs II Verify Design: January 1, 1981 Modify Design: January 1, 1982 II.K. 3.24 BWRs II January 1, 1982 II .K.3.25 PWRs I January 1, 1982 II .K.3.27 BWRs II October 1, 1980
II .K.3.28 BWRs II January 1, 1982 II .K.3.29 LWRs I April 1, 1981 II.K.3.30 LWRs I July 1, 1983 II.K.3.31 LWRs I After 1983 II.K.3.44 LWRs I January 1, 1981 II.K.3.45 BWRs I January 1, 1981 - . l
Page 3 CLASS 9 ITEM TITLE APPLICABILITY ACTIONk l IMPLEMENTATION SCHEDULE
II.K.3 II.K.3.46 BWRs I July 1, 1980
II.K.3.57 BWRs I October 1, 1980
III.D.3.4 Control Room Habitability LWRs * II Review: January 1981 Modify: January 1983 t'JClass of Action:
I - Analysis/Evaluation/Procedural Changes II - Post-implementation review of modifications III - Pre-implementation review of modifications
- This item also applies to Fort St. Vrain
ENCLOSURE 2 PROCEDURES FOR FEEDBACK OF
OPERATING EXPERIENCE TO PLANT STAFF
PART 1: Staff Requirements I.C.S'
PART 2: Copy of Section I.C. to NRC Task Action Plan
STAFF
- l.C.5 PROCEDURES FOR FEEDBACK OF OPERATING EXPERIENCE TO PLANT
POSITION
for Feedback of In accordance with Task Action Plan I.C.5, Procedures shall review its Operating Experience to Plant Staff, each licensee assure that operating infor- procedures and revise them as necessary to within and outside mation pertinent to plant safety originating both to operators and other the utility organization is continually supplied retraining programs.
personnel and is incorporated into training and These procedures shall:
for review
(1) Clearly identify organizational responsibilities informa- of operating experience, the feedback of pertinent tion to operators and other personnel and the incorporation of such information into training and retraining programs;
steps
(2) Identify the administrative and technical byreviewthe operating ex- necessary in translating recommendations changes perience assessment group into plant actions (e.g.>
to procedures; operating orders);
of information Identify the recipients of various categories personnel,
(3) STA's, from operating experience (e.g., Supervisory H. P. technicians) or other- operators, maintenance personnel, can be wise provide means through which such information readily related to the job functions of the recipients.
become aware
(4) Provide means to assure that affected personnel importance that of and understand information of sufficient training and re- should not wait for emphasis through routine training programs;
extraneous
(5) Assure that plant personnel do not routinely receive in such and unimportant information on operaTing experienceor otherwise volume that it would obscure priority information detract from overall Job performance and proficiency;
or contradictory
(6.) Provide suitable checks to assure that conflicting personnel information is not conveyed to operators and other until resolution is reached; and,
(7) Provide periodic internal audit to assure that the feedback program functions effectively at all levels.
DISCUSSION
experience assessment Each utility is expected to carry out an operating having collective competence function which will involve utility personnel with this assessment in all areas important to plant safety. In connection that important function it is important that procedures exist to assure
- 2 -
information on operating experience originating both within and outside the organization is continually provided to operators and other personnel and that it is incorporated into plant operating procedures, and training and retraining programs.
Those involved in the assessment of operating experience will review in- formation from a variety of sources. These include operating information from the licensee's own plant(s), publications such as IE Bulletins, Circulars and Notices, and pertinent NRC or industrial assessments of operating experience. In some cases, information may be of sufficient importance that it must be dealt with promptly (through instructions, changes to operating and emergency procedures, issuance of special precautions, etc.) and must be handled in such a manner to assure that operations management personnel would be directly involved in the process.
In many other cases, however, important information will become available which should be brought to the attention of operators and other personnel for their general information to assure continued safe plant operation.
Since the total volume of information handled by the assessment group may be large it is important that assurance be provided -that high-priority matters are dealt with promptly and that discrimination is used in the feedback of other information so that personnel are not deluged with unimportant and extraneous information to the detriment of their overall proficiency. It is Important, also, that technical reviews be conducted to preclude premature dissemination of conflicting or contradictory infor- mation.
CLARIFICATION
Review of and modifications to procedures governing feedback of operating experience to plant staff shall be completed and the procedures put into effect on or before January 1, 1981.
ACTION: (Class I)
(1) Licensee to implement actions and submit documentation of the method for staff review by scheduled dates.
The following thirteen pages are from the May 1980
version of the TMI Action Plan, NUREG 0660,Section I.C. and only This section is provided for background information respect to note that the subject item being discussed with to our position on I.C.5. is a-subpart.
Task I.C
May 1980
TASK I.C OPERATING PROCEDURES
A. OBJECTIVE: Improve the quality of procedures to provide greater assurance that operator and staff actions are technically correct, explicit and easily understood for normal, transient, and accident conditions. The overall content, wording, and format of procedures that affect plant operation, administration, of maintenance, testing, and surveillance will be included. A principal part this work is to improve procedures for dealing with abnormal conditions and emergencies by improving the delineation of symptoms, events, and plant condi- tions that identify emergency or off-normal situations that confront the operators and, once identified, to assure consistency with operator training.
B. NRC ACTIONS: NRC has taken action, and will take further action, to assure immediate improvement of selected emergency operating and some other operating procedures for operating reactors and near-term operating license applicants. Specific actions are being taken for near-term operations, and actions that will lead to new and better procedures will then be considered for the longer term. In the long term, symptoms-oriented approaches to abnormal and emergency procedures will be evaluated. This effort will be coordinated with control room, simulator, and training improvements. These actions will be integrated with new operating instruments for diagnostic purposes based on the assumption that adequately trained personnel can perform the specified actions. The need for coordination and training of plant per- sonnel is recognized.
1. Short-term accident analysis and procedures revision.
a. Description: There is an ongoing three-phase program for improving the analysis of design basis and off-normal transients and accidents and the procedures for handling such transients and accidents (see NUREG-0578, Sec. 2.1.9)
(1) Small-break loss-of-coolant accidents (LOCAs). NRR sent letters of September 13 and 27, October 10 and 30, and November 9, 1979 referencing Section 2.1.9 of NUREG-0578 to licensees of operating plants, pending operating I. C-1
Task I.C
May 1980
license applicants, licensees of plants under construction, and applicants for construction permits. The staff required that analyses be performed and guidelines prepared to develop emergency operating instructions for handling small-break loss-of-coolant accidents. Appropriate retraining of operators was also required (see also Item I.A.2.1). Guidelines were prepared for each class of operating plants and were reviewed and approved by the NRR staff.
Detailed emergency operating procedures have been or are being prepared for each operating and near-term operating plant to implement the approved guide- l.ines for handling small-break LOCAs. An NRC audit team (with NRR leading and IE participating) performed reviews of procedures for lead plants designed by each reactor manufacturer. Procedures for the remaining operating plants will be reviewed by IE. For each plant that is being reviewed for an operating license, NRR and IE will review the small-break LOCA emergency operating instructions.
(2) Inadequate core cooling. In letters of September 13 and 27, October 10 and 30, and November 9, 1979, NRR required operating licensees, pending operating license applicants, licensees of plants under construction, and applicants for construction permits to perform analysis including preparation of emergency procedure guidelines and to develop procedures and conduct training to assist the plant operating staff to (a) recognize and prevent impending core uncovering and (b) recover from a condition in which the core has experienced inadequate core cooling (see also Item I.A.2.1). An NRR team, with IE members, will review these procedures on an audit basis for lead operating plants. 1E
will review the procedures for the remaining operating plants.
(3) Transients and accidents. In letters of September 13 and 27, October 10 and 30, and November 9, 1979, NRR required licensees of operating plants, operating license applicants, licensees of plants under construction, and pending construction permit applicants to perform analyses of transients and accidents, prepare emergency procedure guidelines, upgrade emergency procedures, including procedures for operating with natural circulation condi- tions, and to conduct operator retraining (see also Item I.A.2.1). Emergency procedures are required to be consistent with the actions necessary to cope I. C-2
Task I.C
May 1980
with the transients and accidents analyzed. Through discussions with the owners' groups, NRR provided guidance for the performance of this task. NRR
will review the responses, which are due in early 1980. In the course of the review of these matters on B&W designed plants, the staff will followup on Bulletin and Orders matters relating to analysis methods and results, as listed in Appendix C. See Table C.1, Items 3, 4, 16, 18, 24, 25, 26, 27;
Table C.2, Items 4, 12, 17, 18, 19, 20; and Table C.3, Items 35, 37, 38, 39,
41, 42, 47, 55, 57.
(4) Confirmatory analyses of selected transients. In addition to the analyses performed by the reactor vendors, analyses of selected transients will be performed by NRR, usinig the best available computer codes, to provide the basis for comparisons with the analytical methods being used by the reactor vendors. These comparisons, together with comparisons to other data, will constitute the short-term verification effort to assure the adequacy of the analytical methods being used to generate emergency procedures. (See also Item II.E.2.2.) These analyses in the case of the B&W design will also be used to establish whether core-barrel check valves have been adequately modeled in the analysis by the vendor since the Three Mile Island accident.
b. Schedule.
(1) Guidelines for handling small-break LOCAs at operating reactors were reviewed and approved by NRR Bulletins and Orders Task Force in late
1979. Reviews of lead operating plants were performed as indicated in NUREG-0645.
1E will conduct reviews of remaining operating plants by June 1, 1980. Reviews of operating license applicants will be consistent with operating license review schedules.
(2) Audits of lead operating plants will be completed in FY80.
1, Reviews for the remaining operating plants will be conducted by IE by April
1981. Reviews of operating licensee applicants will be consistent with operating license review schedules.
I.C-3
-
Task I.C
May 1980
(3) Reviews of analyses of transients and accidents are to be initiated upon receipt of submittal from licensees and applicants in early
1980.
(4) Confirmatory analyses of selected transients are to be complete by June 1980.
c. Resources: NRR FY80 - 3.5 my and $50,000, FY81 - 6.0 my; IE FY80 -
5.0 my, FY81 - 4.0 my; ADM FY80 - 0.1 my and $17,000, FY81 - 0.1 my and $17,000.
2. Shift and relief turnover procedures.
a. Description: Shift and relief turnover is required to ensure that each oncoming shift is aware of critical plant status information and system availability prior to assuming duty. To assure that these functions are adequately prescribed, NRR issued requirements in letters dated September 13 and 27, October 10 and 30, and November 9, 1979, to licensees and applicants to review and revise as necessary shift and relief turnover procedures. See also Table C.1, Item 5b, and Table C.3, Items 6 and 52.
b. Schedule: This work is complete except for IE confirming implementation.
c, Resources: IE FY80 - 0.1 my; NRR FY80 - 0.1 my.
3. Shift supervisor responsibilities.
a. Description: In letters of September 13 and 27, October 10 and 30,
and November 9, 1979, NRC required licensees and applicants to review and revise as necessary plant procedures and directives to assure that the duties, responsibilties, and authority were properly defined to establish a definite line of command and clear delineation of the command decision authority of the supervisor in the control room relative to other plant management personnel.
These letters also emphasized the primary management responsibility of the shift supervisor for safe operation of the plant. Training programs for shift supervisors were required to emphasize and reinforce the responsibility for I.C-4
Task I.C
May 1980
to assure safe safe operation and management function of the shift supervisor operation of the plant.
b. Schedule: This work is complete except for IE confirming implementation.
c. Resources: IE FY80 - 0.1 my; NRR FY80 - 0.1 my.
4. Control room access.
10 and 30,
a. Description: Letters dated September 13 and 27, October requiring that and November 9, 1979, were sent to all licensees and applicants of control room the authority and responsibilities of the person in charge the control room in access and clear lines of authority and responsibility in item 2.2.2.a of the event of an emergency be established in conformance to NUREG-0578.
b. Schedule: This work is complete except for IE confirming implementation.
c. Resources: IE FY80 - 0.1 my; NRR FY80 - 0.1 my.
5. Procedures for feedback of operating experience.
be reviewed a. Description: NRR will require that licensee procedures experience originating and revised as necessary to assure that important operating to operators both within and outside the organization is continually provided retraining programs.
and other personnel and is incorporated into training and dealt with promptly These procedures will assure that high-priority matters are or instructions while keeping operating personnel from being deluged with paper proficiency. See on less important matters to the detriment of their overall also Table C.3, Item 52.
1980. IE will b. Schedule: The requirement will be issued by May 15, audit implementation in normal course of routine inspections.
c. Resources: NRR FY80 - 0.3 my, FY81 - 0.1 my; IE FY60 - 0.2 my.
I.C-5
Task I.C
May 1980
6. Procedures for verification of correct performance of operating activities.
a. Description: NRR will require that licensees procedures be reviewed and revised, as necessary, to assure that an effective system of verifying the correct performance of operating activities is provided as a means of reducing human errors and improving the quality of normal operations. This will reduce the frequency of occurrence of situations that could result in or contribute to accidents. Such a verification system may include automatic system status monitoring, human verification of operations and maintenance activities, independent of the people performing the activity (see NUREG-0585, Recom- mendation 5) or both.
Implementation of automatic status monitoring if required will reduce the extent of human verification of operations and maintenance activities but will not eliminate the need for such verification in all instances. The procedures adopted by the licensees may consist of two phases - one before and one after installation of automatic status monitoring equipment, if required, in accordance with Item I.D.3. See also Table C.1, Item 5.
b. Schedule: The requirement will be issued by July 1, 1980. IE will audit implementation in normal course of routine inspections.
c. Resources: NRR FY80 - 0.2 my; IE FY81 - 0.3 my.
7. NSSS vendor review of procedures.
a. Description: Applicants for near-term operating licenses will be required to obtain NSSS vendor review of low-power and power-ascension test and emergency procedures (see Regulatory Guide 1.33, Appendix A, Section 6) as a further verification of the adequacy of the procedures. After trial use of this requirement on a few pending operating license applications, the staff will decide whether its further use or expansion to include procedure review by the A-E is desirable. This decision will be made in light of the long-term program described in Item I.C.9. See also Table C.1, Item 4a and Table C.3, Item 50.
I.C-6
Task I.C
May 1980
It will b. Schedule: The requirement will be issued by May 15, 1980.
audit implementation in the normal course of routine inspections.
c. Resources: NRR FY80 - 0.1 my, FY81 - 0.1 my; IE FY80 - 0.1 my, FY81 - 0.2 my.
operating
8. Pilot monitoring of selected emergency procedures for near-term license applicants.
a. Description: An interdisciplinary and interoffice NRC task force license will audit emergency procedures received from near-term operating symptoms applicants. They will look especially at the sections that discuss of and immediate actions. This review will provide a sense of the adequacy task the emergency procedures. In conjunction with the procedure review, the postulated force will also review the training related to the symptoms of the transients.
procedures.
The task force will conduct an in-depth review of selected emergency The basic elements of the review will be the following: (1) select specific of procedures for review (e.g., small-break LOCA, loss of feedwater, loss were reset alternating current and restart of engineered safety features that
(2)
prior to power loss, steam-line break, or steam-generator tube rupture);
the meet with the vendor to discuss analyses and guidelines; (3) meet with walk-through applicant to discuss procedure preparation; (4) observe a simulator
(5)
of the selected procedures (with shift crew and shift technical advisor);
(observe observe a plant walk-through for one of the emergency procedures shift crew, shift technical advisor, technical support center operation, pre- operational support center operation, etc.); and (6)make findings on See also paredness for the accidents covered by the selected procedures.
Table C.1, Item 4a and Table C.3, Item 49.
b. Schedule: This work will be completed on each pending operating applicant.
license application prior to issuing a full-power license for that to a few Consideration will be given in FY81 to the extension of this program prior to operating plants of different design to increase the experience base conclusion of item I.C.9.
I.C-7
Task I.C
May 1980
c. Resources: NRR FY80 - 3 my, FY81 - 2 my; IE FY80 - 1.3 my, FY81 -
5 my; ADM FY80 - 0.2 my and $7,000.
9. Long-term program plan for upgrading of procedures.
a. Description: NRC will develop a long-term program plan that will integrate and expand on current efforts in the writing, reviewing, and monitoring of plant procedures. NRR will lead this effort and will receive significant support from IE, SD and RES. Studies to be considered in the plan will include how best to write plant procedures to assure that the wording of procedures is clear and concise; that the content of procedures reflects both engineering thinking and operating practicalities; and that the format of procedures is clear including clear diagnostic instructions for identifying the particular abnormal conditions confronting the operator. Studies will also address the proper interrelationships among administrative, operating, maintenance, test and surveillance procedures; and the depth and content of regulatory and licensee review and monitoring of procedures.
The scope of the plan will include the transient analyses that form the basis of many of the emergency procedures, reliability analysis, human factors engineering, crisis management, and operator training. Plant conditions in addition to those pertinent to the design basis will be considered, as well as administrative prohibitions to prevent improper operator actions during accident conditions that could cause serious threat to reactor safety. The plan will be coordinated with applicable industry groups. See also Table C.3, Item 49, 50,
and 5L.
b. Schedule: The plan will be developed by July 1981.
c. Resources: NRR FY80 - 0.5 my, FY81 - 2 my; IE FY80 - 0.5 my, FY81 -
1 my; SD FY81 - 0.5 my; RES FY80 - 0.1 my, FY81 0.3 my.
I.C-8
rv __
Task I.C
May 1980
C. LICENSEE ACTIONS
1. Short-term accident analysis and procedures revision.
a. Description: The effort underway to improve design-basis and off-normal transient accident response and procedures has been coordinated through owner's groups and with individual licensee representatives. The three-phase effort is as follows:
(1) Small-break loss-of-coolant accidents (LOCAs). Licensees and applicants are required to perform small-break loss-of-coolant accident analyses, prepare emergency procedure guidelines, implement appropriate emergency procedures, and retrain operators.
(2) Inadequate core cooling. Licensees and applicants are required to perform analysis of inadequate core cooling, prepare emergency procedure guidelines, implement appropriate emergency procedures, and conduct retraining.
(3) Transients and accidents. Licensees and applicants are required to perform analysis of accidents and transients, prepare emergency procedure guidelines, implement appropriate procedures, and retrain operators.
b. Implementation.
(1) Operating reactors were required to complete small-break loss- of-coolant accident analysis, guideline preparations procedure revision, and retraining of operators by January 1, 1980. Operating license applicants must complete the work prior to fuel loading.
(2) Operating reactors were required to complete analyses, guideline preparation procedure revision, and retraining by January 1, 1980. Operating license applicants must complete the work prior to fuel loading.
(3) Analyses of transients and accidents are to be completed for operating reactors in early 1980. Implementation of emergency procedures and I.C-9
Task I.C
May 1980
retraining related to accidents and transients are to be completed for operating reactors 3 months after emergency procedure guidelines are established.
Operating license applicants must complete the work on the same schedule as operating reactors or before operating licensed issuance, whichever is later.
c. Resources: FY80 - 4.6 my per plant, FY81 - 1.0 my per plant.
2. Shift and relief turnover procedures.
a. Description: Licensees are to revise plant procedures for shift and relief turnover to ensure that each oncoming'shift is made aware of critical plant status information and system availability.
b. Implementation: Operating reactors were required to complete procedure revision by January 1, 1980. Operating license applicants are to complete this work prior to fuel loading.
c. Resources: 0.1 my per plant.
3. Shift supervisor responsibilities.
a. Description: Licensees are to revise plant procedures to assure that duties, responsibilities, and authority of the shift supervisor and control room operators are properly defined.
b. Implementation: Operating reactors were required to complete procedure revision by January 1, 1980. Operating license applicants are to complete this work prior to fuel loading.
c. Resources: 0.1 my per plant.
4. Control room access.
a. Description: Licensees are to revise procedures to assure that instructions covering the authority and responsibilities of the person in I.C-10
Task I.C
May 1980
in the control charge of access and clear lines of authority and responsibility room in the event of an emergency are established.
to complete procedure b. Implementation: Operating reactors were required are to complete revision by January 1, 1980. Operating license applicants this work prior to fuel loading.
c. Resources: 0.1 my per plant.
staff.
5, Procedures for feedback of operating experience to plant procedures a. Description: Each licensee will review its administrative its organization to assure that operating experience from within and outside and is incorporated in is provided to operators and other operations personnel training programs in accordance with NRC instructions.
January 1, b. Implementation: Operating reactors will complete by to fuel loading.
1981. Operating license applicants will complete prior c. Resources: 0.5 my per plant.
operating activities.
6. Procedures for verification of correct performance of procedures as a. Description: Each licensee will review and revise the correct perform- necessary to assure that an effective system of verifying be accomplished in ance of operating activities is in place. This action will status monitoring two phases - one before and one after installation of automatic equipment.
the first phase b. Implementation: Operating reactors are to complete completion of installa- by January 1, 1981 and the second phase six months after (see Item I.D.3).
t-on of automatic status monitoring equipment, if required on the same schedule Operating license applicants are to complete these tasks is later.
as operating reactors or prior to fuel loading, whichever I.C-11
Task I.C
May 19,80
c. Resources: 0.5 my per reactor for prped4re review and 3.0 my per reactor for implementation.
7. NSSS vendor review of procedureqs.
a. Description: Operating license applicants are required to obtain reactor vendor review of their low-power, power-ascension and emergency procedures as a further verification of the adequacy of the procedures.
b. Implementation: This requirement is not applicable to operating reactors. Applicants for near-term operating licenses must complete vendor review of emergency and power-ascension test procedures prior to full-power operation and low-power test procedures before fuel lo4ding.
c. Resources: $200,000 per plant (cost includes 2 my per plant engineering effort).
8. Pilot monitoring of selected emergency procedures for near-term operating license applicants.
a. Description: Licensees will be required to correct any deficiencies identified before full-power operation.
b. Implementation: See "Description" above.
c. Resources: $50,000 per near-term operating license applicant.
9. Long-term plan for upgrading procedures.
a. Description: Significant industry efforts will be required in the area of plant procedures upgrading. This may be best accomplished through owner's group participation or through INPO and or NSAC. In either case, an industry study of the analytical bases for proceoures, as wall as studies of human engineering and crisis management, will be required. Studies of operator training and training improvements will also be required. In addition, NRC
I.C-12
Task I.C
May 1980
will require industry cooperation in developing a pilot program to implement the upgraded procedures on a lead plant.
b. Implementation: This effort will parallel the NRC actions in this area and will be addressed in the NRC plan to be developed by July 1981.
c. Resources (industry total): Costs will be discussed in NRC plan.
D. OTHER ACTIONS: None.
E. REFERENCES
President's Commission Report: Items A.4.c(i), A.5, B.1.b, B.5, C.3.b, C.3.c, D.4, D.4a, D.7 Other: NUREG-0578, Recommendations 2.1.3b, 2.1.9, 2.2.1a, 2.2.1c, and 2.2.2a NUREG-0585, Recommendations 4, 5, and 6.2 NUREG-0616, Recommendation 2.2.4.1 NUREG/CR-1250, Vol. I, p. 146; Vol. II, Part 1, pp. 105, 185, Part 2, pp. 203, 205, 211, 388; Part 3, pp. 66, 67, 95. The page numbers given here for Vol. II are draft page numbers.
Letter from Chairman, ACRS, to Chairman, NRC, dated May 16, 1979, Subject: "Interim Report No. 3 on the Three Mile Island Nuclear Station, Unit 2"
Letter from Chairman, ACRS, to Chairman, NRC, dated August 14, 1979, Subject: "Studies to Improve Reactor Safety"
Letter from Chairman ACRS, to Chairman, NRC, dated December 13, 1979, Subject: "Report of TMI-2 Lessons Learned Task Force Final Report"
Letter from Chairman, ACRS, to Chairman, NRC, dated March 11, 1980,
Subject: "ACRS Report on NTOL Items from Draft 3 of NUREG-0660, NRC
Action Plans Developed as a Result of the TMI-2 Accident"
I.C-13
ENCLOSURE 3 MEASURES TO MITIGATE SMALL BREAK
LOSS-OF-COOLANT ACCIDENTS AND
LOSS OF FEEDWATER ACCIDENTS
a PART 1: Staff Requirements (30 Subparts)
II.K.3.1; 2; 3; 5; 9; 10; 12; 13; 14;
15; 16; 17; 18; 19; 20; 21; 22; 24; 25;
27; 28; 29; 30; 31; 32; 33; 45; 46; 47;
58 PART 2: Copy of Section II.K to NRC Task Action Plan
INSTALLATION AND TESTING OF AUTOMATIC PORV
ISOLATION SYSTEM (II.K.3.1)
POSITION
(a) Ail PWR licensees should provide a system which uses the PORV
block valve to protect against a small break LOCA. This system will automatically cause the block valve to close when the reactor coolant system pressure decays after the PORV has opened, to relieve excess-pressure. An override feature should be incorporated. Justification should be provided to assure that failure of this system would not decrease overall safety by Intensifying plant transients and accidents.
(b) Each licensee should perform a confirmatory test of the auto- matic block valve closure system installed in response to (a)
above.
CLARIFICATION
Implementation of this action item has been modified in the forthcoming May
1980 version of NUREG-0660. The change delays implementation of this action item until after the studies specified in Action Item II.K.3.2 have been completed, if such studies confirm that the subject system is necessary.
DISCUSSION
NUREG-0565 (2.1.2.a)
NUREG-0611 (3.2.4.e, 3.2.4.f)
NUREG-0635 (3.2.4.a, 3.2.4.b)
SCHEDULE
Design - July 1, 1981 Test - First refueling cycle ACTION: (Class III)
(1) Licensee to document proposed changes for staff approval prior to implementation. Documentation to be submitted by scheduled date.
(2) Licensee to implement modifications and perform confirmatory test at the next refueling outage following staff approval of the design unless this outage is scheduled within six months of the approval date. In this event modifications will be completed during the following refueling outage.
PWR VENDOR REPORT ON PORV FAILURE
REDUCTIONI (II.K.3.2)
FOSITIONN
(a) Each PWR vendor should submit a report for staff review documenting the various actions which have been taken to decrease the probability of a small break LOCA caused by a stuck-open PORY and show how they constitute sufficient improvements in reactor safety. This report should be submitted for staff review.
(b) Safety valve failure rate based on past history of the vendor de- signed operating plants should be included in the report submitted in response to (a) above.
CLARIFICATIO1 In addition to modifications already implemented on PORVs, the report s-ecified above should include consideration of the automatic PORY isolation system identified in Action Item II.K.3.1. This item is applicable to PWRs.
NISCUSSION
tNUREG-0565 (2.1.2.d)
NU!JPEG-0611 (3.2.4.9, 3.2.4.i)
f.UREG-0635 (3.2.4.c)
SCHEDULE
January 1, 1981 ACTION: (Class I)
Licensee to provide the report to the staff by scheduled date.
- rPORTI'G SAFETY AND RELIEF VALVE
FvAILURES AND CHALLENGES (II.K.3.3 POSITION
(a) Future failures of a relief valve to close should be reported promptly to the NRC.
(b) Future challenges to the relief valves should:be documented in the annual report.
(c) Future failures of a safety valve to close should be reported promptly to the NRC.
(d) Future challenges to the safety valves should be documented in the annual report.
CLARIFICATION
This action item is applicable to all LWRs. Safety valve failure rate based on historical data is addressed in Action Item II.K.3.2.
DISCUSSION
NIUREG-0565 (2.1.2.c, 2.1.2.e)
NUREG-0611 (3.2.4.h, 3.2.4.j)
NUREG-0626 (F-2.5, F-3.5)
NUREG-0635 (3.2.4.d)
SCHEDULE
April 1, 1980
ACTION: (Class I)
Licensee to provide. annual report on SRV and RV failures and challenges as of April 1, 1980.
AUTOMATIC TRIP OF REACTOR COOLANT PUMPS
DURING LOCA (ILK.3.5)
POSITION
Tripping of the reactor coolant pumps in case of a LOCA is not an ideal solution. The licensees should consider other solutions to the small break LOCA problem (for example, an increase in safety injection flow rate). In the meantime, until a better solution is found, the reactor coolant pumps should be tripped automatically in case of a small break LOCA. The signals designated to initiate the pump trip should be care- vully selected in order to differentiate between a small break LOCA and ot!er events which do not require reactor coolant pump trip as discussed in NIUREG-0623.
CLA.RIFICATION
Application to PWRs only. This action item has been revised in the May 1980
version of NUREG-0660 to provide for continued study of criteria for early reactor coolant system pump trip. Implementation, if any is required, will be delayed accordingly.
DISCUSSION
NIJUG-0565 (2.3.2.a)
I;UP-EG-0611 (3.2-.2.a)
- 'J-G-0635 (3.2.2.a)
o';".G-0623 (7.3)
SCHEDULE
Study: January 1, 1981 Modify: January I, 1982 ACTION: (Class I)
Licensee to provide results of evaluation of alternate solution to reactor coolant pump trips to staff by scheduled date.
PROPORTIONAL INTEGRAL DERIVATIVE (PID)
CONTROLLER FODIRFCATION (II.K.3.9)
POSITION
The Westinghouse-recon1iended modification to the Proportional Intecral Derivative (PID) controller should be implemented by affected licensees.
CLARIFICATION
This action item is applicable only to Westinghouse-designed PWRs.
D-SCUSSION
r;uNG-0611 (3.2.4.a)
SCHEDULE
July 1, 1980
ACTION (Class II)
Licensee to implement actions and submit documentation of the method for staff review by scheduled date.
PROPOSED ANTICIPATORY TRIP MODIFICATION (II.K.3.10)
POSITION
The anticipatory trip modification proposed by some licensees to confine the range of use to high power levels should not be made until it has been shown on a plant-by-plant basis that the small break LOCA probability resulting from a stuck-open power-operated relief valve (PORV) is little affected by the modification.
CLARIFICATION
This action item is applicable only to Westinghouse-designed PMRs.
CIS.USSION
NUP.EG-0611 (3.2.4.c)
SCHEDULE
Plant by plant ACTION: (Class III)
1) Licensee to document proposed change for staff approval prior to Implementation. Documentatton to be submitted as proposed by the licensee.
2) Licensee to implement modifications at the next refueling outage following staff approval of the design unless this outage is scheduled within six months of the approval date. In this event modifications will be completed during the following refueling outage.
CONFIRM EXISTENCE OF ANTICIPATORY
TRIP UPON TURBINE TRIP (II.K.3.12)
POSITION
Licensees with H-designed operating plants should confirm that their plants have an anticipatory reactor trip on turbine trip. The licensee of any plant where this trip isnot present should provide a conceptual design and evaluation for the installation of this trip.
CLARIFICATION
This item is applicable to Westinghouse PWRs.
DISCUSSION
i:UREG-0611 (3.2.4.a)
SCHEDULE
July 1, 1980
ACTION: (Class III)
(1) Licensee to document proposed changes for staff approval prior to implementation. Documentation to be submitted by scheduled date.
(2) Licensee to implement modifications at the next refueling outage following staff approval of the design unless this outage is scheduled within six months of the approval date. In this event modifications will be completed during the following refueling outage.
SEPA'T-:f a I HPCI AND RCIC SYSTEM INITIATION LEVELS -
r.".'SiS ;.?'D I"PLEMDITATIOMI (II.K.3.13)
C-Urrently, the reactor core isolation cooling (RCIC) system and the high pressure coolant injec-ion (HPCI) system both initiate on the-same low water level signal and both isolate on the same high water level signal.
The HPCI system will restart on low water level but the RCIC system will not. The RCIC system is a low-flow system when compared to the HPCI
system. The initiation levels of the HPCI and RCIC system should be separated so that the RCIC system initiates at a higher water level than tne HCI system. Further, the RCIC system initiation logic should be modified so that the RCIC system will restart on low water level. These changes have the potential to reduce the nubmer of challenges to the H:?CI system and could result in less stress on the vessel from cold water injection. Analyses should be performed to evaluate these chances.
The analyses should be submitted to staff and changes should be implemented if justified by the analyses.
CLARIFICATIONg This item is applicable to BWRs with RCIC and HPCI systems.
L 1SOUSSION
I:JREG-0526, Section A-2.3 SCHEDULE
Analysis: October 1, 1980
Implementation: April 1, 19.81 ACTION: (Class II)
() Licensee to provide results of evaluation to staff by scheduled date.
(2) If justified by analysis licensee to implement actions- by scheduled dates and submit documentation of the method for staff review.
ISOLATION OF ISOLATION CONDENSERS ON HIGH RADIATION: (II.K.3.14)
POSITION
Isolation condensers have radiation monitors on their vents. These monitors provide alarms in the control room but do not isolate the isolation condenser. The isolation condensers are currently isolated on a high radiation signal in the steam line leading to the isolation condensers. The design should be modified such that the isolation condensers are automatically isolated upon receipt of a high radiation signal at the vent rather than at the steam line. The purpose of the change is to increase the availability of the isolation condensers as heat sinks.
CLARIFICATION
This Item is applicable to BWRs which have isolation condensers.
DISCUSSION
tUREG-0626, Section A-2.4 SCHEDULE
January 1, 1981 ACTION : (Class II)
(1) Licensee to implement actions and submit documentation of the method for staff revtewt by scheduled dates.
- -
- ODIFY BREAK &'ETECTICI LOGIC TO PREVENT SPURIOUS ISOLATION
OF HiPi AND RCIC SYSTEMS (II.K.3.l5)
PO5 IT ION
The HCI and RCIC systems use differential pressure sensors on elbow taps in 'he steam lines to their turbine drives to detect and isolate pipe breaks in the systemns. The pipe break detection circuitry has resulted in spurious isolation of the HPCI and RCIC systems due to the pressure spike which accompanies startup of the systems. The pipe break detection cir- cuitry should be modified so that pressure spikes resulting from HPCI and RCiC system initiation will not cause inadvertent system isolation.
CLARIFICATION
This item is applicable to BWRs with HPCI and RCIC systems.
_I3CUSS ION
- tU.'G-0626, Sections A-2.3, A-2.5, and F-2.3 SCHEDULE
January 1, 1981 ACTION : (Class II)
(1) Licensee to implement actions and submit documentation of the method for staff review by scheduled dates.
REDUCTION OF CHALLE;NGES AND FAILURES OF RELIEF VALVES - FEASIBILITY
STUDY AN'D SYSTEM 1MODIFICATION - (II.K.3.16)
POSiTION;
The record of relief valve failures to close for all BWRs in the past three years of plant operation is approximately 30 in 73 reactor years (0.41 failures/reactor year). This has demonstrated that the failure of a relief valhe to close would be the most likely cause of a small-break LOCA. The hich failure rate is the result of a high relief valve challenge rate and a relatively high failure rate per challenge (0.16 failures/challenge).
Typically, five valves are challenged in each event. This results in an equivalent failure rate per challenge of 0.03. The challenge and failure rates can be reduced in the following ways:
(1) Additional anticipatory scram on loss of feedwater,
(2) Revised relief valve actuation setpoints,
(3) Increased emergency core cooling (ECC) flow,
(4) Lower operating pressures,
(5) Earlier initiation of ECC systems,
(6) Heat removal through emergency condensers,
(7) Offset valve setpoints to open fewer valves per challenge,
(8) Installation of additional relief valves with a block or isolation valve feature to eliminate opening of the safety/relief valves (SRVs), consistent with the ASME Code,
(9) Increasing the high steam line flow setpoint for main steam line isolation valve (MSIV) closure,
(10) Lowering the pressure setpoint for MSIV closure,
(11) Reducing the testing frequency of the MSIVs,
(12) More stringent valve leakage criteria, and
(13) Early removal of leaking valves.
An investigation of the feasibility and contraindications of reducing challenges to the relief valves by use of the aforementioned methods should be conducted.
Other methods should also be Included in the feasibility study. Those changes which are shown to reduce relief valve challenges without compromising the performance of the relief valves or other systems should be Implemented.
Challenges to the relief valves should be reduced substantially (by an order of magnitude).
ts'D"CTIO:i OF CLLLE$'GES AND FAILURES OF RELIEF VALVES - FEASIBILITY
STUDY -A:.D SYSTE:" MODIFICATION" - (iI.K.3.16) - Continued CLOm"IF- ICATiOCI
This item is applicable to BWRs.
DISCUSSION
NUREG-0626, Sections A-2.8 and F-3.4 SCHEDULE
Feasibility Study - January 1, 1981 Proposed System Modification - January 1, 1982 Modification - Refueling ACTION: (Class III)
(1) Licensee to provide results of evaluation to staff by scheduled date.
(2) Licensee to document proposed changes for staff approval prior to implementation. -Documentation to be submitted by scheduled date.
(3) Licensee to implement modifications at the next refueling outage following staff approval of the design unless this outage is scheduled within six months of the approval date. In this event modifications will be completed during the following refueling outage.
v-R-T^ 1 0:' C$siAE i C SYSTEMS - LICE:'SEE REUORT AND PROPOSED
TECH"I Cr.! SEWIN I CATION CHANGES (II.K.3.17)
r 'DS I.;T I 0:.
Sev;ral components of the ECC systems are permitted by Technical Specifica- tic-s to have substantial outage times (e.g., 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for one diesel- cre-rator; 14 days for the HPCI system). In addition, there are no cumulative citage time limitations for ECC systems. Licensees should submit a report detailing outage dates and lengths of outages for all ECC systems for the last five years of operation. The report should also include the causes of the outages (e.g., controller failure, spurious isolation).
CkArIFICATION
This item is applicable to all LWRs.
is,'USSIO:
rIJIREG-0626, Section F-3.5 Sr'EDULE
January 1, 1981 ACTION: (Class I)
0 ) Licensee to provide results of evaluation to staff by scheduled date.
i:z:F c.'iO CF -:z- '!:IC - FEASIBILITY STUDY AND IMODIFICATIO:NS
LC. I;;REASED :_dE.SITY FOR SG:ME EVENT SEQUENCES (II.K.3.18)
The ADS actuation logic should be modified to eliminate the need for mr.1a1 actuation to assure adequate core cooling. A feasibility and risk assessmnent study is recurred to determine the optimum approach. One possible scheme which should be considered is ADS actuation on low reactor vessel water level provided no HPCI or HPCS system flow exists and a low pressure ECC system is running. This logic would complement, not replace, the existing ADS actuation logic.
CLARI.-ICATIO:J
This item is applicable to BWRs.
C.':USSIC1.
I;JREG-0026, Sections A-2.9 and F-2.3
_'I G-LE
FEsibility Study - January 1, 1981 Proposed Modifications - January 1, 1982 Modifications - Refueling ACTION: (Class III)
(1) Licensee to provide results of evaluation to staff by scheduled date.
(2) Licensee to document proposed changes for staff approval prior to Implementation. Documentation to be submitted by scheduled date.
(3) Licensee to implement modifications at the next refueling outage following staff approval of the design unless this outage isscheduled within six months of the approval date. Inthis event modifications will be completed during the following refueling outage.
i:1TERLOCK G. -,TCI^ULATIO,, PUMP LOOPS (II.K.3.19)
- T TIO:J
in. rlocks should be installed on non-jet pump plants (other than k;7,oldt Bay) to assure that at least two recirculation loops are o:-n for recirculation flow for modes other than cold shutdown. This Isto assure that the level measurements in the downcomer region are representative of the level in the core region.
C~ IF I CATION
This Item is applicable to non-jet pump BWRs except Humboldt Bay.
-I ZUSSION
- J.G-0526, Section A-2.17 D E
S ZDUL
January 1, 1981 ACTION: (Class II)
(1) Licensee to implement actions and submit documentation of the method for staff review by scheduled dates.
LOSS OF SERVICE W.8ATER FOR BIG ROCK POIN:T (II.K.3.20)
POSITION
The service water system for Big Rock Point has only one cooling train and is powered from normal alternating current power. The Big Rock Point licensee should verify the acceptability of the consequences of.a loss of service water supply to the essential plant components in the event of a loss of offsite power.
CLARIFICATION
This item is applicable only to Big Rock Point.
DISCUSSION
NUREG-0626, Section A-2.13 SCH-EDULE
January 1, 1981 ACTION: (Class I)
(1) Licensee to provide results of evaluation to staff by scheduled date.
RESTART OF CORIE SPRAY JAD LPCI SYSTEIj;S O!J LOW LEVEL - DESIGNJ
A:;9 MODIFICATION' (II.K.3.21)
POSITION
The core spray and LPCI system flow may be stopped by the operator. These systems will not restart authmatically on loss of water level if an initia- tion signal is still present. The core spray and LPCI system logic should be modified so that these systems will restart if required to assure ade- quate core cooling. Because this design modification affects several core cooling modes under accident conditions, a preliminary design should be submitted for staff review and approval prior to making the actual modification.
CLARIFICATION
This item is applicable to BMRs.
DiSCUSSION
!:;REG-0626, Section A-2.7 SCEEDULE
Design - 1/1/81 i:odifications - Refuelina ACTION: (Class III)
(1) Licensee to document proposed changes for staff approval prior to implementation. Documentation to be submitted by scheduled date.
(2) Licensee to implement modifications at the next refueling outage following staff approval of the design unless this outage is scheduled within six months of the approval date. In this event modifications will be completed during the following refueling outage.
.7& ;TIC S' T Cr'.' 'GOF RPCIC SYSTEM SUCTION - VERIFY PROCEDURES
AND ;$;3DIFY DESIGN - (II.K.3.22)
r 1SITION
The RCIC system takes suction from the condensate storage tank with c-ar.jal switchover to the suppression pool when the condensate storage tank level is low. This switchover should be made automatic. Until the automatic switchover is implemented, licensees should verify that clear and cogent procedures exist for the manual switchover of the RCIC system suction from the condensate storage tank to the suppression pool.
CU-F FICATION
This Item is applicable to BWRs with RCIC system.
DISCUSSION
.;U.-EG-0626, Section A-2.3 MCHEDULE
Verify procedures - January 1. 1981 iodify design - January 1, 1982 ACTION: (Class II)
(1) Licensee to implement actions and submit documentation of the method for staff review by scheduled dates.
CO£:FIPR' ADEQUACY OF SPACE COOLING FOR HPCI AID RCIC SYSTEIS - (II.K.3.24)
POSITION
Long-term operation of the RCIC and HPCI systems may require space cooling to maintain the pump room temperatures within allowable limits. The licensees should verify for each plant the acceptability of the consequences of a complete loss of alternating current power. The RCIC and HPCI systems should be designed to withstand a complete loss of alternating current power to their support systems, including coolers, for at least two hours.
CLARIFICATION
T:iis item is applicable to BWRs with RCIC and HPCI systems.
DISCUSSION
NUREG-0626, Section A-2.13 SCHEDULE
January 1, 1982 ACTION: (Class II)
(1) Licensee to implement actions and submit documentation of the method for staff review by scheduled dates.
.
EFFECT OF LOSS OF AC POWER ON PUMP SEALS (II.K.3.25)
rS ITION
F
.. licensees should determine by analysis or experiment, on a plant-specific basis, the consequences of a loss of cooling water to the reactor recirculation xp.D seal coolers. The pump seals should be designed to withstand a complete Loss of alternating current power for at least two hours. Adequacy of the seal design should be demonstrated.
CLARIFICATION
This item is applicable to PWRs.
DISCUSSION
M;UREG-0626, Section A-2.14 S'E..ULE
January 1, 1982 ACTION: (Class I)
Licensee to provi.de. res.ults. of evaluatton. to staff by scheduled date.
PROVIDE CO:!4O,.; REFERENCE LEVEL FOR VESSE' '.-!
ir;STRU:-;ETNTATJO:i (II.K.3.27)
- ?S>ITION3 Different reference points of the various reactor *vessel water level instru- e.ents may cause operator confusion. Theretore, all level instruments should be referenced to the same point. Either the botto, of the vessel or the top OT the active fuel are reasonable reference points.
CLARIFICATION
This item is applicable to BWRs.
DISCUSSION
'X.REG-0626, Section A-2.17 SHcLDULE
October 1, 1980
ACTION: (Class II)
(1)Licensee to Implement actions and submit documentation of the method for staff review by scheduled dates.
STUDY A1r VERT.:Y QUALIFICATION OF ACCUI'ULA73-S X,. ADS VALVES
(II.K.3.28)
POSITION
Safety analysis reports claim that air or nitrogen accumulators for the ADS valves are provided with sufficient capacity to cycle the valves open five times at design pressures. GE has also stated that ECC systems are designed to withstand a hostile environment and still perform their function
100 days after an accident. Licensee should verify that the accumulatnrc nn the ADS valves meet these requirements, even considering normal leakage. If this cannot be demonstrated, show that the accumulator desln is still acceptable.
CLARIFICATION
This item is applicable to BWRs.
DISCUSSiON
NUREG-0626, Section A-2.15 SCHEDULE
January 1, 1982 ACTION: (Class II)
.(1) Licensee to provide results of evaluation to staff by scheduled date.
STUDY TO DU:,O. 1ST2ATE
- PRFOR;*:A.CE OF T'CL ATiON
" II COXDENSERS
WITH ~-O~'SBE (II.K.3.29]
POSITION
If natural circulation plays an irmportant role in depressurizing the system (e.g., in the use of isolation condensers), then the various modes of two-phase flow natural circulation, including non-condensibles, which may play a significant role in plant response following a small-break LOCA
should be demonstrated.
CLARIFICATION
This item is applicable to all LWRs.
DISCUSSION
14UREG-0626, Section F-4.5 SCHEDULE
April 1, 1981 ACTION: (Class I)
(1) Licensee to provide results of evaluation to staff by scheduled date.
REVISE> S,!L-SREAK LOCA METHODS TO SHOW
3 c0:"`PL1Ai.c : 10 C R 50, APPENDIX K (II.K.3.`)
PcGS1T:0I
The analysis methods used by NSSS vendors and/or fuel suppliers for small break LOCA analysis for cor.pliance with Appendix K to 10 CFR Part 50 should be revised, documented, and submitted for NRC approval. The revisions should account for comnarisons with experimental data, including data from the LOFT and Semiscale facilities.
CLARI FICATION
Clarifying information regarding the implementation of this action item will te provided in the forthcbming Draft 4 of NUREG-0560. This item is applicable to LWRs.
D:ScUSST0!1, NJ RE-G-00651 (2.2.2.a)
(3.2.1 .a)
NU%~RE G-06113 (F-4.0)
(3.2.1.a, 3.2.5.a)
SCH EDL 7 January 1, 1982 ACTION: (Class I)
(1) Licensee to submit analysis model for staff approval by scheduled date.
PLANT SPECIFIC CALCULATIONS TO SHOW
COtMLIA!;CE WITH 1O-CFR 50.46 (II.K.3.31)
POSITION
Flant-specific calculations using NRC-approved models for small break LOCKs as described in II.K.3.31 above, to show compliance with 10 CFR
_3.46 should be submitted for NRC approval by all licensees.
CLA.RI FrICAT ION
Clarifying information regarding the implementation of this action item will be provided in the forthcoming Draft 4 of NUREG-0660. This item is applicable to LMRs.
- T""'!SSION
.::. G-0565 (2.2.2. b)
a;J.E G-0611 (3.2.1.b)
. W--G-0626 (F-4.0)
.J;_EG-0635 (3.2.1 .b)
SO G-EDJLE
January 1, 1983 or one year after staff approval of LOCA analysis model.
ACTION: (Class I)
(1) Licensee to provide results of evaluation to staff in accordance with the schedule as indicated above.
EVALUATIC!; Cr A:NTICIPATED TRA;SIcEiJTS WI TH SIrNGLE FAILURE
TO VERIFY 10 FUEL FAILURE (ll.K.3.44)
POSITION
For anticipated transients combined with the worst single failure and assuming proper operator actions, licensees should demonstrate that the core remains covered or provide analysis to show that no significant fuel damage results from core uncovery. Transients which result in a stuck-open relief valve should be included in this category.
CLARIF ICATION
This item is applicable to LWRs.
DISCUSSION
NUREG-0626, Section F-4.3 SCHEDULE
1/1/81 ACTION: (Class I)
(1) Licensee to provide results of evaluation to staff by scheduled date.
EVALUATION OF DEPRESSURIZA;TIOR iTHin OTHER THAN. ADS (II.K.34
- OSITI ON
than full actuation of the Analyses to support depressurization modes other should be provided. Slower ADS (e.g., early blowdown with one or two SRVs)of exceeding vessel integrity
.e-ressurization would reduce the possibility limits by rapid cooldown.
CLARIFICATION
This item is applicable to BWRs.
DISCUSS I ON
HUREG-0626, Section F-4.3 SCHEDULE
1/1/81 ACTION: (Class I)
by scheduled date.
(1) Licensee to provide results of evaluation to staff
.RESPOINSE TO LIST OF CONCERNS FRO:-' ACRS CO:'SULT.;T (II.K.3. 4 6 )
POSITION
GE should provide a response to the Michelson concerns as they relate to BWRs.
CLARIFICATION
GE provided a response to the Michelson concerns as they relate to BWRs by letter dated February 21, 1980. Licensees should assess applicability and adequacy of this response to their plants. This item is applicable to BWRs.
DISCUSSION
NUREG-0626, Section F-4.6 SCHEDULE
7/1/SO
ACTION: (Class I)
(1) Licensee to provide results of evaluation to staff by scheduled date.
57
2 EDIFY BIE.'r J ;-ES PRIOR'. TO I*ANtLAL ACTIVATIO[J OF ADS (II.K.3. ).
r-._rcency procedures should include verification that a source of cooling W.,er, sch as the core spray, LPCI, or condensate systems, is available
- prior to r.nual actuation of the automatic depressurization system (ADS).
Alternate eater scurles should be identified in the procedures and reference should be .nade to procedures for start-up and operation of systems that provide these sources. This is being implemented through the guidelines being developed to assure adequate core cooling.
CLARIFICATION
This item is applicable to BWRs.
DISCUSSI 0:;
- l;EG-0626, Section A-2.9 SC.DULLE
10/1/80
ACTION; (Class I)
(1) Licensee should verify by the scheduled date that Emergency Procedures have been appropriately revised.
The following pages are from the May 1980 version of the TMI Action Plan,Section II.K. This section is provided for background information only and note that the subject being discussed with respect to our positions on the II.K.3 matters is a subpart. AppendiX C to 0660 is included.
Task I.K
May 1980
TASK II.K MEASURES TO MITIGATE SMALL-BREAK LOSS-OF-COOLANT ACCIDENTS AND
LOSS OF FEEDWATER ACCIDENTS
A. OBJECTIVE: To perform systems reliability analyses and to effect changes in emergency operating procedures and operator training to improve the capability of plants to mitigate the consequences of the small-break loss-of-coolant accidents (LOCA) and loss-of-feedwater events.
B. NRC ACTIONS
1. It Bulletins.
a. Description: Between April 1, 1979 and July 26, 1979 the Office of Inspection and Enforcement (IE) issued nine bulletins to various operating plant licensees, depending on the design of the reactor, and reviews of licensee responses were conducted by the NRR Bulletins and Orders Task Force. The responses were determined to be acceptable, and separate evaluation reports have been prepared and issued to some licensees. The effort to complete these reports for all operating plant licensees is continuing.
NRR will require all operating license applicants to evaluate their plants against the requirements specified in applicable IE Bulletins and not otherwise addressed in this Action Plan, and to take corrective actions as necessary prior to fuel loading. Ultimately, these requirements will be codified by NRR
and SD, as appropriate, and required of all plants as preconditions for receipt of an operating license.
A comparison of the composite requirements from the nine bulletins with the action items in this plan is provided in Appendix C. The Bulletin requirements not covered by ac:.n items art listed below:
(1) Review all -- ty-soated ialve positions and positioning requirements and positive zzr^:. as .e as al. redated test and maintenance procedures, to assure proper _rF 'jncticning, if required (see Appendix C, Table C.1, I'em 5).
II. K-1
=
Task II.K
May 1980
(2) Review and modify (as required) procedures for removing safety-related systems from service (and restoring them to service) to assure that operability status is known (see Appendix C, Table C.1, Item 10).
(3) Provide a trip for the pressurizer low-level bistable so that the pressurizer low-pressure signal alone (rather than the low-level/low-pressure coincidence) will trip the reactor. For testing, provide for resetting the pressurizer low-level bistable (see Appendix C, Table C.1, Item 17).
(4) Provide procedures and training to operators for prompt manual reactor trip for LOFW, TT, MSIV Closure, LOOP, LOSG level, and PZR Low Level (see Appendix C, Table C.1, Item 20).
(5) Provide automatic safety-grade anticipatory reactor trip for LOFW,
TT, or significant decrease in SG level (see Appendix C, Table C.1, Item 21).
(6). Describe automatic and manual actions for proper functioning of auxiliary heat removal systems when main feedwater system is not operable (see Appendix C, Table C.1, Item 22).
(7) Describe uses and types of RV level indication for automatic and manual initiation of safety systems. Also describe alternative instrumentation and methods (see Appendix C, Table C.1, Item 23).
b. Schedule: NRR will complete the Bulletin evaluation reports for operating plants by March 31, 1980. NRR will issue requirements to all pending operating license applicants and all plants under construction by July 1, 1980.
C. Resources: NRR FY80 - ..0 my, FY81 - 0.8 my.
2. Commission Orders on 3abcock and Wilcox plants.
a. Description: In April 1_979, i task group was established in NRR to perforn a generic assessment of Exciter transients in B&W-designed operating plan:s In light of -^ _.- - - -2. The study concluded that the staff I I. K-2
Task II.K
May 1980
did not have reasonable assurance that the B&W plants could continue to operate without undue risk to the health and safety of the public and that the plants should be shut down until certain actions were completed to the satisfaction of the staff. The B&W licensees committed to perform these actions and con- firmatory Orders were issued to formalize the agreements reached with the licensees.
The Orders included both short-term and long-term actions. The NRR Bulletins and Orders Task Force reviewed the licensee responses to the short-term actions in the Orders and issued safety evaluation reports lifting the Orders in the period between May 18, 1979, and July 6, 1979. (These are Items 1 through 12 in Appendix C, Table C.2.) Additional items were identified in the review that required further work by the licensees. These items are numbered 13 through 21 in Appendix C, Table C.2; all 21 items are to be implemented by operating B&W reactors. However, because some were suspended by actions elsewhere in this plan, only seven of these actions apply to operating license applicants with B&W reactors (see Table C.2, Appendix C). License applicants with B&W plants will be required by NRR to demonstrate conformance with these seven requirements prior to operating license issuance.
b. Schedule: NRR will complete the evaluation of operating plant licensee implementation of residual actions originating from short-term actions and the implementation of long-term actions of the confirmatory Orders by January 1, 1981. NRR will issue these seven unique requirements, described above, to B&W designed plants now under construction by July 1, 1980.
c. Resources: NRR FY80 - 1.5 my, FY81 - 2 my; IE FY80 - 0.5 my, FY81 -
0.5 my.
3. Final recommendations of B&O Task Force.
a. Description: The Bulletins and Orders Task Force has conducted gereric reviews aI the loss-of-feedwater (LOFW) and small-break loss-of- coclant events on operating PWRs designed by B&W, Westinghouse (W), and Comn- bustion Engineering (CE), and on operating BWRs. These reviews consisted of II. K-3
Task I.K
May 1980
an evaluation of systems reliability analyses, guidelines for emergency proce- dures, and operator training related to these events. From these reviews, a number of recommendations for improvements were developed and issued in reports NUREG-0565 (B&W), NUREG-0611 (W), NUREG-0626 (GE), NUREG-0635 (CE), and NUREG-0623.
Upon approval of these recommendations (shown in Table C.3, Appendix C), NRk will notify licensees of the actions to be taken with respect to system modifica- tions, additional analyses, improved emergency procedures, and improved operator training related to the loss of feedwater and small-break LOCA events. The ACRS will advise NRR in early 1980, after which NRR will review and evaluate licensee commitments and/or actions required.
On a case-by-case basis, NRR will propose the schedule on which these generic requirements must be met by near-term operating license applicants during calender year 1980 (i.e., before fuel loading, before full-power operation, or later). Ultimately, these generic requirements will be codified by NRR and SD
and will be applied to all plants as preconditions for receipt of an operating license.
b. Schedule: NRR will issue requirements to operating plant licensees On early 1980 and will review the responses on a schedule to be completed in
'983. Near-term operating license applicants are being advised of the specific requirements in this area on a case-by-case basis.
c. Resources: NRR FY80 - 7.7 my, FY81 - 11.2 my, FY82 - 4.5 my, FY83 -
4.0 my.
-. U-C-NSE- ACTIONS
- , 7ulletins.
i. :escription: All applicants must respond to the NRC requirements arc sa--cr.be how the actions required by the IE Bulletins are
.; :- .a) imp "enead.
II. K-4
Task II.K
May 1980
b. Implementation: Near-term operating license applicants will be required to implement the requirements prior to fuel loading.
c. Resources: 0.2 my per application.
2. Commission Orders on Babcock and Wilcox plants.
a. Description: Licensees must complete residual actions originating from short-term actions in the confirmatory Orders and long-term actions in the confirmatory Orders. All applicants must respond to the NRC requirements (to be issued) and describe how the actions required by the confirmatory Orders are (or will be) implemented.
b. Implementation: B&W operating reactors must complete actions by January 1, 1981. Operating license applicants must complete actions on the schedules specified in Table C.2 of Appendix C.
c. Resources: 1 my per plant.
3. Final recommendations of B&O Task Force.
a. Description: Licensees must complete actions originating from the generic reviews of the small-break loss-of-coolant accident and loss of feed- water events by the dates set forth in NRC requirements (to be issued). All applicants for plants and designs must resolve all applicable actions specified in NRC requirements (to be issued) and describe how the required actions are (or will be) implemented.
b. Implementation: Operating reactors must complete actions by January 1,
1!88. Operating license applicants must complete actions on the schedules specified in Table C.3 of Appendix C.
c. Resources: 2 my per plant.
II. K-5
Task IL.K
May 1980
D. OTHER ACTIONS: None.
E. REFERENCES
President's Commission Report: D.4.a Other: NUREG-0565, NUREG-0611, NUREG-0626, NUREG-0635, and NUREG-0645.
NUREG/CR-1250, Vol. II, Part 2, pp. 187, 193, 197, 205, 211. The page numbers given here for Vol. II are draft page numbers.
Inspection and Enforcement Bulletins 79-05,79-05A, 79-058,79-05C,
79-06,79-06A, 79-06A (Revision 1),79-06B, 79-06C, and 79-08.
Commission Orders to Duke Power Company dated 5/07/79, Sacramento Municipal Utility District dated 5/07/79, Florida Power Corporation dated 5/16/79, Toledo Edison Company dated 5/16/79, and Arkansas Power & Light Company dated 5/17/79.
Letters lifting Orders to Duke Power Company dated 5/18/79, Arkansas Power & Light Company dated 5/31/79, Sacramento Municipal Utility District dated 6/27/79, Florida Power Corporation, dated 7/06/79, and Toledo Edison Company dated 7/06/79.
Letter from Chairman, ACRS, to Chairman, NRC, dated March 11, 1980,
Subject: "ACRS Report on NTOL Items from Draft 3 of NUREG-0660, NRC
Action Plans Developed as a Result of the TMI-2 Accident"
I'. K-6
APPENDIX C
RECOMMENDATIONS AND REQUIREMENTS BASED ON
IE BULLETINS AND ORDERS AND COMMISSION ORDERS
TABLE C.1 OFFICE OF INSPECTION AND ENFORCEMENT BULLETINS
Operating Operating Source for Reactor License Operating Reactors Applicability Implementation Implementation Requirement
79-05&05A (Item 1) BWR and PWR 3/31/80 I.A.2.2
1. Review TMI-2 PNs and detailed chronology
79-06&06A (Item 1) I.A.3.1 of the TMI-2 accident.
79-OG&068 (Item 1)
79-08 (Item 1)
79-05&05A (Item 2) B&W 3/31/80 I.A.2.2
2. 'Review transients similar to TMI-2 that I.A.3.1 have occurred at other facilities and NRC evaluation of Davis-Besse transient.
79-05&05A (Item 3) PWR 3/31/80 I.C.1
3. Review operating procedures for recog- nizing, preventing, and mitigating void 79-06&06A (Item 2)
formation in transients and accidents. 79-06&06B (Item 2)
79-05&05A (Item 4.a) PWR and BWR 3/31/80 I.C.1
4. Review operating procedures and training I.C.7 instructions to ensure that: 79-058 (Item 2)79-06A (Item 7.a) I.G.1
79-068 (Item 6.a) I.C.8 a. Operators to not override ESF
actions unless continued operation 79-08 (Item 5.a)
is unsafe;
NUREG-0645 (App. G) W, CE 3/31/80 I.C.1 b. HPI system operation NUREG-0565 B&W
(Rec. 104)69-110 6002-00 ANO-1
(11/1/79
69-110 6003-00 Davis-Besse 1
(11/20/79)69-110 6001-00 Oconee 1, 2 & 3
(11/1/79) Crystal River 3 Rancho Seco 1 C.1-1
TABLE C.1 (continued)
Operating Operating Source for Reactor License Requirement Operating Reactors Applicability Implementation Implementation c. RCP operation NUREG-0623 PWR Complete I.C.1 I.A.1.3 d. Operators are instructed not to rely 79-05A (Item 4.d) PWR and BWR Complete I.C.1 on level indication alone in 79-06A (Item 7.d) I.A.3.1 evaluating plant conditions.79-060 (Item 6.d) II.F.2
79-08 (Item 5.b)
5. Safety-related valve position. 79-05&05A (Item 5) PWR and BWR 3/31/80 NTOL: Same as ORs, before FL
a. Review all valve positions and 79-06A (Item 8) OL: I.C.2 &
positioning requirements and positive 79-06B (Item 7) I.C.6 controls and all related test and 79-008 (Item 6)
maintenance procedures to assure proper ESF functioning, if required.
b. Verify that AFW valves are in open 79-05A (Item 5) B&W 3/31/80 I.C.2 position. See Requirement 8 below. I.C.6
6. Review containment isolation initiation 79/05A (Item 6) PWR and BWR 3/31/80 II.E.4.2 design and procedures. Assure isolation 79-06A (Item 4)
of all lines that do not degrade safety 79-06B (Item 3)
features or cooling capability upon 79-08 (Item 2)
automatic initiation of SI.
7. Implement positive position controls on 79-05A (Item 7) B&W 3/31/80 II.E.l.l valves that could compromise or defeat ANW flow.
C.1-2
4 TABLE C.1 (continued)
Operating Operating Source for Reactor License Requirement Operating Reactors Applicability Implementation Implementation
8. Immediately implement procedures that 79-OSA (Item 8) B&W 3/31/80 II.E.l.l assure two independent 100% AFW flow paths, or specify explicitly LCO with reduced AFW
capacity.
9. Review procedures to assure that radio- 79-05A (Item 9) PWR and BWR 3/31/80 II.E.4.2 active liquids and gases are not trans- 79-06A (Item 9)
ferred out of containment inadvertently 79-06B (Item 8)
especially upon ESF reset). List all 79-08 (Item 7)
applicable systems and interlocks.
10. Review and modify (as required)79-05A (Item 10) PWR and BWR 3/31/80 NTOL: Same as procedures for removing safety- 79-06A (Item 10) ORs & I.C.2, related systems from service (and 79-06B (Item 9) before FL
restoring to service) to assure 79-08 (Item 8) OL: I.C.2 &
operability status is known. I.C.6
11. Make all operating and maintenance 79-05A (Item 11) PWR and aWR 3/31/80 I.A.3.1 personnel aware of the seriousness79-06A (Item l.a) I.A.2.2 and consequences of the erroneous79-06B (Item l.a)
actions taken leading up to, and in 79-08 (Item l.a)
early phases of, the TMI-2 accident.
12. One hour notification requirement, and 79-05B (Item 6) PWR and BWR Complete I.E.6 continuous communications channel.79-06A (Item 11) III.A.3.3
79-06B (Item 10)
79-08 (Item 9)
C.1-3
TABLE C.1 (continued)
Operating Operating Source for Reactor License Requirement Operating Reactors Applicability Implementation Implementation
13. Propose Technical Specification changes79-05B (Item 7) PWR and BWR 1/1/81 Normal work reflecting implementation of all Bulletin 79-06A & Rev. 1 on all new OLs items, as required. (Item 13)79-06B (Item 12)
79-08 (Item 1)
14. Review operating modes and procedures79-06A (Ite.. i2) W, CE GE 3/31/80 II.B.4 to deal with significant amounts of 79-06B (Iteig il) II. B.7 hydrogen. 79-08 (Item lo) I I. E.4. 1 II. F. I
15. For facilities with non-automatic AFW 79-06A (Itei, 5) W & CE Complete IH.E. 1.2 initiation, provide dedicated operator 79-06B (Ite. 4)
in continuous communication with CR to operate AFW.
16. Implement (immediately) procedures that 79-06A (Iteii 6) W & CE Complete I.C. 1 identify PRZ PORV "Open" indications and 79-06B (Itein 5) II. D.3 that direct operator to close manually at "RESET" setpoint.
17. Trip PZR Level Bistable so that PZR Lo 79-06A & Rev. 1 W Complete Same as ORs, Press. (rather thdn PZR Lo Press. and PZR (Item 3) before FL
Lo Level coincidence) will initiate safety injection. For test, reset Lo Level bistable.
I B. Develop pJr.oc(!Ilil'S find trdin operators on 79-05B (Itoea, 1) Compl 1Cte I.C. 1 metIhods of estahl ishing an(d maintaining I.G. I
natural circulation.
C.1-4
TABLE C.1 (coitinued)
Opernt.i ln(
Source for Reactor License Requi rement OperatLing R.eactors Applicability Imp onmentati on Impl ementation
19. Describe design and procedure modifications79-05B (Itemi J) B&W 3/31/80 II.E.5 (based on analysis) to reduce likelihood of automatic PZR PORV actuation in transients.
20. Provide procedures and training to 79-050 (Item 4) B&W 3/31/80 Same as ORs, operators for prompt manual reactor trip before FL
for LOFW, TT, MSIV closure, LOOP, LOSG
Level, & Lo PZR Level.
21. Provide automatic safety-grade anticipatory 79-058 (Item 5) B&W 3/31/80 Same as ORs, reactor trip for LOFW, TT, or significant before FL
decrease in SG level.
22. Describe automatic and manual actions 79-08 (Item 3) BWR 3/31/80 Same as ORs, for proper functioning of auxiliary before FL
heat removal systems when FW system not operable.
23. Describe uses and types of RV level 79-08 (Item 4) BWR 3/31/80 Same as ORs indication for automatic and and II.F.2, manual initiation safety systems. before FL
Also, describe alternative -
instrumentation.
24. Perform LOCA analyses for a range of 79-05C (short- PWR Complete I.C.I
small-break sizes and a range of term Item 2)
time lapses between reactor trip 79-06C (short- and RCP trip. term Item 2)
C.1-5
TABLE C.1 (continued)
Operati hg Ope ra Ling Source for Reactor License Requirement Operating Reactors Applicability Impl ementati on Implementation
25. Develop operator action guidelines (based 79-05C (short- PWR Complete I.C.1 on analyses in Requirement 24 above). term Item 3)79-06C (short- term Item 3)
26. Revise emergency procedures and train RO's79-05C (short- PWR Complete I.C.1 and SRO's based on guidelines developed in term Item 4) I.A.3.1 Requirement 25 above.79-06C (short- I.G.1 term Iteni 4)
27. Provide analyses and develop guidelines79-05C (short- PWR Complete I.C.1 and procedures for inadequate core term Item 5) II.1:. 2 cooling conditions. Also, define RCP 79-06C (short- restart criteria. term Item 5)
28. Provide design that will assure automatic NUREG-0623 PWR 1/1/81 See Table C.3, RCP trip for all circumstances where item 5 required.
C.1-6
TABLE C.2 REQUIREMENTS FOR NEW B&W PLANTS DERIVED FROM COMMISSION
ORDERS ON OPERATING B&W PLANTS
Operating Operating Requirement Source Applicability Reactor License Implementation Impleientation l. Upgrade timeliness and reliability Commission Order B&W Complete II.E.1 of AFW system.
2. Procedures and training to initiate Coiivission Order B&W Complete II.K.2 and control AFW independent of integrated control system.
3. Hard-wired control-grade anticipatory Commission Order B&W Complete None-see reactor-trips. Requirement 10
below
4. Small-break LOCA analysis, procedures, Coommission Order B&W Complete I.A.3.1 and operator training. , I.C.1
5. Complete TMI-2 simulator training for Commission Order B&W Complete. I.A.2.6 all operators.
6. Reevaluate analysis for dual-level Commission Order Davis-Besse 1 Complete NA
setpoint control.
7. Reevaluate transient of September 24, Commission Order Davis-Besse 1 Complete NA
1977.
8. Continued upgrading of AFW system. Commission Order B&W 1/1/81 II.E.1 C.2-1
TABLE C.2 (continued)
Operating Operating Reouirement Source Applicability Reactor License Implementation Implementation
9. Analysis and upgrading of integrated Commission Order B&W 1/1/81 Same as ORs, control system. before OL
10. 1ard-wired safety-grade anticipatory Commission Order B&W 1/1/81 Same as ORs, reactor trips. before OL
11. Operator training and drilling. Commission Order B&W 1/1/81 I.A.3.1 I.A.2.2 I.A.2.5 I.G.1
12. Transient analysis and procedures for Commission Order B&W I.C.1 I.C.1 management of small breaks.
13. Thermal-mechanical report -- effect Letter, D. Ross to B&W 1/1/81 Same as ORs, of HPI on vessel integrity for small- B&W operating plants, before OL
break LOCA with no AFW. 8/21/79
14. Demonstrate that predicted lift Letter, 0. Ross to B&W 1/1/81 Sanme as ORs, frequency of PORVs and SVs is B&W operating plants, before OL
acceptable. 8/21/79
15. Analysis of effects of slug flow on Letter, D. Ross to B&W 6/1/80 Same as ORs, once-through steam generator tubes B&W operating-pldnts, before OL
after primary system voiding. 8/21/79 C.2-2
TABLE C.2 (continued)
Operatil u OperaLi uUJ
Requirement Source Applicability Reactor License Implecientation Implementation
16. Impact of RCP seal damage following Letter, D. Ross to B&W 6/1/80 Sanie as ORs, small-break LOCA with loss of offsite B&W operating before OL
power. plants, 8/21/79
17. Analysis of potential voiding in Letter, R. Reid All B&W 1/1/81 I.C.1 RCS during anticipated transients. to all B&W operating plants 1/9/80
18. Analysis of loss of feedwater and Letter, 0. Ross to All B&W I.C.1 I.C.1 other anticipated transients. B&W operating plants,
8/21/79
19. Benchmark analysis of sequential Letter, D. Ross to All B&W 1/1/81 I.C.1 AFW flow to once-through steam B&W operating plants, generator. 8/21/79
20. Analysis of system response to small- Letter, D. Ross to All B&W 1/1/81 I.C.1 break LOCA that causes system pressure B&W operating plants to exceed PORV setpoint. 8/21/79
21. LOFT 3-1 predictions. Letter, D. Ross to All B&W Complete None B&W operating plants,
8/21/79 C.2-3
TABLE C.3 FINAL RECOMMENDATIONS OF BULLETINS AND ORDERS TASK FORCE
Near-Term Operating Operating Operating Reactor License License Requirement Source Applicability Implementation Implementation Requirements
1. Install automatic PORV isolation NUREG-0565(2.1.2.a) PWR 7/1/81 Same as OR NA
system and perform operational NUREG-0611(3.2.4.e and first test. 3.2.4.f) refueling NUREG-0635(3.2.4.a) and depending on
(3.2.4.b) results of item 2, below.
2. Report on overall safety effect NUREG-0565 (2.1.2.d)
of PORV isolation system. NUREG-0611(3.2.4.g, PWRs 1/1/81 Same as OR NA
3.2.4.i)
NUREG-0635(3.2.4.c)
3. Report safety and relief valve NUREG-0565(2.1.2.c, All 4/1/80 Same as.OR FP
failures promptly and challenges 2.1.2.e)
annually. NUREG-0611(3.2.4.h,
3.2.4.j)
NUREG-0626(B.14)
NUREG-0635(3.2.4.d)
4. Review and upgrade reliability NUREG-0565(2.3.2.b) All None II.C.1 NA
and redundancy of non-safety NUREG-0611(3.2.2.b) II.C.2 equlJpAlent for small-break LOCA NUREG-0626 (B.12, II.C.3 mitigation. NUREG-0635(3.2.2.b)
5. Continue to study need for NUREG-0565(2.3.2.a) PWR Study - Same as OR NA
C.1.4.c and need for auto- NUREG-0611(3.2.2.a) 1/1/81 matic trip of RCPs, then NUREG-0635(3.2.2.a) Modify -
modify procedures or designs NUREG-0623 1/1/82 as appropriate.
C.3-1
TABLE C.3 (continued)
Near-Term Operating Operating Operating Reactor License License Requi rement Source Applicability Implementation Implementation Requi rements
6. Instrumentation to verify NUJRCG-0565(2.6.2.b) PWR I. c. 1 I. C.1 NA
natural circulation. NUREG-0611(3.2.3.b) II. F.2 I. F.2 NUREG-0635(3.2.3.b) II. F. 3 II. F.3
7. Evaluation of PORV opening NUREG-0565(2. i.2.b) O&W See Table See Table NA
probability during overpressure C.2, item C.2, item transi ent. 14 14
8. Further staff consideration of NUREG-0565(2.5.2.a) PWR II.C.1 II.C.1 NA
need for diverse decay heat NUREG-0635 (4.2.5.,
removal method independent App. VIII)
of SG's NUREG-0611 (4.2.5, II.E.3.3 II.E.3.3 App. VIII)
9. Pre'ssure Integral Derivative NUREG-0611(3.2.4.b) W 7/1/80 Same as OR FL
controller modification.
10. Anticipatory trip modifcation NUREG-0611(3.2.4.c) W Plant by Same as OR FL
proposed by some licensees to plant confine range of use to high power levels.
11. Control use of PORV supplied NUREG-0611(3.2.4.d) All Case by Same as OR FL
by Control Components Inc. until case further review complete.
12. Confirm existence of anticipa- NUREG-0611(3.2.4.a) W 7/1/80 Same as OR FL
tory trip upon turbine trip.
C.3-2
TABLE C.3 (continued)
Near- Term Operating Operating O)erati ng Reactor License License Requi rewent Source Applicability Implementation Implementation Requi rements
13. Separation of IIPCI and RCIC NUREG-0626(A.1) GE Analyses - Same as OR NA
system initiation levels. 10/1/80
Analysis and impliementation. Implement -
4/1/81
14. Isolation of isolation NUREG-0626(A.2) GE plants 1/1/81 NA NA
condensers on high radiation. with isolation condenser
15. Modify break detection logic NUREG-0626(A.3) GE 1/1/81 Same as OR NA
to prevent spurious isolation of HIPCI and RCIC systems.
16. Reduction of challenges and NUREG-0626(A.4) GE Study - Same as OR NA
failures of relief valves - 1/1/81 feasibility study and system Modify -
modification. 1/1/82
17. Report on outage of ECC NUREG-0626(A.6) GE 1/1/81 Same as OR NA
systems - licensee report and proposed technical specification changes.
18. Modification of ADS logic - NUREG-0626(A.7) GE Study - Same as OR NA
feasibility study and modifica- V1//81 tion for increased diversity Modify -
for some event sequences. 1/1/82 C.3-3
TABLE C.3 (continued)
Near-Term Operating Operating Operating Reactor License License Requirement Source Applicability Implementation Implementation Requirements
19. Interlock on recirculation NUREG-0626(A.8) GE Non-Jet 1/1/81 NA NA
pump loops. Pump ORs
20. Loss of service water for NUREG-0626(A.9) Big Rock 1/1/81 NA NA
Big Rock Point. Point
21. Restart of core spray and LPCI NUREG-0626(A.10) GE Design - Same as OR NA
systems on low level - design 1/1/81 and modification. Modify -
1/1/82
22. Automatic switchover of RCIC NUREG-0626(B.1) GE Verify - Same as OR NA
system suction - verify 1/1/81 procedures and modify design. Modify -
1/1/82
23. Central water level recording. NUREG-0626(B.2) GE I.D.2 I.D.2 NA
III.A.1.2 III.A.1.2 III.A.3.4 III.A.3.4
24. Confirm adequacy of space cool- NUREG-0626(B.3) GE 1/1/82 Same as OR NA
ing for HPCI and RCIC systems.
25. Effect of loss of AC power on NUREG-0626(B.4) GE 1/1/82 Same as OR NA
pump seals.
C.3-4
TABLE C.3 (continued)
Near-Term Operating Operating Operating Reactor Licens.e License Requi reineit Source Applicability Implementation Implementation Requirements
26. Study effect on RIR reliability NUREG-0626(0.5) GE II.E.2.1 II.E.2.1 NA
of its use for fuel pool cooling.
21. Provied coiwiinoi rteference level NUREG-0626(B.G) GE 10/1/80 Same as Oil NA
for vessel level instrumentation.
28. Study and verify qualification NUREG-0626(B.7) GE 1/1/82 Same as OR NA
of accumulators on ADS valves.
29. Study to demonstrate perform- NUREG-0626(B.13) GE Isolation 4/1/81 NA NA
ance of isolation condensers Condenser ORs with non-condensibles.
30. Revised small-break LOCA methods NUREG-0565(2.2.2.a) All Beyond Same as OR NA
to show compliance with 10 CFR NUREG-0611(3.2.1.a) 1982
50, Appendix K. NUREG-0626(A.12)
NUREG-0635(3.2.1.a)
(3.2.5.a)
31. Plant-specific calculations to NUREG-0565(2.2.2.b) All Beyond Same as OR NA
show compliance with 10 CFR NUREG-0611(3.2.1.b) 1982
50.46. NUREG-0626(A.13, 8.10)
NUREG-0635(3.2.1.b)
C.3-5
TABLE C.3 (.continued)
Nr-_r Ncar-Term Operating Operating Operat infg Reactor License License Requ ireinent Source Applicability IMIpleilntation iinpl etnentati on Requ i remenlts NUREG-0565(2.6.2.a) PWR NA NA NA
32. Provide experimlental verifica- Lion of two-phase natural NURCG-0611(3.2.3.a) (Matter under consideration for Semiscale/LOFT
circul ati on models. NUREG-0635(3.2.3.a) - see II.E.2.2 and for a PWR startup)
NUIREG-0565(3.5) PWR II.C.1 II.C.1 NA
33. Evaluate elimination of PORV
function. NUREG-0611(3.2.4.k)
NUREG-0635(3. 2.4.e)
NUREG-0611(3.2.5) PWR NA NA NA
34. RELAP-4 model development.
NIUREG-0635(3.2.5) (II.E.2.2 covers this staff action)
NUREG-0565(2.2.2.c) B&W I.C.1 I.C.1 NA
35. Evaluation of effects of core flood tank injection on small- break LOCAs.
NUREG-0565(2.4.2.a) B&W NA NA NA
36. Additional staff audit calcula- tions of B&W small-break LOCA (I.C.1 covers this staff action)
analyses.
B&W I.C.1 I.C.1 NA
37. Analysis of B&W plant response NUREG-0565(2.6.2.c)
to isolated small-break LOCA.
NUREG-0565(2.6.2.d) B&W I.C.1 I.C.1 NA
38. Analysis of plant response to a small-break LOCA in the pressurizer spray line.
C.3-6
TABLE C.3 (continued)
Near-Term Operating Operating Operating Reactor License License Requirement Source Applicability Implementation Implementation Requirements
39. Evaluation of effects of water NUREG-0565(2.6.2.e) B&W I.C.1 I.C.1 NA
slugs in piping caused by HPI
and CFT flows.
40. Evaluation of RCP seal damage NUREG-0565(2.6.2.f) B&W See Table C-2, See Table C.2, NA
and leakage during a small- item 16 item 16 break LOCA.
41. Submit predictions for LOFT Test NUREG-0565(2.6.2.g) B&W I.C.1 I.C.1 NA
13-6 with RCPs running.
42. Submit requested information NUREG-0565(2.6.2.h) B&W I.C.1 I.C.1 NA
on the effects of non- condensible gases.
43. Evaluation of mechanical effects NUREG-0565(2.6.2.i) B&W See Table C-2, See Table C.2, NA
of slug flow on steam generator item 15 item 15 tubes.
44. Evaluation of anticipated NUREG-0626(A.14) GE 1/1/81 Same as OR NA
transients with single failure to verify no significant fuel failure.
45. Evaluate depressurization with NUREG-0626(A.15) GE 1/1/81 Same as OR NA
other than full ADS.
C.3-7
rABLE C.3 (continued)
Near-Term Operating Operating Operating Reactor License License Retti ireienIL Source Applicability Implemen tation Implementation Requirements
46. Response to list of concerns NUREG-0626(A.17) GE 7/1/80 Same as OR NA
from ACRS consultant.
47. Test program for small-break NUREG-0626(B.9) GE I.C.1 I.C.1 NA
LOCA model verification pretest II.E.2.2 II.E.2.2 prediction test program and model verification.
48. Assess change in safety NUREG-0626(B.15) GE II.C.1 II.C.1 NA
reliability as result of imple- II.C.2 II.C.2 menting B&OlF recoinmendations.
49. Review of procedures (NRC). NUREG-0611(3.4.1) W, CE I.C.9 I.C.8 NA
NUREG-0635(3.4.1) I.C.9
50. Review of procedures NUREG-O611(3.4.2) W, CE I.C.9 I.C.7 NA
(NSSS vendors) NUREG-0635(3.4.2) I.C.9
51. Symptom-based emergency NUREG-0611(3.4.3) W, CE I.C.9 I.C.9 NA
procedures. NUREG-0626(B.8) GE
NUREG-0635(3.4.3)
52. Operator awareness of revised NUREG-0626(A.11) GE I.B.1 I.B.1 NA
emergency procedures. I.C.2 I.C.2 I.C.5 I.C.5 C.3-8
TABLE C.3 (continued)
Near-Term Operating Operating Operating Reactor License License Requi rement Source Applicability Implementation Implementation Requirements
53. Two operators in control room. NUREG-0626(A.16) GE I.A.1.3 I.A.1.3 NA
54. Simulator upgrade for small- NUREG-0565(2.3.2.c) All I.A.4.1 I.A.4.1 NA
break LOCAs. NUREG-0611(3.3.1.b)
NUREG-0626(B.11)
NUREG-0635(3. 3.1. b)
55. Operator monitoring of control NUREG-0611(3.5.1) W, CE I.C.1 I.C.1 NA
board. NUREG-0635(3.5.1) I.D.2 I.D.2 I.D.3 I.D.3
56. Simulator training requirements. NUREG-0611(3.3.1.a) W, CE I.A.3.1 I.A.3.1 NA
NUREG-0635(3.3.1.a) I.A.2.6 I.A.2.6
57. Identify water sources NUREG-0626(A.5) GE 10/1/80 I.C.1 NA
prior to manual activation of ADS
C.3-9 I
ENCLOSURE 4 WORKER RADIATION PROTECTION IMPROVEMENTS
PART 1: Staff Requirements III.D.3.4 PART 2: Copy of Section III.D.3 to NRC Task Action Plan
The following nine pages are the May 1980 version of the TMI Action Plan,Section III.D.3. This section is provided for background information only aridnote that the subject being discussed with respect to OLirpositions on the Control Room Habitability Requirements is a subpart.
Control Room Habitability Requirements Position In accordance with action item III.D.3.4, Control Room Habitability, licensees shall assure that control room operators will be adequately protected against the effects of accidental release of toxic and radioactive gases and that the nuclear power plant can be safely operated or shut down under design basis accident conditions (Criterion 19, "Control Room," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50).
Clarification All facilities that have not been reviewed for conformance with the following sections of the Standard Review Plan:
2.2.1-2.2.2 Identification of Potential Hazards in Site Vicinity;
2.2.3 Evaluation of Potential Accidents;
6.4 Habitability Systems;
shall perform the necessary evaluations and recommend appropriate modifica- tions to meet control room habitability requirements. The following docu- ments may be used for guidance in performing the. required evaluations:
1. Regulatory Guide 1.78, "Assumptions of Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release."
2. Regulatory Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release."
3. K. G. Murphy and K. M. Campe, "Nuclear Power Plant Control Room Ventilation System Design for Meeting General Design Criterion 19,"
13th AEC Air Cleaning Conference, August, 1974.
The licensees submittal shall include the results of the analyses of control room concentrations from postulated accidental release of toxic gases and
-2- control room operator radiation exposures from airborne radioactive material and direct radiation resulting from design basis accidents. The toxic gas accident analysis should be performed for all potential hazardous chemical releases occurring either on the site or within five miles of plant site boundary. Regulatory Guide 1.78 lists the chemicals most commonly en- countered in the evaluation of control room habitability but is not all- inclusive.
The DBA radiation source term should be for the LOCA containment leakage and ESF leakage contribution outside containment as described in Appendix A and B of Standard Review Plan Chapter 15.6.5. In addition, BWR facility evaluations should add any leakage from the main steam isolation valves (e.g., valve stem leakage, valve seat leakage, main steam isolation valve leakage control system release) to the containment leakage and ESF leakage following a LOCA. Other DBA's should be reviewed to determine whether they might constitute a more severe control room hazard than the LOCA.
In addition to the accident analysis results which should either identify the possible need for control room modifications or provide assurance that the habitability systems will operate under all postulated conditions to permit the control room operators to remain in the control room to take appropriate actions as required by General Design Criteria 19, the licensee should submit sufficient information needed for an independent evaluation of the adequacy of the habitability systems. Attachment 1 lists the in- formation that should be provided along with the licensee's evaluation.
ACTION- (Class II)
Licensees should submit their responses to this request on or before January 1, 1981. Modifications needed for compliance with the control room habitability requirements specified in this letter should be identified and a schedule for completion of the modifications should be provided. Implemen- tation of such modifications should be started without awaiting for the results of the staff's review. Additional needed modifications, if any, identified by the staff during its review will be specified to licensees by July 1981. All modifications must be scheduled for completion by January 1,
1983.
ATTACHMENT 1 Information Required for Control Room Habitability Evaluation.
1. Control Room Mode of Operation, i.e., pressurization and filter re- circulation for radiological accident isolation or chlorine release
2. Control Room Characteristics a. air Yolume of control room b. control room emergency zone (control room, critical files, kitchen, washroom, computer room, etc.)
c. control room ventilation system schematic with normal and emergency air flow rates d. infiltration leakage rate e. HEPA filter and'charcoal adsorber efficiencies f. closest distance between containment and iir.intake g. layout of control room, air intakes, containment building, and chlorine or other chemical storage facility with dimensions h. control room shielding including radiation streaming from penetrations, doors, ducts, stairways, etc.
i. automatic isolation capability-dampeP closing time, damper leakage and area J. chlorine detectors or toxic gas (local or remote)
k. self-contained breathing apparatus availability (number)
1. bottled air supply (hours supply)
m. emergency food and potable water supply (how many days and how many people)
n. control room personnel capacity (normal and emergency)
o. potassium iodide drug supply
3. On-site storage of chlorine and other hazardous chemicals a. total amount and size of container b. closest distance from control room air intake
4. Off-site manufacturing, storage or transportation facilities of hazardous chemicals a. identify facilities within a five-mile radius b. distance from control room c. quantity of hazardous chemicals in one container d. frequency of hazardous chemical transportation traffic (truck, rail, and barge)-
-2-
5. Technical Specifications (refer to standard technical specifications)
a. chlorine detection system b. control room emergency filtration system including gross leakage determination by control room pressurization at l.8 inch water gage, verification of isolation by test signals and damper closure times and filter testing requirements.
.
Task III.D.3 May 1980
TASK III.D.3 WORKER RADIATION PROTECTION IMPROVEMENT
A. OBJECTIVE: Improve nuclear power plant worker radiation protection to allow workers to take effective action to control the course and consequences cf an accident, as well as to keep exposures as low as reasonably achievable (ALARA) during normal operation and accidents, by improving radiation protec- ticn plans, health physics, inplant radiation monitoring, control room habitability, and radiation worker exposure data base.
B. NRC ACTIONS
1. Radiation protection plans.
a. Description: NRC will require all licensees to prepare and implement radiation protection plans (RPP) that will incorporate commitments to criteria in existing Regulatory Guides, including Regulatory Guide 8.8, and Standard Review Plan Chapter 12, as well as criteria to be developed from analysis of tl.e _ appraisal of health physics programs at all operating sites. The RPP
wi l be integrated into the emergency plan to assure worker protection without
.. .;uy restricting accident mitigation and recovery.
The results of the following task action items will be incorporated into the RP; Item I.A.1, "Operating Personnel and Staffing," to determine the necessary nurber and types of radiation protection personnel for each shift and to investigate the desirability of separation of the radiation protection and chemistry functions; Item I.A.2, "Training and Qualifications of Operating Personnel," to review the training program for radiation protection personnel and develop new regulations or guides for such personnel; Item I.A.3, "Licensing ant Requalifications of Operating Personnel," to study the need for licensing r_ ,atjn protection personnel; and Item I.B.1, "Organization and Management
.riteria," to determine the organization and qualifications of the radiation protection staff.
III.D.3-1
Task III.D.3 May 1980
(1) NRR will, in cooperation with IE and SD, precare a draft Guidie for the preparation of an RPP that will include an existing draft Guide on
'-7]ementaticn of ALARA at Operating Plants."
(2) NRR will develop acceptance criteria using existing regulatory guices, the Standard Review Plan, and information to be developed on the bas s of feedback from ongoing IE comprehensive appraisals at all operating reactors to assess the adequacy of existing radiation protection programs.
(3) NRR will publish for review and action by licensees the draft RPP Guide (see item 1 above), which will specify format, content, and acceptance criteria, including guidance on implementing ALARA at operating plants and will send an information notice to licensees providing clarification that all health physics personnel, including temporary contractor personnel, must meet the tech- nical specification training and qualifications requirements.
(4) NRR will hold regional meetings to discuss Implementation of RPPs and to receive comments on improvements in the draft Guide.
(5) NRR will revise the draft Guide based on the feedback obtained at the regional meetings and from IE.
(6) NRR will require licensees to provide RPPs and request amendment of technical specifications, including a commitment to ixplement the RPP.
(7) NRR will review the RPPs and, for reference, the amended technical specifications.
(8) NRR will revise Standard Review Plan Section 12.5, "Health Physics Proc-am," to include the RPP Guide in the acceptance criteria.
(9) SD will revise Regulatory Guide 1.70, "Standard Format and Content cF Safety Analysis Reports for Nuclear Power Plants."
b. Schedule: Initiate NRC work in FY82, or later.
IIT. .3-2
Task III.D.3 May 1980
c. Resources: NRR first FY - 2 my, second FY - 0.1 my per site for 40%
of sites, third FY - 0.1 my per site for 60% of sites; SD first FY - 0.7 my, third FY - 0.2 my; IE first FY - 0.55 my; ADM first FY - 0.1 my and $10,000,
second FY - 0.2 my and $20,000.
2. Health physics improvements.
a. Description: The accuracy of health physics measurements for both routine and emergency conditions is to be improved. Accurate high dose rate warning devices and radioiodine respiratory protection are needed.
(1) SD will amend 10 CFR 20 to require that personnel dosimetry processing be done only by nationally certified processors who meet specific performance criteria (utilities could themselves become certified if they desire).
(2) SD will issue a regulatory guide containing specifications for audible alarm dosimeters and criteria for their use.
(3) SD, in cooperation with the American National Standards Institute (A.ISI), will develop standard performance criteria for radiation survey and monitoring instruments. SD will contract for performance testing of on-the-shelf instruments to determine feasibility of the standards. NRC will adopt a final standard and require that only instruments meeting the standard be used at licensed facilities.
(4) Under contract with RES, the Los Alamos Scientific Laboratory will develop a method for testing and certifying air-purifying respirators for use against radioiodines. The method and equipment will be transferred to NIOSH,
and NIOSH will be requested to amend 30 CFR 11 to incorporate the method into respirator test and certification schedules. NRR will evaluate the need to specify the quantity and types of respirators necessary for normal and emergency use.
N I.0.3-3
Task III.D.3 Mlay 1i80
b. Schedule: This is a Decision Group 0 item. Therefore, schedules and resources are to be developed in connection with routine agency oudgetary Processes.
c. Resources: See "Schedule" above.
3. Inplant radiation monitoring.
a. Description: Licensees are to improve systems for monitoring inplant radiation and airborne radioactivity with instruments appropriate for a broad range of routine and emergency conditions and to provide calibration methods for such instruments.
(1) NRR has issued a letter requiring improved radioiodine sampling instrumentation (NUREG-0578, 2.1.8.c).
(2) NRR will set criteria requiring licensees to evaluate in their plants the need for additional survey equipment and radiation monitors in vital areas and requiring, as necessary, installation of area monitors with remote readout. NRR will evaluate the need to specify the minimum types and quantities C, portable monitoring instrumentation, including very high dose rate survey instruments. Operating reactors will be reviewed for conformance with Standard Review Plan Section 12.3.4, "Area Radiation and Airborne Radioactivity Monitoring Instrumentation." NRR will revise Standard Review Plan Sections 12.5 ana +/-2.3.4 to incorporate additional monitor requirement criteria. I'E w..ill inspect implementation.
(3) SD will issue a rule change providing acceptable methods for cavibration of radiation-monitoring instruments.
(4) SD will issue a Regulatory Guide providing acceptable methods
-r calibration of air-sampling instruments.
III. D. 3-4
Task III.D.3 May 1980
monitoring b. Schedule: NRR issued requirements regarding radioiodine NRC work on require- by letter to operating plant licensees on October 30, 1979;
rill be initiated ments regarding area monitors and portable instrumentation D items; schedules In FY82, or later. Items (3) and (4) above are Decision Group agency budgetary and resources are to be developed in connection with routine processes.
FY81 0.1 my c. Resources: NRR FY 80- 0.3 my and $60,000 for contract, my; ADM FY 80 -
and $120,000 for contract; IE FY80 - 0.1 my, FY81 - 0.2
0.1 and $5,000, FY81 - 0.1 my and $5,000.
that workers a. Description: NRR will follow a two-step approach to assure other hazards, and are adequately protected from radioactivity', radiation, and First, NRR
that the control room can be used in the event of an emergency.
conformance to Regu- will require all facilities that have not been reviewed for
2.2.1, 2.2.2, latory Guides 1.78 and 1.95 and Standard Review Plan Sections for necestary
2.2.3, and 6.4 to do the evaluations and establish a schedule for near-tarm modifications. This will be a condition of full-power operation with the rulenaking operating license facilities. Then, NRR will, in conjunction and pathways of proposed in Item II.B.8, examine and evaluate other sources habitability problems, radioactivity and radiation that may lead to control room the Regulatory Guides and will, if necessary, make changes in the requirements of the plant) pathways and the Standard Review Plan. Such potential internal (to TMI-2 accident.
for potential control room contamination were flagged by the doses due to such Review and quantification of potential control room operator pathways internal airborne radioactivity ingress and radiation penetration from to plant structures will be the basis for such changes.
reactors by b. Schedule: NRR will issue the requirements for operating NRR will complete evalua-
[lay 1980, regarding the existing criteria listed above.
by July 1981.
tion of licensee responses and notify licensees of acceptance conformance by no later
1E will complete inspections on a case-by-case basis for dependent on the results than July 1983. Longer term changes in criteria will be of the rulemaking proceeding on degraded cores.
III. 0.3-5
Task III.0.3 May 1980
c. Resources: NRR FY80 - 0.7 my, $110,000, FY81 - 1.2 my, $90,000; IE
F-0 - 0.1 my, FY81 - 0.7 my; ADM FY80 - 0.1 my, FY81 - 0.2 my.
5. Radiation worker exposure data base.
a. Description: NRC will continue its efforts to improve and expand the data base on industry employees to facilitate possible future epidemiological studies on worker health.
(1) The NRC staff has been actively engaged in this and similar efforts for some time. Examples are our participation in the working groups of the interagency Task Force on the Health Effects of Ionizing Radiation (the so-called Li-assi Committee), the Fredrickson Committee on Federal Research on the Biological Effects of Ionizing Radiation Research (NIH), and the Upton Subcommittee on T.1I Followup Studies (NIH).
More recently, NRC and NIOSH have been cooperating to establish a worker registry at TmlI to facilitate possible future health studies. We also have been in contact with -PRI to investigate expansion of our efforts to the entire U.S. nuclear utility industry. In addition, SD has funded an epidemiology feasibility and planning study which, among other things, will provide information on how to
-t.Zrove the worker's health and exposure data base.
SO will develop a format for data to be collected by utilities regarding total radiation exposures to workers, as well as other data pertinent to eventual epidemiological studies. These data will include both external and internal doses, medical radiation exposures, health data, and exposure to nonradioactive carcinogens (both within and outside of the workplace).
(2) NRC will investigate methods of obtaining employee health data i:
,onlegislative means until such time as legislation is passed allowing routine collection of these data by NRC.
(3) SD will, following appropriate legislative action to permit such regulatory requirement, revise 10 CFR 20 to require licensees to collect worker data.
III. 0. 3-6
Task III.D.3 May 1980
b. Schedule: This is a Decision Group 0 item. Therefore, schedules and resources are to be developed in connection with routine agency budgetary processes.
c. Resources: See "Schedule" above.
C. LICENSEE ACTIONS
1. Radiation protection plans.
a. Description: Operating reactor licensees will develop an RPP based on NRC guidance and propose a technical specification change. Following NRC
review, the licensees will take corrective actions, as necessary, based on inspection findings.
b. Implementation: Operating reactors will complete by 15 months after issuance of requirement by NRC; operating license applicants will complete before fuel loading or by 15 months after issuance of requirement by NRC, whichever is later.
c. Resources: .1.0 my per reactor; $5,000 for printing RPP and related procedures.
2. Health physics improvements: This is a Decision Grouo D item.
3. Inplant radiation monitoring.
a. Description: Licensees must evaluate locations and ranges of radio- iodine monitors, provide results to NRC, and install new monitors as required.
They must also comply with the rule on radiation monitoring instruments and the Regulatory Guide on air-sampling instruments.
b. Implementation: Operating reactors and near-term operating license applicants must have radioiodine detection capability by January 1, 1980 or before fuel loading and must add area monitors and a low-background area for III. D. 3-7
Task III.D.3 May 1980
iodine analysis by June 1982; other operating license applicants and construc- ti:,n permit holders must comply by June 1982 or prior to licensing for opera-
- n, Whichever is later.
-.
c. Resources: Evaluation of radioiodine detection capability will require
0.2 my per reactor, and the addition of monitors will require 0.2 my and $50,000
De- monitor.
a. Description: Licensees must review.control room habitability against specified guidance and make necessary modifications.
b. Implementation: For operating reactors, reviews must be complete by
'anuary 1981, and modifications must be complete by January 1983; operating license applicants must schedule necessary modifications to achieve compliance
2efore full-power operation; construction permit holders must comply before an ocprating license is issued.
c. Resources: 2.0 my and $500,000 per reactor for operating reactors.
',imate one-tenth of this for NTOLs that are likely to be substantially in compliance with existing guidance.
a. Radiation worker exposure data base: This is a a Decision Group D item.
0. OTHER ACTIONS: None.
E. REFERENCES
President's Commission Report: Items A.4.c.3iii, A.5, 8.3, E.1.c, E.4
-°ents Response, dated December 7, 1979 III.0.3-8
Task III.D.3 May 1980
NUREG-0578, Recommendation 2.1.8.C
NUREG-0600, Recommendations 26, 27, and 28
.UREG-0616, Recommendations 2.5.5, 2.6.1.5 NUREG/CR-1250, Vol. I, p. 155; Vol. II, Part 2, pp 39, 135, 141, II
143, 147, 157, 158, 161, 172. The page numbers given here for Vol.
are draft page numbers.
"US-3364, Review of the Health-Physics Program at the Three iGenerlc Mile Island Nuclear Station," March 20, 1979 Letter from Chairman, ACRS, to Chairman, NRC, dated March 11,
1980; Subject: "ACRS Report on NTOL Items from Draft 3 of NUREG-0660, NRC Action Plans Developed as a Result of the TMI-2 Accident"
III. 0. 3-9
Mr. Donald P. Dise Nine Mile Point Niagara Mohawk Power Corporation 50-220
cc:1 Eugene B. Thomas, Jr., Esquire LeBoeuf, Lamb, Leiby & MacRae
1757 N Street, N.W.
Washington, D. C. 20036 State University College at Oswego Penfield Library - Documents Oswego, New York 13126 Mr. Donald P. Dise Vice President - Engineering c/o Miss Catherine R. Seibert Niagara Mohawk Power Corporation
300 Erie Boulevard West Syracuse, New York 13202
Mr. D. Louis Peoples Quad Cities Units 1 and 2 Commonwealth Edison Company
50-254/265 cc:
Mr. D. R. Stichnoth President Iowa-Illinois Gas and Electric Company
206 East Second Avenue Davenport, Iowa 52801 Mr. John W. Rowe Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. Nick Kalivianakas Plant Superintendent Quad Cities Nuclear Power Station
22710 - 206th Avenue - North Cordova, Illinois 61242 Moline Public Library
504 - 17th Street Moline, Illinois 61265 Susan N. Sekuler Assistant Attorney General Environmental Control Division
188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Mr. N. Chrissotimos, Inspector U. S. Nuclear Regulatory Commission Box 756 Bettendorf, Iowa 52722 Mr. D. Louis Peoples Director of Nuclear Licensing Commonwealth Edison Company P. 0. Box 767 Chicago, Illinois 60690
Mr. D. Louis Peoples Dresden 3 Commonwealth Edison Company 50-249 cc:
Mr. John W. Rowe Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450
Morris Public Library
604 Liberty Street Morris, Illinois 60451 U. S. Nuclear Regulatory Commission Resident Inspector's Office Dresden Station RR #1 Morris, Illinois 60450
Susan N. Sekuler Assistant Attorney General Environmental Control Division
188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Mr. Louis D. Peoples Director of Nuclear Licensing Commonwealth Edison Company P. 0. Box 767 Chicago, Illinois 60690
Mr. Hugh G. Parris Browns Ferry Plant Units 1, 2 and 3 Tennessee Valley Authority 50-259/260/296 cc:
H. S. Sanger, Jr., Esquire General Counsel Tennessee Valley Authority
400 Commerce Avenue E 11B 33 C
Knoxville, Tennessee 37902 Mr. Ron Rogers Tennessee Valley Authority
400 Chestnut Street, Tower II
Chattanooga, Tennessee 37401 Mr. H. N. Culver
249A HBD
400 Commerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 Robert F. Sullivan U. S. Nuclear Regulatory Commission P. 0. Box 1863 Decatur, Alabama 35602 Athens Public Library South and Forrest Athens, Alabama 35611 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority
500 A Chestnut Street, Tower II
Chattanooga, Tennessee 37401
Mr. J. A. Jones Brunswick Steam Electric'Plant Units 1 & 2 Carolina Power & Light Company 50-325/324 cc:
Richard E. Jones, Esquire Carolina Power & Light Company
336 Fayetteville Street Raleigh, North Carolina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge
1800 M Street, N. W.
Washington, D. C. 20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot
110 North Fifth Avenue Wilmington, North Carolina 28401 Resident Inspector U. S. Nuclear Re9ulatory Commission P. 0. Box 1057 Southport, North Carolina 28461 Southport - Brunswick County Library
109 W. Moore Street Southport, North Carolina 28461 Mr. Fred Tollison Plant Manager P. 0. Box 458 Southport, North Carolina 28461 Mr. J. A. Jones Executive Vice President Carolina Power & Light Company
336 Fayetteville Street Raleigh, North Carolina 27602
Mr. William Widner 50-321/366 Georgia Power Company Edwin I. Hatch Nuclear Plant cc:
G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge
1800 M Street, N. W.
Washington, D. C. 20036 Ruble A. Thomas Vice President P. 0. Box 2625 Southern Services, Inc.
Birmingham, Alabama 35202 Ozen Batum P. 0. Box 2625 Southern Services, Inc.
Birmingham, Alabama 35202 Mr. L. T. Gucwa Georgia Power Company Engineering Department P. 0. Box 4545 Atlanta, Georgia 30302 Appling County Public Library Parker Street Baxley, Georgia 31413 Mr. R. F. Rogers U. S. Nuclear Regulatory Commission P. 0. Box 710
Baxley, Georgia 31513 Mr. William Widner Vice President - Engineering Georgia Power Company P. 0. Box 4545 Atlanta, Georgia 30302
Mr. G. Carl Andognini Pilgrim Nuclear Power Station Boston Edison Company 50-293 cc:
Mr. Paul J. McGuire Pilgrim Station Acting Manager Boston Edison Company RFD #1, Rocky Hill Road Plymouth, Massachusetts 02360
Henry Herrmann, Esquire Massachusetts Wildlife Federation
151 Tremont Street Boston, Massachusetts 02111 Plymouth Public Library North Street Plymouth, Massachusetts 02360
Mr. G. Carl Andognini Boston Edison Company M/C NUCLEAR
800 Boylston Street Boston, Massachusetts 02199
Commonwealth Edison Company Docket Nos. 50-295/304 Zion Station, Unit Nos. 1 and 2 cc: Mr. D. Louis Peoples Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Robert J. Vollen, Esquire
109 North Dearborn Street Chicago, Illinois 60602 Dr. Cecil Lue-Hing Director of Research and Development Metropolitan Sanitary District of Greater Chicago
100 East Erie Street Chicago, Illinois 60611 Zion-Benton Public Library District
2600 Emmaus Avenue Zion, Illinois 60099 Mr. Phillip P. Steptoe Isham, Lincoln and Beale Counselors at Law One First National Plaza
42nd Floor Chicago,.Illinois 60603 Susan N. Sekuler, Esquire Assistant Attorney General Environmental Control.Division
188 West Randolph Street, Suite 2315 Chicago, Illinois 60601 U. S. Nuclear Regulatory Commission Resident Inspectors Office Post Office Box 288 Deerfield, Illinois 60015
Consolidated Edison Company of New York, Inc.
Indian Point Nuclear Plant, Unit Nos. 1 and 2 Docket Nos. 50-3/247 cc: Mr. William J. Cahill, Jr. Ms. Ellyn Weiss Vice President She ldon, Harmon and Weiss Consolidated Edison Company 172'5 I Street, N.W.
of New York, Inc. Sul te 506
4 Irving Place Was hington, 0. C. 20006 New York, New York 10003 White Plains Public Library
100 Martine Avenue White Plains, New York 10601 Joseph D. Block, Esquire Executive Vice President Administrative Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003 Joyce P. Davis, Esquire Law Department Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003 Richard Remshaw Nuclear Licensing Engineer Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003 Dr. Lawrence R. Quarles Apartment 51 Kendal at Longwood Kennett Square, Pennsylvania 19348 Theodore A. Rebelowski Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 38 Buchanan, New York 10511 John D. O'Toole Assistant Vice President Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003
Alabama Power Company Joseph M. Farley Nuclear Plant Docket No. 50-348 cc: Mr. F. L. Clayton Senior Vice President Alabama Power Company Post Office Box 2641 Birmingham, Alabama 35291 Alan R. Barton Executive Vice President Alabama Power Company Post Office Box 2641 Birmingham, Alabama 35291 Ruble A. Thomas, Vice President Southern Company Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 George F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge
1800 M Street, N.W.
Washington, D. C. 20036 Mr. Robert A. Buettner, Esquire Balch, Bingham, Baker, Hawthorne, Williams and Ward Post Office Box 306 Birmingham, Alabama 35201 Edward H. Keiler, Esquire Keiler and Buckley
9047 Jefferson Highway River Ridge, Louisiana 70123 George S. Houston Memorial Library
212 W. Burdeshaw Street Dothan, Alabama 36303
Carolina Power and Light Company H. B. Robinson, Unit 2 Docket No. 50-261 cc: Mr. J. A. Jones Senior Executive Vice President Carolina Power and Light Company
336 Fayetteville Street Raleigh, North Carolina 27602 G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge
1800 M Street, N.W.
Washington, D. C. 20036 Hartsville Memorial Library Home and Fifth Avenues Hartsville, South Carolina 29550
Michael C. Farrar, Chairman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washingtonj D. C. 20555 Richard S. Salzman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Conmission Washington, D. C. 20555 Dr. W. Reed Johnson Atomic Safety and Licensing Appeal Board Panel '
U. S. Nuclear Regulatory Commission Washington, D. C. 20555
James A. FitzPatrick Nuclear Mr. George T. Berry Power Plant Power Authority of the State of New York 50-333 cc:
Mr. Charles M. Pratt Assistant General Counsel Power Authority of the State of New York
10 Columbus Circle New York, New York 10019 Mr. Peter W. Lyon Senior Vice President -
Nuclear Generation Power Authority of the State of New York
10 Columbus Circle New York, New York 10019 Mr. Raymond J. Pasternak Resident Manager James A. FitzPatrick Nuclear Power Plant P. 0. Box 41 Lycoming, New York 13093 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 George M. Wilverding, Licensing Supervisor Power Authority of the State of New York
10 Columbus Circle New York, New York 10019 State University College at Oswego Penfield Library - Documents Oswego, New York 13126 Mr. George T. Berry President and Chief Operating Officer Power Authority of the State of New York
10 Columbus Circle New York, New York 10019
Mr. Philip A. Crane, Jr. Humboldt Bay Pacific Gas & Electric Company 50-133 cc:
Mr. James Hanchett Public Information Officer Region V - IE
U. S. Nuclear Regulatory Comnission
1990 N. California Boulevard Walnut Creek, California 94596 Humboldt County Library
636 F Street Eureka, California 95501 Michael R. Sherwood, Esq.
Sierra Club Legal Defense Fund, Inc.
311 California Street, Suite 311 San Francisco, California 94104 Linda J. Brown, Esquire Donohew, Jones, Brown & Clifford
100 Van Ness Avenue, 19th Floor San Francisco, California 94102 Dr. Perry Aminoto Department of Conservation Division of Mines & Geology
1416 9th STreet, Room 1341 Sacramento, California 95814 Friends of the Earth ATTN: Andrew Baldwin
124 Spear Street San Francisco, California 94105 Mr. Philip A. Crane Vice President and General Counsel Pacific Gas and Electric Company
77 Beale Street, 31st Floor San Francisco, California 94106 Bruce Norton, Esq.
3216 N. Third Street, Suite 202 Phoenix, Arizona 85012
Vermont Yankee Nuclear Power Station Mr. Robert L. Smith Vermont Yankee Nuclear Power 50-271 Corporation cc:
John R. Stanton, Director Ms. J. M. Abbey Radiation Control Agency Vermont Yankee Nuclear Power Hazen Drive Corporation Concord, New Hampshire 03301
77 Grove Street Rutland, Vermont 05701 John W. Stevens Conservation Society of Mr. Louis H. Heider, Southern Vermont Vice President P. 0. Box 256 Vermont Yankee Nuclear Power Townshend, Vermont 05353 Corporation
25 Research Drive Dr. Mars Longley, Director Westboro, Massachusetts 01581 Occupational & Radiological Heal th
10 Baldwin Street John A. Ritsher, Esquire Ropes & Gray Montpelier, Vermont 05602
225 Franklin Street New England Coalition on Nuclear Boston, Massachusetts 02110 Pollution Hill and Dale Farm Laurie Burt West Hill - Faraway Road Assistant Attorney, General Putney, Vermont 05346 Environmental Protection Division Attorney General's Office Public Service Board One Ashburton Place, 19th Floor State of Vennont Boston Massachusetts 02108 120 State Street Montpelier, Vermont 05602 Ronald J. Wilson
810 18th Street, N. W. W. P. Murphy, Plant Superintendent Suite 802 Vermont Yankee Nuclear Power Washington, D. C. 20006 Corporation P. 0. Box 157 Honorable M. Jerome Diamond Vernon, Vernant 05354 Attorney General State of Vermont Mr. Charles Sheketoff
109 State Street Assistant Director Pavilion Office Building Vermont Public Interest Montpelier, Vermont 05602 Research Group, Inc.
26 State Street Mr. J. E. Griffin, President Montpelier, Vermont 05602 Vermont Yankee Nuclear Power Corporation Brooks Memorial Library
77 Grove Street 224 Main Street Rutland, Vermont 05701 Brattleboro, Vermont 05301 Mr. Robert L. Smith Licensing Engineer Vermont Yankee Nuclear Power Corporation
25 Research Drive Westboro, Massachusetts 01581
Mr. Robert L. Smith - 2 -
cc:
Vermont Yankee Decommissioning Alliance
127 Main Street Brattleboro, Vermont 05301 Vermont Yankee Decommissioning Alliance
5 State Street Box 1117 Montpelier, Vermont 05602
Peach Bottom Atomic Station Mr. Edward G. Bauer, Jr.
Philadelphia Electric Company 50-2771278 cc:
Mr. Edward G. Bauer, Jr.
Eugene J. Bradley Vice President and General Counsel Philadelphia Electric Company Philadelphia Electric Company Assistant General Counsel 2301 Market Street
2301 Market Street Philadephia, Pennsylvania 19101 Philadelphia, Pennsylvania 19101 Troy B. Conner, Jr.
1747 Pennsylvania Avenue, N. W.
Washington, D. C. 20006 Raymond L. Hovis, Esquire
35 South Duke Street York, Pennsylvania 17401 Warren K. Rich, Esquire Assistant Attorney General Department of Natural Resources Annapolis, Maryland 21401 Government Publications Section State Library of Pennsylvania Education Building Commonwealth and Walnut Streets Harrisburg, Pennsylvania 17126 M. J. Cooney, Superintendent Generation Division - Nuclear Philadelphia Electric Company
2301 Market Street Philadelphia, Pennsylvania 19101 Curt Cowgill U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Peach Bottom Atomic Power Station P. 0. Box 399 Delta, Pennsylvania 17314 Philadelphia Electric Company ATTN: Mr. W. T. Ullrich Peach Bottom Atomic Power Station Delta, Pennsylvania 17314
Mr. J. M. Pilant Cooper Nuclear Power Station Nebraska Public Power District 50-298 cc:
Mr. G. D. Watson, General Counsel Nebraska Public Power District P. 0. Box 499 Columbus, Nebraska 68601 Mr. Arthur C. Gehr, Attorney Snell & Wilmer
3100 Valley Center Phoenix, Arizona 85073 Cooper Nuclear Station ATTN: Mr. L. Lessor Station Superintendent P. 0. Box 98 Brownville, Nebraska 68321 Auburn Public Library
118 - 15th Street Auburn, Nebraska 68305 Mr. J. M. Pilant, Director Licensing & Quality Assurance Nebraska Public Power District P. 0. Box 499 Columbus, Nebraska 68601
Wisconsin Public Service Corporation Kewaunee Nuclear Plant Docket No. 50-305 cc: Mr. Eugene R. Mathews, Vice President Power Supply and Engineering Wisconsin Public Service Corporation Post Office Box 1200
Green Bay, Wisconsin 54305 Steven E. Keane, Esquire Foley and Lardner
777 East Wisconsin Avenue Milwaukee, Wisconsin 53202 Kewaunee Public Library
822 Juneau Street Kewaunee, Wisconsin 54216 Stanley LaCrosse, Chairman Town of Carlton Route 1 Kewaunee, Wisconsin 54216
Arkansas Power & Light Company 50-313 & 368.
Arkansas Nuclear One, 1 & 2 cc w/enclosure(s):
Phillip K. Lyon, Esq. Director, Technical Assessment House, HoIns & Jewell Division
1550 Tower Building Office of Radiation Programs Little Rock, Arkansas 72201 (AW-459)
U. S. Environmental Protection Agency Mr. David C. Trimble Crystal Mall #2 Manager, Licensing Arlington, Virginia 20460
Arkansas Power & Light Company P. 0. Box 551 U. S. Environmental Protecticon Agency Little Rock, Arkansas 72203 Region VI Office ATTN: EIS COORDINATOR
Mr. James P. O'Hanlon 1201 Elm Street General Manager First International Building Arkansas Nuclear One Dallas, Texas 75270
P. 0. Box 608 Russellville, Arkansas 72801 Mr. William Johnson Director, Bureau of Environmental U. S. Nuclear Regulatory Commission Health Services P. 0. Box 2090 4815 West Markham Street Russeliville, Arkansas 72801 Little Rock, Arkansas 72201 Kr. Robert B. Borsum Mr. William Cavanaugh, III
Babcock & Wilcox Vice President, Generation Nuclear Power Generation Division and Construction Suite 420, 7735 Old Georgetown Road Arkansas Power & Light Company Bethesda, Maryland 20014 P.O. Box 551 Little Rock, Arkansas 72203 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber
1747 Pennsylvania Avenue, N.W.
Washington, D.C. 20006 Arkansas Polytechnic College Russellville, Arkansas 72801 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Mr. Paul F. Levy, Director Arkansas Department of Energy
3000 Kavanaugh Little Rock, Arkansas 72205
Virginia Electric and Power Company 2 Docket Nos. 50-280/281 Surry Power Station, Unit Nos. 1 and cc: Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Poiwer Company Post Office Box 26666 Richmond, Virginia 23261 Mr. Michael W. Maupin Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213 Mr. W. L. Stewart, Manager P. 0. Box 315 Surry, Virginia 23883 Swem Library College of William and Mary Williamsburg, Virginia 23185 Donald J. Burke, Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission Post Office Box 959 Williamsburg, Virginia 23185
Wisconsin Electric Power Company Point Beach Nuclear Plant Units 1 and 2 Docket Nos. 50-266/301 cc: Mr. Sol Burstein Executive Vice President Wisconsin Electric Power Company
231 West Michigan Street Milwaukee, Wisconsin 53201 Mr. Bruce Churchill, Esquire Shaw, Pittman, Potts and Trowbridge
1800 M Street, N.W.
Washington, D. C. 20036 Document Department University of Wisconsin Stevens Point Library Stevens Point, Wisconsin 54481 Mr. Glenn A. Reed, Manager Nuclear Operations Wisconsin Electric Power Company Point Beach Nuclear Plant
6610 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Kathleen M. Falk General Counsel Wisconsin's Environmental Decade
302 E. Washington Avenue Madison, Wisconsin 53703
Public Service Electric and Gas Company Docket No. 50-272 Salem 1 cc: Mr. F. P. Librizzi, General Manager Electric Production Production Department Public Service Electric and Gas Company
80 Park Place, Room 7221 Newark, New Jersey 07101 Mark J. Wetterhahn, Esquire Conner, Moore and Corber Suite 1050
1747 Pennsylvania Avenue, NW
Washington, D. C. 20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric and Gas Company
80 Park Place Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection
380 Scotch Road Trenton, New Jersey 08628 Mr. Hank Midura, Manager Salem Nuclear Generating Station Public Service Electric and Gas Company
80 Park Place Newark, New Jersey 07101 Mr. R. L. Mittl, General Manager Licensing and Environment Public Service Electric and Gas Company
80 Park Place Newark, New Jersey 07101 Salem Free Library
112 West Broadway Salem, New Jersey 08079 Leif J. Norrholm, Resident Inspector Salem Nuclear Generating Station U. S. Nuclear Regulatory Commission Drawer I
Hancocks Bridge, New Jersey 08038
Virginia Electric and Power Company North Anna Unit 1 Docket No. 50-338 cc: Mr. J. H. Ferguson Atomic Safety and Licensing Appeal Executive Vice President - Power Board Panel Virginia Electric and Power Company U. S. Nuclear Regulatory Commission Post Office Box 26666 Washington, D. C. 20555 Richmond, Virginia 23261 Richard M. Foster, Esquire
1230 A Pearl Street Denver, Colorado 80203 Michael W. Maupin, Esquire Hunton, Williams, Gay and Gibson P. 0. Box 1535 Richmond, Virginia 23212 Alderman Library Manuscripts Department University of Virginia Charlottesville, Virginia 22901 Mr. Edward Kube Board of Supervisors Louisa County Courthouse P. 0. Box 27 Louisa, Virginia 23093 Ellyn R. Weiss, Esquire Sheldon, Harmon, Roisman and Weiss
1725 I Street, N.W., Suite 506 Washington, D. C. 20006t Commonwealth of Virginia Council on the Environment
903 Ninth Street Office Building Richmond, Virginia 23129 Mr. Michael S. Kidd U. S. Nuclear Regulatory Commission Post Office Box 128 Spotsylvania, Virginia 22553 Mr. W. R. Cartwright, Station Manager P. 0. Box 402 Mineral, Virginia 23117
Portland General Electric Company Docket No. 50-344 Trojan Plant cc: Mr. Charles Goodwin, Jr. Robert M. Hunt, Chairman Assistant Vice President Board of County Comnissioners Portland General Electric Company Columbia County
121 S.W. Salmon Street St. Helens, Oregon 97501 Portland, Oregon 97204 Mr. J. W. Durham, Esquire Vice President and Corporate Counsel Portland General Electric Company
121 S.W. Salmon Street Portland, Oregon 97204 Warren Hastings, Esquire Counsel for Portland General Electric Company
121 S.W. Salmon Street Portland, Oregon 97204 Mr. Jack W. Lentsch, Manager Generation Licensing and Analysis Portland General Electric Company
121 S.W. Salmon Street Portland, Oregon 97204 Columbia County Courthouse Law Library, Circuit Court Room St. Helens, Oregon 97501 Director, Oregon Department of Energy Labor and Industries Building, Room 111 Salem, Oregon 97310
Richard M. Sandvik, Esquire Counsel for Oregon Energy Facility Siting Counsel and Oregon Department of Energy
500 Pacific Building
520 S.W. Yantill Portland, Oregon 97204 Michael Malmros, Resident Inspector U. S. Nuclear Regulatory Commission Trojan Nuclear Plant P. 0. Box 0
Rainier, Oregon 97048 Mr. Donald W. Godard, Supervisor Siting and Regulation Oregon Department of Energy Labor and Industries Building, Room 111 Salem, Oregon 97310
Power Authority of the State of New York Indian Point Unit No. 3 Docket No. 50-286 cc: White Plains Public Library Mr. J. P. Bayne, Resident Manager
100 Martine Avenue Indian Point 3 Nuclear Power Plant White Plains, New York 10601 P. 0. Box 215 Buchanan, New York 10511 Mr. Charles M. Pratt Assistant General Counsel Mr. J. W. Blake, Ph.D., Director Power Authority of the Environmental Programs State of New York Power Authority of the
10 Columbus Circle State of New York New York, New York 10019 10 Columbus Circle New York, New York 10019 Ms. Ellyn Weiss Sheldon, Harmon and Weiss Theodore A. Rebelowski
1725 I Street, N.W., Suite 506 Resident Inspector Washington, D. C. 20006 Indian Point Nuclear Generating U. S. Nuclear Regulatory Commission Dr. Lawrence D. Quarles Post Office Box 38 Apartment 51 Buchanan, New York 10511 Kendal at Longwood Kennett Square, Pennsylvania 19348 Mr. George T. Berry, President and Chief Operating Officer Mr. George M. Wilverding Power Authority of-the State Licensing Supervisor of New York Power Authority of the 10 Columbus Circle State of New York New York, New York 10019
10 Columbus Circle New York, New York 10019 Mr. P. W. Lyon, Senior Vice President - Nuclear Generation Power Authority of the State of New York
10 Columbus Circle New York, New York 10019
Indiana and Michigan Electric Company
50-315/316 D. C. Cook Nuclear Plant, Unit Nos. 1 and 2 Docket Nos.
cc: Mr. John Dolan, Vice President Indiana and Michigan Electric Company Post Office Box 18 Bowling Green Station New York, New York 10004 Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation
2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge
1800 M Street, N.W.
Washington, D. C. 20036 Citizens for a Better Environment
59 East Van Buren Street Chicago, Illinois 60605 Maude Preston Palenske Memorial Library
500 Market Street St. Joseph, Michigan 49085 Mr. D. Shaller, Plant Manager Donald C. Cook Nuclear Plant P. 0. Box 458 Bridgman, Michigan 49106 Mr. Robert Masse Resident Inspector Donald C. Cook Nuclear Plant U. S. Nuclear Regulatory Conmission P. 0. Box 458 Bridgman, Michigan 49106 William J. Scanlon, Esquire
2034 Pauline Boulevard Ann Arbor, Michigan 48103
Northern States Power Company Prairie Island, Unit Nos. 1 and 2 Docket Nos. 50-282/306 cc: Mr. L. 0. Mayer, Manager Nuclear Support Services Northern States Power Company
414 Nicollet Mall - 8th Floor Minneapolis, Minnesota 55401 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge
1800 M Street, N.W.
Washington, D. C. 20036 Ms. Terry Hoffman Executive Director Minnesota Pollution Control Agency
1935 W. County Road B2 Roseville, Minnesota 55113 The Environmental Conservation Library Minneapolis Public Library
300 Nicollet Mall Minneapolis, Minnesota 55401 Mr. F. P. Tierney, Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company Route 2 Welch, Minnesota 55089 Joclyn F. Olson, Esquire Special Assistant Attorney General Minnesota Pollution Control Agency
1935 W. County Road B2 Roseville, Minnesota 55113 Robert L. Nybo, Jr., Chairman Minnesota-Wisconsin Boundary Area Coumission
619 Second Street Hudson, Wisconsin 54016 Clarence D. Fierabend Resident Inspector Prairie Island Nuclear Generating Plant U. S. Nuclear Regulatory Commission P. 0. Box 374 Red Wing, Minnesota 55066
- 'Ir
-.
L
L. Ferguson North Anna Power Station, Unit 2 Docket No. 50-339
- .t t,-:: tive Vice President - Po.er
-. -_;ato ns
- V'rirnia Electric & Pcnier Conpany P. O. Eox 26666 RIc!%r,:nd, Virginia 23261 Clarence T. Kipps, Jr., Esq.
cc: Mr. Anthony Gambaradella 1700 Pennsylvania Avenue, N.>.
Office of the Attorney General I.'ashington, D. C. 20006
11 South 12th Street - Room 308 Richmond, Virginia 23219 Carroll J. Savage, Esq.
1700 Pennsylvania Avenue, N. W.
Richard M4.Foster, Esq. Washington, D. C. 20006
';usick, Williamson, Schwartz Leavenworth & Cope, P. C. lMr. James C. Dunstan P. 0. Box 4519 State Corporation Commission Soulder, Colorado 80306 Comronwealth of Virginia Blandon Building
"Achael W. 1M1aupin, Esq. Richmond, Virginia 23209
17unton, Williams, Gay & Gibson P. 0. Box 1535 Alan S. Rosenthal, Esq.
Aichmond, Virginia 23212 Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Coramission
"rs. June Allen Washington, D. C. 20555
412 Owens Drive
.:jntsville, Alabana 35801
'IMichael C. Farrar, Esq.
"rs. Jai-es Torson Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Com.aission Z'01 Leroy B7801 Washington, D. C. 20555 Socorro, 'New Mexico Dr. John H. Buck Xrs. Margaret Dietrich Atomic Safety and Licensing Appeal Board Route 2, Box 568
22942 U.S. Nuclear Regulatory Comnission Gordonsville, Virginia 20555 Washington, D. C,
w'illiam H. Rodgers, Jr., Esq.
Atomic Safety and Licensing Board Panel Georgetown University Law Center
600 'sew Jersey Avenue, N. W. U.S. Nuclear Regulatory Commission Washington, D. C. 20001 Washington, D. C. 20555 Mir. Iichael S. Kidd Mr. Peter S. Hepp U.S. Nuclear Regulatory Commission Executive Vice President P. 0. Box 128 Sun Shipping & Dry Dock Company Spotslvania, Virginia 22553 P. 0. Box 540
Chester, Pennsylvania 19013 Dr. Paul W. Purdom Department of Civil Engineering
- ¶r. R. B. Briggs Drexel University Associate Director 19104 Philadelphia, Pennsylvania
110 Evans Lane Cak Ridge, Tennessee 37830
Mr. J. H. Ferguson cc: Dr. Lawrence R. Quarles Apartment No. 51 Kendal-at-Longwood Kennett Square, Pennsylvania 19348 Mr. Irwin B. Kroot Citizens Energy Forum P. 0. Box 138.
McLean, Virginia 22101 James B. Dougherty, Esq.
1416 S Street, N.W.
Washington, D. C. 20009 W. R. Cartwright, Stat~ion Manager P. 0.. Box 402 Mineral, Virginia 23117 W. L. Stewart, Manager P. 0. Box 315 Surry, Virginia 23883
z Locxet >0-311 Salem Nuclear Generating Station, Unit No. 2 ir.R. L. Mitt], GenerdlI Manager Licensing and Envirorb;;imnt Engineering and Construction Department Public Service Electric and Gas Company
80 Park Place Newark, New Jersey 07101 J
cc: Richard Fryling, Jr., Esq.
- Assistant General Counsel Public Service Electric 8 Gas Company.
80 Park Place Newark, New Jersey 01100
Mark Wetterhahn, Esq.
Conner, Moore ; Cober
1747 Pennsylvania Avenue, N.W.
Suite 1050
Washington, D.C. 20006 Mr. Leif J. Norrholm U. S. Nuclear Regulatory Commission Region I
Drawer I
Hancocks Bridge, New Jersey 08038
Seauoyah Nuclear Plant, Unit 1 Docket No. 50-327 Mr. H. G. Parris Manager of Paoier Tennessee Valley Authority
500A Chestnut Street Tower II
- Chattanooga, Tennessee 37401 ccs:
Herbert S. Sanger, Jr. Esq.
General Counsel Tennessee Valley Authority
400 Commerce Avenue E 11B 33.
Knoxville, Tennessee 37902 Mr. H. N. Culver
- Tennessee Valley Authority
400 Commerce Avenue, 249A HBB
Knoxville, Tennessee 37902 Mr. Michael Harding Westinghouse Electric Corporation P. 0. Box 355 Pittsburgh, Pennsylvania 15230
Mr. David Lambert Tennessee Valley Authority
400 Chestnut Street Tower II
Chattanooga, Tennessee 37401 Mr. J. F. Cox Tennessee Valley Authority
400 Commerce Avenue, WIOCI31C
Knoxville, Tennessee 37902
'.#. Resident lnspector/Sequoyah NPS
C/o U.S. Nuclear Regulatory Comnission P. 0. Box 699
- Hixson, Tennessee 37343
Docket No. 50-244 R. E. Ginna Nuclear Power Station Mr. Leon D. White, Jr.
cc Director, Technical Assessment Harry H. Voigt, Esquire Division LeBoeuf, Lamb, Leiby & MacRae Office of Radiation Programs
1757 N Street, N. W. (AW-459)
Washington, D. C. 20036 U. S. Environmental Protection Agency Mr. Michael Slade Crystal Mall 12
12 Trailwood Circle Arlington, Virginia 20460
Rochester, New York 14618 U. S. Environmental Priotect ion Rochester Committee for Agency Scientific Information Region II Office Robert E. Lee, Ph.D. ATTN: EIS COORDINATOR
P. 0. Box 5236 River Campus 26 Federal Plaza Station New York, New York 10007 Rochester, New York 14627 Herbert Grossman, Esq., Chairman Jeffrey Cohen Atomic Safety and Licensing Board New York State Energy Office U. S. Nuclear Regulatory Commission Swan Street Building Washington, D. C. 20555 Core 1, Second Floor Empire State Plaza Dr. Richard F. Cole Albany, New York 12223 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Director, Technical Development Programs Washington, D. C. 20555 State of New York Energy Office Agency Building 2 Dr. Emmeth A. Luebke Empire State Plaza Atomic Safety and Licensing Board Albany, New York 12223 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Rochester Public Library
115 South Avenue Mr. Thomas B. Cochran Rochester, New York 14604 Natural Resources Defense Council, Inc.
1725 I Street, N. W.
Supervisor of the Town Suite 600
of Ontario Washington, D. C. 20006
107 Ridge Road West Ontario, New York 14519 LICENSEE:
Mr. Leon D. White, Jr.
Vice President Electric and Steam Production Rochester Gas and Electric Corporation
89 East Avenue Rochester, New York 14649
Docket No. 50-206 San Onofre Nuclear Generating Station, Unit 1 I
Mr. R. Dietch cc Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459)
Rosemead, California 91770 U. S. Environmental-Protection Agency David R. Pigott Crystal Mall 12 SSamuel B. Casey Arlington, Virginia 20460
Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN: EIS COORDINATOR
Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector c/o U. S. NRC
P. 0. Box AA LICENSEE:
Oceanside, California 92054 Mr. R. Dietch
- Mission Viejo Branch Library Vice President
24851 Chrisanta Drive Nuclear Engineering and Operations Mission Viejo, California 92676 Southern California Edison Company
2244 Walnut Grove Avenue Mayor Post Office Box 800
City of San Clemente Rosemead, California 91770
San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section
714 P Street, Room 498 Sacramento, California 95814
Docket No. 50-29 Yankee Rowe Atomic Power Station Mr. Janes A. Kay cc Mr. James E. Tribble, President Yankee Atomic Electric Company
25 Research Drive LICENSEE:
Westborough, Massachusetts 01581 Mr. James A. Kay Greenfield Community College Senior Engineer-Licensing
1 College Drive Yankee Atomic Electric Company Greenfield, Massachusetts 01301 25 Research Drive Westborough, Massachusetts 01581 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council
14th Floor One Ashburton Place Boston, Massachusetts 02108 Director, Technical Assessme nt Division Office of Radiation Programs (AW-459)
U. S. Environmental Protecti on Agency Crystal Mall 12 Arlington, Virginia 20460
U. S. Environmental Pr otection Agency Region I Office ATTN: EIS COORDINATOR
JFK Federal Building Boston, Massachusetts 02203
Ft. St. Vrain C. K. Millen 50-267 HTGR
C. K. Millen Senior Vice President Public Service Company of Colorado P. 0. Box 840
Denver, Colorado 80201 James B. Graham, Manager Licensing and Regulation East Coast Office General Atomic Company
2021 K Street, N. W.
Suite 709 Washington, 0. C. 20006 Mr. J. K. Fuller, Vice President Public Service Company of Colorado P. 0. Box 840
Denver, Colorado 80201 Mr. W. Dickerson NRC Resident Inspector
16805 Weld County Road 19 1/2 Platteville, Colorado 80651 Director, Division of Planning Department of Local Affairs
615 Columbine Building
1845 Sherman Street Denver, Colorado 80203 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative, Radiation Programs Environmental Protection Agency
1860 Lincoln Street Denver, Colorado 80203 Mr. Don Warembourg Nuclear Production Manager Public Service Company of Colorado
16805 Weld County Road 19-1/2 Platteville, Colorado 80651
Docket No. 50-255 Palisades Plant Mr. David P. Hoffman cc U. S. Environmental Protection M. I. Miller, Esquire Agency Ishar:, Lincoln & Beale Federal Activities Branch Suite 4200 Region V Office One First National Plaza ATTN: EIS COORDINATOR
Chicago, Illinois 60670 230 South Dearborn Street Chicago, Illinois 60604 Mr. Paul A. Perry, Secretary Consumers Power Conpany Charles Bechhoefer, Esq., Chairman
212 West Michigan Avenue Atomic Safety and Licensing Board Jackson, Michigan 49201 Panel U. S. Nuclear Regulatory Commission Judd L. Bacon, Esquire Washington, D. C. 20555 Consumers Power Conmany
212 West Michigan Avenue Dr. George C. Anderson Jackson, Michigan 49201 Department of Oceanography Myron M. Cherry, Esquire University of Washington Seattle, Washington 98195 Suite 4501 One 'BM Plaza Dr. M. Stanley Livingston Chicago, Illinois 60611 1005 Calle Largo Santa Fe, New Mexico 87501 Ms. Mary P. Sinclair Great Lakes Energy Alliance Resident Inspector
5711 Summerset Drive c/o U. S. NRC
Midland, Michigan 48640 P. 0. Box 87 South Haven, Michigan 49090
Kala-mazoo Public Library
315 South Rose Street Palisades Plant Kalanazoo, Michigan 49006 ATTN: Mr. J. G. Lewis Plant Manager Township Supervisor Covert, Michigan 49043 Covert Township Route 1, Box 10 William J. Scanlon, Esquire Van Buren County, Michigan 49043 2034 Pauline Boulevard Ann Arbor, Michigan 48103 Office of the Governor (2)
Room 1 - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment LICENSEE:
Division Office of Radiation Programs Mr. David P. Hoffman (AW-459) Nuclear Licensing Administrator U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Crystal Mall 12 Jackson, Michigan 49201 Arlington, Virginia 20460
Docket No. 50-409 La Crosse Boiling Water Reactor i Mr. Frank Linder cc Fritz Schubert, Esquire Director, Technical Assessment Staff Attorney Division Dairyland Power Cooperative Office of Radiation Programs
2615 East Avenue South (AW-459)
La Crosse, Wisconsin 54601 U. S. Environmental Protection Agency O. S. Heistand, Jr., Esquire Crystal Mall #2 Morgan, Lewis & Bockius Arlington, Virginia 20460
1800 M Street, N. W.
Washington, D. C. 20036 U. S. Environmental Protection Agency Mr. R. E. Shimshak Federal Activities Branch La Crosse Boiling Water Reactor Region V Office Dairyland Power Cooperative ATTN: EIS COORDINATOR
P. 0. Box 135 230 South Dearborn Street Genoa, Wisconsin 54632 Chicago, Illinois 60604 Coulee Region Energy Coalition Charles Bechhoefer, Esq., Chairman ATTN: George R. Nygaard Atomic Safety and Licensing Board P. 0. Box 1583 U. S. Nuclear Regulatory Commission La Crosse, Wisconsin 54601 Washington, D. C. 20555 La Crosse Public Library Dr. George C. Anderson
800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Seattle, Washington 98195 Mrs. Ellen Sabelko Society Against Nuclear Energy Mr. Ralph S. Decker
929 Cameron Trail Route 4, Box 190D
Eau Claire, Wisconsin 54701 Cambridge, Maryland 21613 Town Chairman Dr. Lawrence R. Quarles Town of Genoa Kendal at Longwood, Apt. 51 Route 1 Kenneth Square, Pennsylvania 19348 Genoa, Wisconsin 54632 Chairman, Public Service Comnission Thomas S. Moore, Esq.
of Wisconsin Atomic Safety and Licensing Appeal Board Hill Farms State Office Building U. S. Nuclear Regulatory Comnission Madison, Wisconsin 53702 Washington, D. C. 20555 Alan S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Appeal Board LICENSEE:
U. S. Nuclear Regulatory Cormnission Washington, 0. C. 20555 Mr. Frank Linder General Manager Dairyland Power Cooperative
2615 East Avenue South La Crosse, Wisconsin 54601
Docket No. 50-219 Oyster Creek Nuclear Generating Station Mr. I. R. Finfrock, Jr.
cc Gene Fisher G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge Bureau Chief
1800 M Street, N. W. Bureau of Radiation Protection Washington, D. C. 20036 380 Scotts Road Trenton, New Jersey 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Mark L. First Licensing Manager Deputy Attorney General
260 Cherry Hill Road State of New Jersey Parsippany, New Jersey 07054 Department of Law and Public Safety Environmental Protection Section Anthony Z. Roisman 36 West State Street Natural Resources Defense Council Trenton, New Jersey 08625
917 15th Street, N. W.
Washington, D. C. 20006 Joseph T. Carroll, Jr.
Plant Superintendent Oyster Creek Nuclear Generating Steven P. Russo, Esquire Station
248 Washington Street P. 0. Box 388 P. 0. Box 1060 Forked River, New Jersey 08731 Toms River, New Jersey 08753 Joseph W. Ferraro, Jr., Esquire Director, Technical Assessment Deputy Attorney General Division State of New Jersey Office of Radiation Programs Department of Law and Public Safety (AW-459)
1100 Raymond Boulevard U. S. Environmental Protection Newark, New Jersey 07012 Agency Crystal Mall 12 Ocean County Library Arlington, Virginia 20460
Brick Township Branch
401 Chambers Bridge Road U. S. Environmental PriDtection Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS COORDINATOR
Lacey Township 26 Federal Plaza P. 0. Box 475 New York, New York 101 007 Forked River, New Jersey 08731 Commissioner LICENSEE:
Department of Public Utilities State of New Jersey Mr. I. R. Finfrock, Jr.
101 Connerce Street Vice President - Generation Newark, New Jersey 07102 Jersey Central Power & Light Company Madison Avenue Punch Bowl Road Morristown, New Jersey 07960
Docket No. 50-245 Millstone Nuclear Power Station, Unit I
Mr. W. G. Counsil cc William H. Cuddy, Esquire Connecticut Energy Agency Day, Berry & Howard ATTN: Assistant Director Counselors at Law Research and Policy One Constitution Plaza Development Hartford, Connecticut 06103 Department of Planning and Energy Policy Anthony Z. Roisman 20 Grand Street Natural Resources Defense Council Hartford, Connecticut 06106
917 15th Street, N. W.
Washington, D. C. 20005 Director, Technical Assessment Division Northeast Nuclear Energy Company Office of Radiation Programs ATTN: Superintendent (AW-459)
Millstone Plant U. S. Environmental Protection P. 0. Box 128 Agency Waterford, Connecticut 06385 Crystal Mall #2 Arlington, Virginia 20460
Mr. James R. Himmelwright Northeast Utilities Service Company U. S. Environmental Protection P. 0. Box 270 Agency Hartford, Connecticut 06101 Region I Office ATTN: EIS COORDINATOR
Resident Inspector JFK Federal Building c/o U. S. NRC Boston, Massachusetts 02203 P. 0. Box Drawer KK
Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 LICENSEE:
Waterford, Connecticut 06385 Mr. W. G. Counsil, Vice President First Selectman of the Town Nuclear Engineering and Operations of Waterford Northeast Nuclear Energy Company Hall of Records P. 0. Box 270
200 Boston Post Road Hartford, Connecticut 06101 Waterford, Connecticut 06385
Docket No. 50-213 Haddam Neck Plant Mr. W. G. Counsil cc Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region I Office Hartford, Connecticut 06103 ATTN: EIS COORDINATOR
JFK Federal Building Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RFD #1 Post Office Box 127E
East Hampton, Connecticut 06424 Mr. James R. Himmelwright Northeast Utilities Service Company LICENSEE:
P. 0. Box 270
Hartford, Connecticut 06101 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Russell Library Connecticut Yankee Atomic Power Company
119 Broad Street Post Office Box 270
Middletown, Connecticut 06457 Hartford, Connecticut 06101 Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN: Assistant Director Research and Policy Development Department of Planning and Energy Policy
20 Grand Street Hartford, Connecticut 06106 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
Docket No. 50-155 Big Rock Point Mr. David P. Hoffman cc Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Company Agency
212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN: EIS COORDINATOR
Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604
212 West Michigan Avenue Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C. 20555
1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C. 20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C. 20555
505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Sheldon, Harmon and Weiss U. S. Nuclear Regulatory Commission
1725 I Street, N. W. Washington, D. C. 20555 Suite 506 Washington, D. C. 20006 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720
Maple City, Michigan 49664 Christa-Maria d0
Charlevoix Public Library Route 2, Box 108C
107 Clinton Street Charlevoix, Michigan 49720
Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720
LICENSEE:
Office of the Governor (2)
Room 1 - Capitol Building Mr. David P. Hoffman Lansing, Michigan 48913 Nuclear Licensing Administrator Consumers Power Company Director, Technical Assessment 212 West Michigan Avenue Division Jackson, Michigan 49201 Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
Docket No. 50-10
Dresden Nuclear Power Station, Unit No. 1 Mr. D. Louis Peoples cc Director, Technical Assessment Isham, Lincoln & Beale Counselors at Law Division Office of Radiation Programs One First National Plaza, 42nd Floor Chicago, Illinois 60603 (AW-459)
U. S. Environmental Protection Mr. B. B. Stephenson Agency Plant Superintendent Crystal Mall #2 Dresden Nuclear Power Station Arlington, Virginia 20460
Rural Route #1 Morris, Illinois 60450 U. S. Environmental Protection Agency U. S. Nuclear Regulatory Commission Federal Activities Branch Resident Inspectors Office Region V Office Dresden Station ATTN: EIS COORDINATOR
RR #1 230 South Dearborn Street Morris, Illinois 60450 Chicago, Illinois 60604 Susan N. Sekuler Assistant Attorney General Environmental Control Division
188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Morris Public Library LICENSEE:
604 Liberty Street Morris, Illinois 60451 Mr. D. Louis Peoples Director of Nuclear Licensing Chairman Commonwealth Edison Company Board of Supervisors of Post Office Box 767 Grunndy County Chicago, Illinois 60690
Grundy County Courthouse Morris, Illinois 60450
Department of Public Health ATTN: Chief, Division of Nuclear Safety
535 West Jefferson Springfield, Illinois 62761
Docket No. 50-237 Dresden Nuclear Power Station, Unit 2 Mr. D. Louis Peoples cc Isham, Lincoln & Beale Department of Public Health Counselors at Law ATTN: Chief, Division of One First National Plaza, 42nd Floor Nuclear Safety Chicago, Illinois 60603 535 West Jefferson Springfield, Illinois 62761 Mr. B. B. Stephenson Plant Superintendent Director, Technical Assessment Dresden Nuclear Power Station Division Rural Route #1 Office of Radiation Programs Morris, Illinois 60450 (AW-459)
U. S. Environmental Protection Anthony Z. Roisman Agency Natural Resources Defense Council Crystal Mall 12
917 15th Street, N. W. Arlington, Virginia 20460
Washington, D. C. 20005 U. S. Environmental Protection U. S. Nuclear Regulatory Commission Agency Resident Inspectors Office Federal Activities Branch Dresden Station Region V Office RR #1 ATTN: EIS COORDINATOR
Morris, Illinois 60450 230 South Dearborn Street Chicago, Illinois 60604 Susan N. Sekuler Assistant Attorney General Environmental Control Division
188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 LICENSEE:
Morris Public Library Mr. D. Louis Peoples
604 Liberty Street Director of Nuclear Licensing Morris, Illinois 60451 ' Commonwealth Edison Company Post Office Box 767 Chairman Chicago, Illinois 60690
Board of Supervisors of Gruncb County Grundy County Courthouse Morris, Illinois 60450
I -3- Metopolitan Edison Company Mr. R. J. Toole Manager, TMI-1 Governor's Office of State Planning Metropolitan Edison Company Ond Development P. 0. Box 480 ATTN: Coordinator, Pennsylvania Middletown, PA 17057 State Clearinghouse P. 0. Box 1323 Mr. W. E. Potts Harrisburg, Pennsylvania 17120
Radiological Controls Manager, ThY-i Metropolitan Edison Company P. 0. Box 480
Middletown, PA 17057 Mr. I. R. Finfrock, Jr.
Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07950
J. B. Lieberman, Esq.
Berlock, Israel, Lieberman
26 Broadway New York, NY 10004 Mr. J. J. Colitz Plant Engineering Manager, TMI-1 Metropolitan Edison Company P. 0. Box 480
Middletown, Pennsylvania 17057 York College of Pennsylvania Country Club Road York, Pennsylvania 17405 Mr. R. C. Arnold Senior Vice President Metropolitan Edison Company
100 Interpace Parkway Parsippany, New Jersey 07054 Mr. G. K. Hovey Director, TMI-2 Metropolitan Edison Company P. 0. Box 480
Middletown, PA 17057 fir. B. Elam Manager, Plant Engineering Metropolitan Edison Company P. 0. Box 480
Middletown, PA 17057 Mr. Richard Roberts The Patriot
812 Market Street Harrisburg, PA 17105
50-289/320
Three Mile Island 1 & 2 -' - Dr. Walter H. Jordan Metiropolitan Edison Company 881 W. Outer Drive Oak Ridge, Tennessee 37830
cc w/er.clasu-1(s): Dr. Linda W. Little Mr. Marvin I. Lewis 5000 Hermitage Drive
6504 Bradford Terrace Raleigh, North Carolina 27612 Pphiladelphias Pennsylvania 19149
- Holly S. rack Walter W. Cohen, Cons 'mer Advocate Anti-Nuclear Group Representing Department of Justice York Strawberry Square, 14th Floor 245 W. Philadelphia Street Harrisburg, Pennsylvania 17127 York, Pennsylvania 17404 Robert L. Knupp, Esq.
Assistant Solicitor John Levin, Esq.
Knupp and Andrews Pennsylvania Public Utilities Comm.
P.O. Box P Box 3265
407 N. Front Street Harrisburg, Pennsylvania 17120
Harrisburg, Pennsylvania 17108 Jordan D. Cunningham, Esq.
John E. Minnich, Chairman Fox, Farr and Cunningham Dauphin Co. Board of Commissioners 2320 North 2nd Street Dauphin County Courthouse Harrisburg, Pennsylvania 17110
Front and Market Sts.
Harrisburg, Pennsylvania .17101 Theodore A. Adler, Esq.
WIDOFF REAGER SELKOWITZ & ADLER
- Atomic Safety and Licensing Appeal Board Post Office Box 1547 U.S. Nuclear Regulatory Commission Harrisburg. Pennsylvania 17105 Washington, D. C. 20555 Ms. Marjorie M. Aamodt R.D. #5
- Atomic Safety and Licensing Board Panel Coatesville, Pennsylvania 19320
U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Ms. Karen Sheldon Sheldon, Harmon, Roisman & Weiss
- Docketing and Service Section 1725 1 Street, N. W.
U.S. Nuclear Regulatory Commission Suite 506 Washington, D. C. 20555 Washington, D. C; 20006 Robert Q. Pollard Earl B. Hoffman Chesapeak Energy Alliance Dauphin County Commissioner
'609 Montpelier Street Dauphin County Courthouse Baltimore, Maryland 21218 Front and Market Streets Harrisburg, Pennsylvania 17101 Chauncey Kepford Judith H. Johnsrud Ellyn Weiss, Esq.
Sheldon Harmon Roisman & Weiss Environmental Coalition on Nuclear Power 1725 1 Itreet, I.w.
433 Orlando Avenue Suite 506 State College, Pennsylvania 16801 Washington, D.C. 20006 Ms. Frieda Berryhill, Chairman Mr. Steven C. Sholly Coalition for Nuclear Power Plant 304 South Market Street Postponement Mechanicsburg, Pennsylvania 17055
2610 Grendon Drive Wilmington, Delaware 19808 Mr. Thomas Gerusky Bureau of Radiation Protection Mrs. Rhoda D. Carr Department of Environmental Resources
1402 Marene Drive P.O. Box 2063 Harrisburg, Pennsylvania 17109 Harrisburg, Pennsylvania 17120
-it Metropolitan Edison Cinpany pAr"" v.. Cartaro E4q.
05 Executive House P. O. Box 2357 Mr. 6. P. Miller asrrisburg, Pennsylvania 17120
Mr. R. F. Wilson Mr. J. J. Barton Honorable Mark Cohen Metropolitan Edidon Company S12 E-3 Main Capital Buildia P. 0. Box 480 Narrisburg, Pennsylvania 17120
Middletown, Pennsylvania 1057 G. F. Trowbridge, Esquire Dauphin County Office Emergency Shaw, P1ttman, Potts & Trowbridge Preparedness
1800 M Street, N.W. Court House, Room 7 Washington, D. C. 20036 Front & Market Streets Harrisburg, Pennsylvania 17101 GPU Service Corporation Richard W. Heward, Project Manager Mr. E. G. Wallace Department of Environmental Resources Licensing Manager ATTN: Director, Office of Radiological
100 Interpace Parkway Health Parsippany, New Jersey 07054 Post Office Box 2063 Harrisburg, Pennsylvania 17105 Pennsylvania Electric Company Mr. R. W. Conrad Director, Technical Assessment Vice President, Generation Division
1001 Broad Street Office of Radiation Programs Johnstown, Pennsylvania 15907 (AW-459)
U. S. Environmental Protection Agency Miss Mary V. Southard, Chairman Crystal Mall #2 Citizens for a Safe Environment Arlington, Virginia 20460
Post Office Box 405 Harrisburg, Pennsylvania 17108 Mr. Robert B. Borsum Babcock & Wilcox Government Publications Section Nuclear Power Generation Division State of Library of Pennsylvania Suite 420, 7735 Old Georgetown Road Box 1601 (Education Building) Bethesda, Maryland 20014 Harrisburg, Pennsylvania 17126 h Ivan W. Smith, Esq.
Yr. David D. Maxwell, Chairman Atomic Safety & Licensing Board Panel Board of Supervisors U.S. Nuclear Regulatory Conmnlssion Londonderry Township Washington3 D. C. 20555 RFD#l - Geyers Church Road Middletown, Pennsylvania 17057 Ms. Kathy McCaughin Three Mile Island Alert, Inc.
U. S. Environmental Protection Agency 23 South 21st Street Region III Office Harrisburg, Pennsylvania 17104 ATTN: EIS COORDINATOR
Curtis Building (Sixth Floor) Mr. L. ',. Harding
6th and Walnut Streets Supervisor of Licensing Philadelphia, Pennsylvania 19106 Metropolitan Edison Company Mr. J. G. Herbein P. 0. Box 480
Vice President Middletown, Pennsylvania 17057 Metropolitan Edison Compary P. 0. Box 480
Middletown, Pennsylvania 17057 Ms. Jane Lee Rt.D. 3; Box 3521 Etters, Pennsylvania 173 19
Rancho Seco Sacramento Municipal Utility District cc w/enclosure(s): Christopher Ellison, Esq.
Dian Grueuich, Eso Commission David S. Kaplan, Secretary and California Enerry General Counsel 1111 Howe Avenue
6201 S Street Sacramento, California 95825
"P.0. Box 15830
Sacramento, California 95813 Ms. Eleanor Schwartz California State Office Sacramento County 600 Pennsylvania Avenue, S.E., Rm. 201 Board of Supervisors Washington, D.C. 20003
827 7th Street, Room 424 Sacramento, California 95814 Docketing and Service Section Office of the Secretary Business and Municipal Department U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Sacramento City-County Library
828 I Street Sacramento, California 95814 Resident Inspector P. 0. Box 48 Director, Technical Assessment Fair Oaks, California 95628 Division Office of Radiation Programs Dr. Richard F. Cole (AW-459) Atomic Safety and Licensing Board U. S. Environmental Protection Agency Panel Crystal Mall #2 U. S. Nuclear Regulatory Commission Arlington, Virginia 20460 Washington, D.C. 20555 U. S. Environmental Protection Agency Mr. Frederick J. Shon Region IX Office Atomic Safety and Licensing Board ATtN: EIS COORDINATOR Panel
215 Fremont Street U. S. Nuclear Regulatory Commission Washington, D.C. 20555 San Francisco, California 94111 Mr. Robert B. Borsum Elizabeth S. Bowers, Esq.
Babcock & Wilcox Chairman, Atomic Safety and Nuclear Power Generation Division Licensing Board Panel Suite 420, 7735 Old Georgetown Road U. S. Nuclear Regulatory Commission
.ethesda, Maryland 20014 Washington, DC 20555 Thomas Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge
1800 M Street,, W
Aashinqton, D. C.--20036 Mr. Michael R. Eaton Herbert H. Brown, Esq. Energy Issues Coordinator Lawrence Coe Lanpher, Esq. Sierra Club Legislative Office Hill, Christopher and Phillips, P. C. 1107 9th St., Room 1020
1900 M St., NW
Sacramento, CA 95814 Washington, D. C. 20036 Helen Hubbard P. O. Box 63
.Sunol, California 94586
Sacramento Municipal Utility -2- 50-312 District Rancho Seco cc w/enclosure(s)-
Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D.C. 20555 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section
714 P Street, Room 498 Sacramento, California Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District
6201 S Street P. 0. Box 15830
Sacramento, CA 95813
50-346 Toledo Edison Company Davis-BesSe 1 cc w/enclosure(s):
. S. nuclear Regulatory fomeission Mr. Donald H. Hauser, Esq. esident Inspector's Office The Cleveland Electric 503 N. State Route 2 Illuminating Company Oak Harbor, Ohio 43449 P. 0. Box 5000
Cleveland, Ohio 44101 Director, Technical Assessment Division Gerald Charnoff, Esq. Office of Radiation Programs Shaw, Pittman, Potts (AW-459)
and Trowbridge U. S. Environmental Protection Agency
1800 M Street, N.W. Crystal Mall 12 Washington, D.C. 20036 Arlington, Virginia 20460
Leslie Henry, Esq. U. S. Environmental Protection Agency Fuller, Seney, Henry and Hodge Federal Activities Branch
300 Madison Avenue Region V Office Toledo, Ohio 43604 ATTN: EIS COORDINATOR
230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois 60604 Babcock'& Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Ohio Department of Health ATTN: Director of Health Ida Rupp Public Library 450 East Town Street
310 Madison Street Columbus, Ohio 43216 Port ClintonOhio 43452 President, Board of County Mr. Lowell E. Roe Commissioners of Ottawa County Vice President, Facilities Port Clinton, Ohio 43452 Development Toledo Edison Company Attorney General Edison Plaza Department of Attorney General 300 Madison Avenue
30 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43215 Harold Kahn, Staff Scientist Power Siting Commission
361 East Broad Street Columbus, Ohio 43216 Mr, Rick Jagger Industrial Commission State of Ohio
2323 West 5th Avenue Columbus, Ohio 43216 Mir, Ted Myers Licensing Engineer Toledo Edison Company Edison Plaza
300 Madison Avenue Toledo, Ohio 43652
50-269/270 & 287 Oconee 1, 2& 3 Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Mr. Robert B. Borsum Duke Power Company Babcock & Wilcox P. O. Box 2178 Nuclear Power Generation Division
422 South Church Street Suite 420, 7735 Old Georgetown Road Charlotte, North CaroTina 28242 Bethesda, Maryland 20014 Oconee Public Library Manager, LIS
201 South Spring Street NUS Corporation Walhalla, South Carolina 29691 2536 Countryside Boulevard Clearwater, Florida 33515 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Office of Intergovernmental Relations Director, Technical Assessment 116 West Jones Street Division Raleigh, North Carolina 27603 Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
U. S. Environmental Protection Agency Region IV Office ATTN: EIS COORDINATOR
345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U. S. Nuclear Regulatory Commission P. 0. Box 7 Seneca, South Carolina 29678 Mr. William 0. Parker, Jr.
Vice President - Steam Production Duke Power Company P. O. Box 2178
422 South Church Street Charlotte, North Carolina 28242
50-335 Florida Power & Light Company St. Lucie 1 cc w/enclosure(s): r. Jack Shreve Robert Lowenstein, Esquire Office of the Public Counsel Lowenstein, Newman, Reis & Axelrad %Dom 4, Holland Bldg.
1025 Connecticut Avenue, N.W. Tallahassee, Florida 32304 Washington, D.C. 20036 Worman A. Coll, Esquire McCarthy, Steel, Hector & Davis
14th Floor, First National Bank Building Bureau of Intergovernmental Relations Miami, Florida 33131 660 Apalachee Parkway Indian River Junior College Library Tallahassee, Florida 32304
3209 Virginia Avenue Fort Pierce, Florida 33450 Dr. Robert E. Uhrig Vice President Florida Power & Light Company Administrator Advanced Systems & Technology Department of Environmental Regulation P. 0. Box 529100
Power Plant Siting Section Miami, Florida 33152 State of Florida
2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator St. Lucie County
2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450
Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. S. Environmental PrQtection Agency Crystal Mall #2 Arlington, Virginia 20460
U.S. Environmental Protection Agency Region IV Office ATTN: EIS COORDINATOR
345 Courtland Street, N.E.
Atlanta, Georgia 30308
Florida Power Corporation 50-302 Crystal River 3 cc w/enclosure(s):
Mr. S. A. Brandimore Mr. Robe B. Borsum Vice President and General Counsel Babcock & Wilcox P. 0. Box 14042 Nuclear Power Generation Division St. Petersburg, Florida 33733 Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Mr. Wilbur Langely, Chairman Board of County Commissioners Citrus County Iverness, Florida 36250 Bureau of Intergovernmental Relations U. S. Environmental Protection Agency 660 Apalachee Parkway Region IV Office Tallahassee, Florida 32304 ATTN: EIS COORDINATOR
345 Courtland Street, N.E. Mr. J. A. Hancock Atlanta, Georgia 30308 Director, Nuclear Operations Florida Power Corporation Director. Technical Assessment P. 0. Box 14042, Mail Stop C-4 Division St. Petersburg, Florida 33733 Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
Crystal River Public Library Crystal River, Florida 32629 Mr. J, Shreve The Publ ic Counsel Room 4 Holland Bldg.
Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida
2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Dr. William R. Stratton Los Alamos Scientific Lab Box 503 Los Alamos, New Mexico 87544
Yankee Atomic Electric Company .. 50-309 Maine Yankee cc w/enclosure(s): firs. L. Patricia Doyle, President E. W. Thurlow, President SAFE POWER FOR MAINE
Maine Yankee Atomic Power Company Post Office Box 774 Edison Drive Camden, Maine 04843 Augusta, Maine 04336 First Selectman of Wiscasset Mr. Donald E. Vandenburgh Municipal Building Vice President - Engineering U. S. Route I
Yankee Atomic Electric Company Wiscasset, Maine 04578
20 Turnpike Road Westboro, Massachusetts 01581 Director, Technical Assessment Division John A. Ritsher, Esquire Office of Radiation Programs Ropes & Gray (AW-459)
225 Franklin Street U. S. Environmental Protection Agenc y Boston, Massachusetts 02110 Crystal Mall #2 Arlington, Virginia 20460
Mr. John M.- R. Paterson Assistant Attorney General U. S. Environmental Protectfion Agency State of Maine Region I Office Augusta, Maine 04330 ATTN: EIS COORDINATOR
JFK Federal Building Mr. Nicholas Barth Boston, Massachusetts 02203 Executive Director Sheepscot Valley Conservation Stanley R. Tupper, Esq.
Association, Inc. Tupper and Bradley P. 0. Box 125 102 Townsend Avenue Alan, Maine 04535 Boothbay Harbor, Maine 04538 Wiscassett Public Library Association David Santee Miller, Esq.
High Street 213 Morgan Street, N. W.
Wiscasset, Maine 04578 Washington. D. C. 20001 Mr. Robert R. Radcliffe Mr. Robert H. Groce Office of Energy Resources Senior Engineer - Licensing
55 Capitol Street Maine Yankee Atomic Power Company Augusta, Maine 04330 25 Research Drive Westboro, Massachusetts 01581 Robert M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Laboratory University of California Bodega Bay, California 94923 Mr. Gustave A. Linenberqer State Planning Officer Atomic Safety and Licensing Board Executive Department U. S. Nuclear Regulatory Commission State of Maine Washington, D. C. 20555 189 State Street Augusta, Maine 04330
7 Northeast Nuclear Energy Company 50-336 Millstone 2 cc w/enclosure(s):
William H. Cuddy, Esquire Day, Berry & Howard Mr. John T. Shedlosky Counselors at Law U. S. Nuclear Regulatory Commission One Constitution Plaza P. 0. Drawer KK
Hartford, Connecticut 06103 Niantic, CT 06357 Anthony Z. Roisman Natural Resources Defense Council
917 15th Street, N.W.
Washington, D.C. 20005 Connecticut Energy Agency Mr. Lawrence Bettencourt. First Selectman *ATTN: Assistant Director, Research Town of Waterford and Policy Development Hall of Records - 200 Boston Post Road Department of Planning and Energy Waterford, Connecticut 06385 Policy
20 Grand Street Northeast Nuclear Energy Company Hartford, Connecticut 06106 ATTN: Superintendent Millstone Plant Mr. W. G. Counsil, Vice President Post Office Box 128 Nuclear Engineering & Operations Waterford, Connecticut 06385 Northeast Nuclear Energy Company P. 0. Box 270.
Director, Technical Assessment Hartford, Connecticut 06101 Division Office of Radiation Programs (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
U. S. Environmental Protection Agency Region I Office ATTN: EIS COORDINATOR
John F. Kennedy Federal Building Boston, Massachusetts 02203 Waterford Public Library -
Rope Ferry Road, Route 156 Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. James R. Himmelwright Nuclear Engineering and Operations P. 0. Box 270
Hartford, Connecticut 06101
J-
4De ).ekttooi t*'hze, ALL POWER REACTOR LICENSEES
' 1
5,q 3 Docket No. 50-348 Docket No. 50-3 Indian Point Unit 1 a/-JRya Farley Unit 1 Docket No. 50-313 Docket No. 50-247 Arkansas Unit 1 Indian Point Unit 2 Docket 50-286 Docket No. 50-368 Indian Point Unit 3 Arkansas Unit 2 Docket No. 50-155 Docket No. 50-317 Big Rock Point Calvert Cliffs Unit 1 Docket No. 50-318 Docket No. 50-255 Palisades Calvert Cliffs Unit 2 Docket No. 50-409 Docket No. 50-293 Lacrosse Pilgrim Unit 1 Docket No. 50-325 Docket No. 50-269 Oconee Unit I
Brunswick Unit 1 Docket No. 50-270
Docket No. 50-324 Oconee Unit 2 Brunswick Unit 2 Docket No. 50-287 Docket No. 50-261 Oconee Unit 3 H. B. Robinson Unit 2 Docket No. 50-334 Docket NoV. 50-10 Beaver Valley Unit 1 Dresden Unit 1 Docket No. 50-302 Docket No. 50-237 . I,
Crystal River 3 C
Dresden Unit 2 Docket No. 50-335 Docket No. 50-249 St. Lucie Unit I
Dresden Unit 3 Docket No. 50-250
Docket No. 50-254 Turkey Point Unit 3 Quad-Cities Unit 1 Docket No. 50-251 Docket No. 50-265 Turkey Point Unit 4 Quad-Cities Unit 2 Docket No. 50-321 Docket No. 50-295 Edwin I. Hatch Unit 1 Zion Unit 1 Docket No. 50-366 Docket No. 50-304 Edwin I. Hatch Unit 2 Zion Unit 2 Docket No. 50-315 Docket No. 50-213 D. C. Cook Unit 1 Connecticut Yankee (Haddam Neck)
N 11I Big! - `_ _
ML a
- 40
- 2- .
I
Docket No. 50-316 Docket No. 50-344 D. C. Cook Unit 2 Trojan Docket No. 50-331 Docket No. 50-333 Duane Arnold FitzPatrick Docket No. 50-219 Docket No. 50-267 Oyster Creek Unit 1 Ft. St. Vrain Docket No. 50-309 Docket No. 50-272 Maine Yankee Salem Unit 1 Docket No. 50-289 Docket No. 50-244 Three Mile Island Unit 1 .R.E. Ginna 1 Docket No. 50-320 Docket No. 50-312 Three Mile Island Unit 2 Rancho Seco Docket No. 50-298 Docket No. 50-206 Cooper Station San Onofre 1 Docket No. 50-220 Docket No. 50-259 Nine Mile Point Unit 1 Browns Ferry Unit 1 Docket No. 50-245 Docket No. 50-260
Millstone Unit 1 Browns Ferry Unit 2 Docket No. 50-336 Docket No. 50-296 Millstone Unit 2 Browns Ferry Unit 3 Docket No. 50-263 Docket No. 50-346 Monticello Davis-Besse 1 Docket No. 50-282 Docket No. 50-271 Prairie Island Unit 1 Vermont Yankee Docket No. 50-306 Docket No. 50-338 Prairie Island Unit 2 North Anna 1 Docket No. 50-285 Docket No. 50-280
Ft. Calhoun Surry Unit 1 Docket No. 50-133 Docket No. 50-281 Humboldt Bay Surry Unit 2 Docket No. 50-277 Docket No. 50-266 Peach Bottom 2 Point Beach Unit 1 Docket No. 50-278 Docket No. 50-301 Peach Bottom 3 Point Beach Unit 2
a Docket No. 50-305 Kewaunee Docket No. 50-29 Yankee-Rowe Docket No. 50-267 Ft. St. Vrain Docket No. 50-311 Salem 2 Docket No. 50-327 Sequoyah 1 Docket No. 50-339 North Anna 2
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