ML19309E916
| ML19309E916 | |
| Person / Time | |
|---|---|
| Site: | 05000514, 05000515, 05000471, Allens Creek, Perkins, Skagit, Black Fox File:Houston Lighting and Power Company icon.png |
| Issue date: | 04/07/1980 |
| From: | Thomas C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004240557 | |
| Download: ML19309E916 (47) | |
Text
NBc PDe
- a'*
o UNITED STATES
~g' 8
NUCLEAR REGULATORY COMMISSION o
{
WA5HINGTON, D. C. 20666
%,*****/
APR '
1980 Docket Nos.: 50-522/523 50-466, 50-488/89/90 50-471, 50-514/515 50-556/557
SUMMARY
OF APRIL 2, 1980 MEETING WITH fiTER APPLICANTS GROUP On April 2, 1980, we met with representatives of the Near-Term Construction Permit (NTCP) Applicants Group (Applicants Group) in Bethesda, Maryland to discuss the progress made to date in establishing proposed requirements stemming from the TMI-2 accident to be addressed by NTCP applicants. We had met previously with the Applicants Group on March 19, 1980 and with the Applicants Working Group on March 28, 1980 on this matter. An attendance list is provided in Enclosure 1.
The Applicants Group expressed the need for additional clarification of the language of our proposed requirement categories, especially the category that would require that the applicants implement modifications indicated by the results of studies that might not haVe been completed prior to the issuance of a construction permit. We noted the Applicants Group's concerns and agreed to reconsider the language of our proposed requirements in light thereof.
The Applicants Group enumerated a number of issues which, in its opinion, require policy decisions by the Comission in order to assure the viability of the affected proposed plants. These issues are listed in Enclosure 2.
We encouraged the Applicants Group to present its views on this matter to the ACRS and the Commission at the same time that we discuss with these bodies our proposed requirements.
The Applicants Group expressed concern about the availability of our resources to complete our review of the NTCP applications, including the information to be submitted in response to our proposed requirements, and to support the associated public hearings. We described the impending Office of Nuclear Reactor Regulation reorganization and how our review of the NTCP applications would likely be affected by the reorganization. We also advised the Applicants Group that, although we plan to devote the majority of our resources to operating plants and plants that are under construction, we do plan to allocate a limited amount of our resources to the NTCP applications.
We provided the Applicants Group with copies of our proposed requirement category assignments for each of the action items of Draft 3 of the TMI-2 Action Plan. A copy of our proposed requirement category assignments is provided herein as Enclosure 3.
We also discussed with the Applicants Group the remaining differences between our proposed requirement category assign-ments and those of the Applicants Working Group. These differences are noted in Enclosure 4.
8004240 b5)
APR 7 1980 Meeting Sumary - April 2,1980 Finally, we advised the Applicants Group of our future plans with regard to our proposed requirements. Namely, we are scheduled to discuss our proposed requirements with the TMI-2 Accident Implications ACRS Subcommittee at its April 9, 1980 meeting. We plan to discuss our proposed requirements with the ACRS Full Committee at its May meeting and hope to receive a letter from the ACRS in mid-May. We also plan to present our proposed requirements to the Commission for its consideration in the form of a Commission Paper in late-May or early-June.
M o. O&n Cecil 0. Thomas, Project Manager Standardization Branch Division of Project Management
Enclosures:
As stated cc w/ enclosures:
See attached lists i
ENCLOSURE 1 ATTENDANCE LIST - APRIL 2, 1980 MEETING WITH NTCP APPLICANTS GROUP Applicants Group '
i l
Vaughn L. Conrad Public Service Company of Oklahoma Gordon W. Jacobsen Puget Sound Power & Light Company James E. Mecca Puget Sound Power & Light Company t
Edward Howard Boston Edison Company George M. McHugh, Jr.
Boston Edison Company R. M. Butler Boston Edison Company Dale Stoodley Boston Edison Company W. H. Rasin Duke Power Company Jack Newman Lowenstein, Newman, Reis, Axelrad & Toll i
Kathleen H. Shea Lowenstein, Newman, Reis, Axelrad & Toll George 0prea Houston Lighting & Power Company Joseph Gallo Isham, Lincoln & Beale Other Charles S. Rogers Attorney General, State of Oklahoma Nuclear Regulatory Commission H. Denton C. Thomas D. Ross P. O'Reilly R. Denise J. Snell R. Purple J. Conran W. Kane T. Cox E. Reis F. Miraglia R. Goddard i
o O
ENCLOSURE 2 ITEMS DEEMED BY THE APPLICANTS GROUP TO REQUIRE COMMISSION POLICY DECISIONS TO ASSURE PROJECT VIABILITY f
1.
Siting 2.
Degraded Core Conditions 4.
Management for Design and Construction 5.
Control Room Design 6.
Reliability and Risk Assessment 7.
Radiation Source Control i
8.
Radioactive Gas Management 9.
Quality Assurance List 10.
Electric Power 11.
Simulator 12.
Radioactive Effluent Monitoring
ENCLOSURE 3 PROPOSED REQUIREMENT CATEGORY ASSIGNMENTS TAALE 1 -
' CATEGOR.IZATLOW OF ITEMS IN TMI-2 ACTION PLAN Implementation for Near-Tenn Actlen Ites Co Appljcations I.
Operational Safety I.A.I Operating Personnel and staffing l.
shift technical Adviser 2*
Refer to " Criteria for Utility Management and Technical Competence," Draft dated 2/25/80 for 2
guidance.
2.
shif t sigerviser Admin. Duties 3.
Shift Manning 2*
Same as I.A.l.1 above e
4.
Ieas-term upgrading ld Same as I.A.1.1 above I.A.2 Tralelas and Quellfications of Operating Personnel ld Same as I.A.l.1 above 1.
Immediate Upgrade of 30 and 500 Qual.
2.
Training and Qualifications of Other ld Same as I.A.l.1 above Personnel ID 3.
lult Audit Training 4.
NRR Participation in IE Inspector ID 1 raining 5.
Plant Drills 2
6.
tong-ters thwrading lb Same as I.A.l.1 above 7.
Accreditation of Iraining 1b lastitullons
~
o See Comments
IAftLE I (continued)
Implementation for Near-term Comments Actlen lies CP Applications I.A.3 Licensing and Requalification of Operating Personnel 1.
Revise scope and criteria for Emans 2
Refer to Action Plan Item I.A.3.2 2.
NBC Operator Licensing Reforms lb 3.
operator Fitness lb NRC to develop criteria.
4.
Licenslag of Additlenal Operattens
]d Personnel lb 5.
IIRC/B0E/INro Statement of understanding I.A.4 5Beulater Use and Development 1.
Inltlal Slaulater Improvement ld 2.
Long-Tere Slaulater upgrading 4
3.
Nec Training Slaulator lb 4.
NRC Engineering Computer Ib I.B.I Management for Operations 1.
Organization and Management 5
NRC to develop criteria Long-tere Improvements 2.
Evaluation of NIOL Organization and Management Improvements Id 3.
Loss of Safety' function ID
-2~
o See Coments
l 1A8tE I (continued)
Implementation for Near-Term Comments Actlen item CP Applications I.O.2 laspection of Operating Reacters 1.
Revise IE Inspectlen Program 1b 2.
Resident Inspector at Operating Beacters 1D 3.
Seglemal Evaluations 1b 4.
Overview of Licenaee Performance 1 b I.C Sperating Precedures 1.
Short-Ters Accident Analysis and Precedure Revisten 4
2.
Shift and Rollet Turnover 2
2 3.
shift Swerviser Responsibilities 2
4.
Centrol Rees Access 4
5.
Eeeesck of Operating Emperience 2
Action Plan to be modified to address construction 6.
Verification of operating Activities 7.
N555 Vender Review 2
a.
Pilot Program - NIOL 1b 9.
Long-Term Program Plan 4
3 o See Comments
IkStE1 (continued)
Implementation for Near-Term Comments A'"I*" II'"
CP Applications 1.8 Centrol Rees Besign 4
I.
Design Review 2.
Safety Parameter Ceasele 4
3.
Systes status neeltering 4
4.
Design standard 4
NRC criteria to be based on revision of IEEE Stds. 566 and 567.
5.
Research 1b 6.
Technology Transfer Conference 1b I.E Analysis and elsseelnatles of Operating E gerlence I.
Office for Analysis and Evalmallen of Operational yb seta 1 b 2.
Office Programs 1b 3.
Sata Analysis 4.
Coordination of Programs 4
5.
Nuclear Plant Reliability Data Syste.
1b 6.
Reporting Requirements 1 b
- See Comments 4,
.----y
-m s
TA8tE 1 (continued)
Implementation for Near-Term Connents CP Applications 7.
Foreign sources lb 8.
Ituman Error Analysis lb I.F quellty Assurance I.
Expand 44 list 4
2.
Detalled Criteria 4
8.G Training During Low-Peuer Testing l.
Training Requirements 1
2.
Scope of lest Program (Does not exist)
II. Siting and Design II.A Siting
't.
Siting Policy Rulemaking lb 2.
Site Evaluation 4
II.B Degraded er Melted Ceres 1.
Primary System Vents 4
2.
Plant 58eleiding 4
3.
Festaccident Sampling 4.
r e
IABLE 1 (continued)
Implementation for Near-Tem Comments CP Applications 4.
Training 2
5.
Research lb 6.
Risk Reductiee for Operatlag Reacters at Sites with High Populatloa Sensity 1C 7.
Contalement Inerting 4
8.
Rulemaking en Degraded Core Accidents Ib II.C Reliability Engineering and Risk Assessment 1.
Initial Integrated Rellability Evaluation Progran (IREP) lb 2.
Continuallen of IREp lb 3.
Systems Interaction lc 4.
Reliability Engineering 2
11.8 Reacter Coolant System Roller and Safety valves I.
Test Requirements 4
TABLE I (continued)
I.nplementation for hear-Term Coments Actles Itse.
CP Applications 2.-
Research 3
3.
Positten Indication 4
II.E SystemDesled II.E.1 Annillary feeeheater System NRC to develop schedule.
I.
Evaluatten 3
4 2.
Ante Initiation and flow Indication Ib 3.
Lipdate Sar and Issue Regulatory Guide II.E.2 Emergency Core Coeling System 2
1.
Bellence en ECCS lb 2.
Research 3.
Uncertainties la Performance 3
NRC to develop schedule.
Predictlens II.E.3 Decay llent Renewal 1.
ItaturalCirculation 4
2.
Systems sellability lb O See Coments
,7,
IA8t E 1 (continueil)
Implementation for Near-Term Comments Actlen Ites CF Applical.iund 3.
Alternate Concepts Research lb 4.
Regulatory Guide Ib II.E.4 Centainment Design 1.
Dedicated Penetrations 5
2.
Isolatten Bependability 3.
Integrity Check 2
4 4.
Purging II.E.5 Besign Sensitivity of S&W Reacters dI.E.6 In Situ Testing of Valves lb II.F Instrimentallen and Centrols 1.
Additlenal Accident Monitoring Instrueentallen 4
4 2.
Inadequate Core Coeling 3.
4.
Centrol and Protectlen Actions lb
.g.
i IABLE 1 (continued)
Implementation for Near-Term Comments Actlen Item CP Applications II.8 Electrical Power for PetV. Sleck Valve and level Indicatten 4
II.N IME-2 Cleanup and Enamination l.
IME-2 Safety lb 2.
abtain Information lb 3.
Evaluation and feeeack lb Action Plan should be revised to address applicability at construction permit stage of 4.
Secleecenamic Effect and review.
Property values lb II.J General leplicatlens of IMI for Design and Constructlen Activities II.J.I Vender Inspectlen Progran I.
Inspectlen Priority lb 2.
Modify Existing Progran lb lb 3.
Expand Regulatory Centrol 4.
Resident inspectors at NS$$
Vendors and AEs lb II.J.2 Constructic.a inspection Progran 1.
Reorlent Program Ib 2.
Independent Measurement lb i 0 See Comnents
TABLE I (continued)
Ir.iplementation for Near-Term CP Applications 3.
Resident inspectors lb II.J.3 Management for Design and Construction 5
1.
Organlaation and Staffing 2.
Regulatory Guide Ib II.J.4 Revise Deficiency Reporting Ib Requirements II.E Small-Break LOCAs and Less of feedwater Accidents See Table C.1 1.
IE Bulletins 2.
Commission orders en R&W Plants See Table C.2 3.
Final Recommendations of B&O See Table C.3 lask Force Ill. Energency Preparattens and Radiation Protection Ill.A.I Igrove Licensee Emergency Preparedness Short-ters 1
).
tipgradeEmergencfPreparedness 5
2.
tipgrade Support Facilities 4
IABLE 1 (continued)
Implementation for Near-Term Comments i.:
Actfen Ites CP Applications 2*
Applies to workers only. N/A to public.
3.
Thyroid Blocking Agent Ill.A.2 Improving Licensee Emergency Preparedness - Long-ters 1.
Rule Change 5
2.
Guldence and Criteria 5
Ill.A.3 leproving NGC Emergency Preparedness 1.
MRC Role 1b Ib 2.
Improve Operattens Centers 3.
Communications 4
4.
Nuclear Data Link 4
5.
Iraining. Drills, and insts 2
6.
Interactlen with Other Agencies Ib Ill.B Emergency Preparedness of State and Local Governments I.
Transfer of Responsibilities to FEMA lb 2.
Implementation of NRC and FEMA Responsibilities 1b
- See Comments
. II -
TABLE I (continued)
Implementation for Near-Tenn A*"I*"
I"*"
"* " S CP Applications
'Pielic Informatlee III.C 1.
Infersatten Availability 1b Action Plan should be revised to address construction.
permit stage of review.
2.
Agency Policy and Training ib Ill.t.1 Radiatlee Source Centrol 1.
Source Outside Contalement 4
2.
Radleactivedasflanagement 4
Action Plan should be revised to include requirements for applicants.
3.
Vent System and Radlelodine Adsorber Criteria 4
4.
Raesaste System Besign features lb III.B.2 Public Radiatlee Protectieg Improvement 1.
Effluent Monitoring lb 2.
Radlelodine, Carbon-14, and Tritium D
Path Dese Analysis 3.
Liquid Pathway Radlelogical Centrol 2
4.
Offsite Bose Measurements 2
5.
Dose Calculation Manuel 2
In$pendentMeasurements 6.
Ib o See Coments
IA8LE 1 (continued)
Implementation for Near-Term Action itse Comments III.S.3 Worker Radiation Protectlen Improvements 1.
Radiatten Protectlen Plans 4
2.
Ilealth Physics Improvements ib f4RC to develop criteria.
3.
Implant Monitoring 4
4.
Castrel Room Habitability 4
5.
Badiation Worker Exposure Data Base la IV. Practices and Precedures IV.A Strengthen Enforcement Authority I.
Seek Legislative Authority ID 2.
Revise Enforcement Policy lb IV.B Revise Practices for Providing lastructlens and Information to Licensees lb IV.C Entend lessons learned to Licensed i
Activltles Other Than Power Reacters lb IV.O Assess NGC Training Heeds lb o See comments. _ _ _.
.. - ~ _
TABLE I (continued)
Implementation for Near-Term Actlen Ites CP Applications Comments IV.E Safety teclslan-h king 1.
Espand Research en quantificatten lb
, of safety Socislen-Making 2.
Plan for early resolution of safety issues l b Plan for Resolving lasses at 3.
Censtructlen Peralt Stage 1b
- 4. Resolve Generic Issues by Relemaking lb
- 5. Assess Currently Operatlag Beacters lb IV.F Financlel BIsincentive to Safety I.
Increased IE Scrutiny of Power Ascenslen Test Progran lb 2.
Evaluate Ispact of Financial Disincentives to Safety of Nuclear Power Plants lb IV.S leprove Sirety Rulemaking Procedures 1.
Sevelop Public Agenda lb 2.
Perledic and Systematic Reevaluation of Enlsting Rules 1b 3.
leprove Rulemaking Procedures lb 4.
Stanly Alternative for leproved Rulemaking Process ID
. gg -
TABLE 1 (continued)
Implementation for Near-Term U""*"
S Actlen Ites CP Applications V.
IWC Policy Orgentration, and !'
- -
- nt l.
IWC Policy Statement en Safety 1b 2.
Study Elleination of Hensafety b
1 Responsibilities 3.
Strengthen Role of ACR5 1b 4.
Study Need for Addlllenal Advisory Cemelttees 1b 5.
Improve Feelic and Intervenor Participallen la Hearing Process 1 b 6.
Study Constructlen-guring-Adjudicallen Rules 1b 7.
Study IIeed for INI-Related legislatten 1b a.
Study Need to Establish an Independent leuclear Safety Board 1D 9.
Study Refens of Licensing Process 1b
- 13. Study NRC Top Management Structure and Process 1 b 1
- 11. Reenseine Organlaation and functions of NRC Offices 1b j
G m
l TABLE 1 (continued) l l
l f
Implementation for Near-Tem Coments Actlen Ites CP Applications l
l
- 12. Revise Selegetless of Antherity to Staff lb
- 13. Roles of Chatraan, Commission, and EDO lb
- 14. Selesale Emergency Response lb functions to e Single Camelsstener
- 15. Achieve Single Location - Long-term lb
- 16. Achieve Single Lacellen - Interin lb
- 17. Reenamine Cennission Role in Adjudication lb l
i
TABLE C.1 0FFICE OF INSPECTIDH AND ENFORCEMENT 8ULLETINS N
Operating Operating Source for Reactor License Requirement Operating Reactors Appilcability Implementation Implementationf 1.
Review TMI-2 PNs and detailed chronology 79-05&05A (Item 1)
of the TMI-2 accident.
79-06&O6A (Item 1)
I.A.3.1 79-06&O68 (Item 1) 79-08 (Item 1) 2.
Review transients'siellar to THI-2 that 79-05&05A (Item 2)
B&W 3/31/80 1.A.2.2 have occurred at other facilities and I.A.3.1 2
NRC evaluation of Davis-Besse transient.
3.
Review operating procedures for recog-79-05&05A (Item 3)
PWR 3/31/80 I.C.1 nizing, preventing, and mitigating void 79-06&O6A (Item 2) 2 formation in transients and accidents.
79-06&O6B (Item 2) 4.
Review operating procedures and training 79-05&05A (Item 4.a) PWR and BWR 3/31/80 I. C.1 2
instructions to ensure that:
79-05B (Item 2)
I.C.7 79-06A (Item 7.a)
I.G.1 a.
Operators to not override ESF 79-068 (Item 6.a) 1.C.8 actions unless continued operation 79-08 (Item 5.a) is unsafe; b.
HPI system remains in operation (if 79-05&05A (Item 4.b) PWR and BWR 3/31/80 I.C.1 2
actuated automatically) unless79-058 (Item 1)79-06A (Item 7.b)
(1) LPI pumps operating at >1000 gpa 79-068 (Item 6.b) and situation stable for 20 min; (2) HPI system operating for 20 min.
RCS > 50*F subcooled (limited by RV NOT considerations).
C.1-1 e
n.
--.,,,.-.,,-,..,w
TABLE C.1 (continu:d) t N
Operating Operating T
Source for Reactor License p
Requirement Operating Reactors Applicability Implementation Implementation 1
c.
Uniti long-tera design change 79-06C (Item 1.A)
PWR Complete I.C.1 requirement of IE8 79-06C is79-05C (Item 1.A)
I. A.1. 3 taplemented:
79-06C (Item 1.B)
Id (1) Upon reactor trip and HPI initia-79-06C (Item 1.8) tion caused by RCS low pressura,79-05C (Iten 1.8)
II.K.3.5 famed. trip all operating RCPs;-
(2) Provide two opeiators in CR at all times to accomplish RCP trips (three operators for dual CR facility 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.79-068 (Ites 6.d)
II.F.2 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 79-068 (Item 7)
I.C.6 controls and all related test arti 79-008 (Item 6) maintenance procedures to assure 2
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 2
position. See Requirement 8 below.
I.C.6 c.1-2
TABLE C.1 (continued)
N Operating Operating T
Source for Reactor License C
Requirement Operating Reactors Appitcability Implementation Implementationp 6.
Review containment isolation initiation 79/05A (Iten 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 79-068 (Item 3) 2 features or cooling capability upon 79-08 (Item 2) automatic initiation of SI.
7.
Implement positive position controls on 79-05A (Ites 7)
B&W 3/31/80 II.E.1.1 2
valves that could compromise or defeat AFW flow.
8.
Immediately implement procedures that 79-05A (Item 8)
B&W 3/31/80 II.E.1.1 assure two independent 100% AFW flow paths, 2
or specify explicitly LCO with reduced AFW capacity.
9.
Review procedures to assure that radio-79-05A (Ites 9)
PWR and BWR 3/31/80 II.E.4.2 active liquids and gases are not trans-79-06A (Ites 9) 2 ferred out of containment inadvertently 79-068 (Item 8) especially upon ESF reset).
List all 79-08 (Item 7) appilcable 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, 2
related systess from service (and 79-068 (Ites 9) before FL restoring to service) to assure 79-08 (Item 8)
OL:
I.C.2 &
operability status is known.
I.C.6 C.1-3
TABLE C.1 (continued)
Operating Operating Source for Reactor License C
Requirement Operating Reactors Applicability Implementation Implementatio#
- 11. Make all operating and maintenance 79-05A (Item 11)
PWR and BWR 3/31/80 f.A.3.1 personnel aware of the seriousness79-06A (Item 1.a)
I.A.2.2 and consequences of the erroneous79-06B (Item 1.a) 2 actions taken leading up to, and in 79-08 (Item 1.a) ear'ly phases of, the THI-2 accident.
- 12. One hour notification requirement, and 79-05B (Ites 6)
PWR and BWR Complete I.E.6 continuous commualcations channel.79-06A (Item 11)
III.A.3.3 79-068 (Item 10) 2 79-08 (Ites 9)
- 13. Propose Technical Specification changes79-058 (Item 7)
PWR and BWR 1/1/81 Normal work reflecting implementation of all Bulletin 79-06A & Rev. I on all new OLs items, as required.
(Iten 13) la 79-068 (Item 12) 79-08 (Ites 11)
- 14. Review operating modes and procedures79-06A (Ites 12)
W. CE GE 3/31/80 II.B.4 to deal with significant amounts of 79-068 (Ites 11) 11.8.7 2
79-08 (Item 10)
II.E.4.1 II.F.1 15.
For facilities with non-automatic AFW 79-06A (Ites 5)
W & CE Complete II.E.1.2 initiation, provide dedicated operator 79-068 (Ites 4) id in continuous communication with CR to operator AFW.
C.1-4
TABLE C.1 (centinued) l I
N Operating Operating T
l Source for Reactor License C
i Requirement Operating Reactors Appilcability Implementation Implementationp l
16.
Implement (immediately) procedures that 79-06A (Ites 6)
W & CE Complete I. C. )
identify PRZ PORV "Open" indications and 79-068 (Itee 5) 11.0.3 I4 that direct operator to close manually at "2ESET" setpoint.
1
- 17. Trip PZR Level Bistable so that PZR Lo 79-06A & Rev. 1 W
Complete Same as ors, Press. (rather than PZR Lo Press. and PZR (Item 3) before FL Ic Lo Level coincidence) will trip reactor.
for test, reset to Level bistable.
18.
Develop procedures and train operators on 79-058 (Item 1)'
BtW Complete I.C.1 methods of establishing and maintaining I.G 1 natural circulation.
2
~19.
Describe design and procedure modifications79-058 (Ites 3) 8&W 3/31/80 II.E.5 (based on analysis) to reduce likelihood 2
of automatic PZR PORV actuation in transients.
20.
Provide procedures and training to 79-058 (Item 4)
B&W 3/31/80 Same as ors, operators for prompt manual reactor trip before FL 4
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, If, or significant before FL 5
decrease in SG 1evel.
=
C.1 8
NTCP 5
5 2
2 2
2 no i
t s
s,
R 2.L a
R O
g t
OL F. F n
n F
1 iee s
s t sm ae aI e 2
ane r
I r 1
1 131 1
. F.
rel eo e
o ecp mf mdf C.
C.
C. A. G.
C. I pi m ae ane OLI Sb S ab I
I III II no i
ta g
t n
n e
e e
e ire 0
0 t
t t
t t om 8
8 e
e e
e at e
/
/
l l
l l
rcl 1
1 p
p p
p eap 3
3 m
m m
m pem
/
/
o o
o o
ORI 3
3 C
C C
C e
y t
i l
i bac i
lp R
R R
R R
R p
W W
W W
W W
A B
B P
P P
P
)
deu s
n r
i o
t t
n c
)
)
e a
3 4
t t
t t
t t
t t
c e
r) r) r) r) r) r) r) r)
(
R m
s o2o2 o3o3 o4o4 o5o5 r
e e
h h
h h
h h
h h
6 1
og t
t ssss ssss ssss smss f n I
I
( e( e
( e( e
( e( e
( e( e 1
C i
(
(
t t
t t
t t
t t
et CICI CICI CICI CICI C
E ca 8
8 5
6 5
6 5
6 5
6 L
rr 0
0 0 s0 n 0s0n 0s0n 0n0 n B
ue r-r r-r r-r r-r A
op 9
9 9e9e 9e9e 9e9e 9 e9e T
SO 7
7 7t7t 7t7t 7t7t 7t7t sn d
i
'O es Rd s
r.
e e
np n
P b
sn s
f
()
io i
C oye l
o e
al l
R irt e
sv re ee tas v
e eo t v dre ciy e
s gf p nb e
i on al s l
m noi ia dd uci i
e a
r l
n g
f xW V
t ret e4 as ee l
auF Rds g
d2 e
ptd uaM ny anr i
sn oa t
n f ase ao ut ei l u n
af n o
v rrt gn rl eqo e
moe c yi o
c e
ue ves m
h sitt faa nm dd edl e
dgw et ea e
oe ei daA r
nn paf n sdr ir cu n
ais ymar en ti oge di iu nm t ose san cu r
v n
q coe t
t y
e aq pno ars e
iit dunl l se e
ob on R
tt s naoa aew rR y
a sf oa
.n nzt o
cd e
ii acy a
i mns rt eo aie t n ne5 sst r ou soabi sb ai es2 yeie tfl e efiit A
p r
ga l rdt u
al s
t ra Cksi es rbt auni arvb unict Oaer pe e
n ndor eoa onsn L est os mse aecc m
c epmr eiiee rp y
e'O e boee bt dm mbaP pl e o gt irrp ial u
r lC oa err drnr rp o
rca
,r ol R
l n sSi i pi a c
t ciuot fl e ea i
u v
lt srat sdnss ramd v
vdq odos eoeo enal n emin en ene rnoe Dfhn DimAi Psta Do RaR Pacr 2
3 4
5 6
7 2
2 2
2 2
2
TABLE C.1 (centinued)
N Operating Operating T
Source for Reactor License C
Requirement Operating Reactors Appilcability Implementation Implementation P
- 28. Provide design that will assure automatic 79-05C (long-PWR 1/1/81 See Table C.3, Item 5 RCP trip for all circumstances where ters Ites 1)
Id required.79-06C (long-tere Ites 1)
~
f C.1-7
TABLE C.2 REQUIREMENTS FOR NEW B&W PLANTS DERIVE 0 FROM COMMISSION ORDERS OH OPERATING B&W PLANTS a
Operating Operating T
Requirement Source Applicability Reactor License C
P Implementation Implementation 1.
Upgrade timeliness and reliability Commission Order B&W Complete II.E.1 of AFW system.
Id 2.
Procedures and training to initiate Commission Order B&W Complete II.K.2 4
and control APJ independent of integrated control system.
3.
Hard-wired control grade anticipatory Commission Order B&W Complete None-see jd reactor trips.
Requirement 10 below 4.
Small-break LOCA analysis, procedures, Commission Order B&W Complete I.A.3.1 and operator training.
I.C.)
Id 5.
Complete TMI-2 slaulator training for Coenission Order B&W Complete I.A.3.1 all operators.
2 6.
Reevaluate analysis for dual-level Commission Order Davis-Besse 1 Complete NA setpoint control.
Ic 7.
Reevaluate transient of September 24, Commission Order Davis-Besse 1 Complete NA Ic 1977.
8.
Continued upgrading of AfW system.
Commission Order B&W 1/1/81 II.E.1 Id C.2-1 m
TABLE C.2 (centinued)
N Operating Operating T
Requirement Source Applicability Reactor License C
Implementation Implementation P
9.
Analysis and upgrading of integrated Commission Order B&W 1/1/81 Same as ors, control system.
before OL 4
- 10. Hard-wired safety grade anticipatory Commission Order B&W 1/1/81 Same as ors, reactor trips.
before OL 4
- 11. Operator training and drilling.
Commission Order B&W
~1/1/81 I.A.3.1 Id I.A.2.2 I.A.2.5 1.G.I
!.C.1 Id 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 3
8/21/79
- 14. Demonstrate that predicted lif t Letter, D. Ross to B&W 1/1/81 Same as ors, 3
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, 3
once-through steam generator tubes B&W operating plants, before OL after primary systen voiding.
8/21/79 C.2-2
nTCP 3
2 2
2 2
e j
no i
t s
a R
g t
OL n
n O
iee s
t sm ae ane r
)
1
)
1 e
rel eo n
ecp mf C.
C.
C.
C.
o pi m ae OLI Sb I
I I
I N
no i
ta g
t n
n e
ire t
t om 0
1 1
1 e
at e 8
8 1
8 8
l
/
/
p rcl
/
/
1 1
m C.
eap 1
1
/
/
o pem
/
/
n ORI 6
1 I
1 1
C y
t i
l i
ba W
W W
W W
c B
B B
B B
l i
p W
l l
l l
l p
l l
l l
l
)
A B
A A
A A
A d:un i
t g
s s
s s
n n
t t
t t
e o
i on on on on c
t t
t a t a ta t a
(
a l
l l
l s
9 dr sp sp sp sp 3
2 s
7 ie s
s s
s o g/
e p0 og og og og 2
C R n1 Ro8 Rn Rn Rn Rn e
i2
/
i i
i i
c E
c
.t/
.W9
.t
.t
.t
.t L
r Da8 R&/
Da Da Da Da
,B 1 r
,r r
r B
u r
,e9 e9
,e9
,e9 A
o
.e T
S rps rl s r p7 r p7 r p7 r p7 eot elt eo/
eo/
eo/
eo/
t n
tan t
1 t
1 t
1 t
1 tWa t
a tW2 tW2 tW2 tW2 e&l eol e&/
e&/
e&/
e&/
LBp Lt p LB8 LB8 LB8 LB8 e
e
- r t
l u gi l s as ns if s
d me wf nt n
l sr oo i n a
a p
l e
i e o
t a t s lf gi r
oo ns es na e
f i n tt et et s
da an us ss es i r we q
ny go ot di eh os al v
es sg p
t m
d en u
ssn t
ah l e f a f o eei n
dt at r
or rso s
e i
i a ft h
up n
l w t p o
st mat o
m e
a ni d
i -
ece i
r eA ec se se t
s t
i sC ti st yc st c
u O
ot oa l n yaV i
q PL pn l p ao shR d
e C
a i
n tO e
R Rk f
f c ao f
P r
oA p
a og oi t.
f e n
t k
r Cd or si sn rwo sOe 1
b ir i a aot iLe t -.
su s
ml a s
c 3
cl r yd yr hf r yk x al e l
l e c
e l ae T
paw aS ah nWn ae F
mmo nC nt eFe nro O
I sp AR Ao bag Abt L
6 7
8 9
0 1
1 1
1 1
2 2
TA8tE C.3 FINAL RECOMENDATIONS OF 8ULLETINS AND ORDERS TASK FnREE N
Near-Ters T
Operating Operating Operating C
Reactor License License P
Requirement Source App 11cabillty Implementation ImplemenLation Requireaents 1.
Install automatic PORY isolation NUREG-0565(2.1.2.a)
system and perform operational NUREG-0611(3.2.4.e and first test.
3.2.4.f) refueling NUREG-0635(3.2.4.a)
(3.2.4.b) 2.
Report on overall safety effect NUREG-0565 (2.1.2.d) of PORV isolation system.
NUREG-0611(3.2.4.g.
3.2.4.1)
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) 2 annually.
NUREG-0611(3.2.4.h, 3.2.4.j)
NUREG-0626(8.14)
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 lb equipment for small-break LOCA NUREG-0626 (8.12)
II.C.3 mitigation.
NUREG-0635(3.2.2.b) 5.
Install automatic trip of RCPs NUREG-0565(2.3.2.a)
PWR 1/1/81 Same as OR NA during LOCA.
NUREG-0611(3.2.2.a) 4 NUREG-0635(3.2.2.a)
C.3-1
TABLE C.3 (continued)
N Near-Ters T
Operating Operating Operating C
Reactor License License P
Requirement Source App 11cabtilty Implementation Implementation Requiresents 6.
Instrumentation to verify NUREG-0565(2.6.2.b)
PWR I.C.1 I.C.1 NA 2
natural circulation.
NUREG-0611(3.2.3.b)
II.F.2 II.F.2 NUREG-0635(3.2.3.b)
II.F.3 II.F.3 7.
Evaluattun of PORV opening NUREG-0565(2.1.2.b)
B&W See Table II.K.2.14 NA 2
probability during overpressure C.2, ites transive..
14 8.
Consideration of diverse decay NUREG-0565(2.5.2.a)
Davis-Besse 1 II.C.1 II.C.1 NA 2
heat removal method for Davis-design type Besse 1.
9.
Pressure Integral Derivative NUREG-0611(3.2.4.b)
W 7/1/80 Same as OR FL controller modification.
2
- 10. Anticipatory trip modifcation NUREG-0611(3.2.4.c)
W Plant by Same as OR FL proposed by some licensees to plant 5
confine range of use to high power levels.
l r
j
- 11. Control use of PORV supplied NUREG-0611(3.2.4.d)
All NA Same as OR FL by Control Components Inc. until 5
l further review complete.
l l
l
- 12. Confirm existence of anticipa-NUREG-0611(3.2.4.a)
W 7/1/80 Same as OR FL Ic l
tory trip upon turbine trip.
l l
l C.3-2 i
TA8LE C.3 (continued)
N Near-Tern T
Operating Operating Operating C
Reactor License License P
Requirement Source Applicability Implementation Implementation Requirements
- 13. Separation of HPCI and RCIC NUREG-0626(A.1)
GE 10/1/80 &
Same as OR NA 3
system initiation levels.
4/1/81 Analysis and implementation.
14.
Isolation of isolation NUREG-0626(A.2)
GE plants 1/1/81 NA NA je condensers oc high radiation, with isolation condenser
- 15. Modify break detection logic NUREG-0626(A.3)
to prevent spurious isolation of HPCI and RCIC systems,
- 16. Reduction of challenges and NUREG-0626(A.4)
GE 1/1/81 &
Same as OR NA failures of relief valves -
1/1/82 feasibility study and system modification.
- 17. Report on outage of ECC NUREG-0626(A.6)
GE 1/1/81 Same as OR NA la systems - Ilcensee report and proposed technical specification changes.
18.
Modification of ADS logic -
NUREG-0626(A.7)
GE 1/1/81 &
Same as OR NA 3
feasibility study and modifica-1/1/82 tion for increased diversity for same event sequences.
C.3-3
TABLE C.3 (continued)
~
N Near-Ter.
T Operating Operating Operating C
l Reactor License License P
Requirement Source Appilcability Implementation Implementation Requirements
(
19.
Interlock on recirculation NUREG-0626(A.8)
GE Non-Jet 1/1/81 NA NA pump loops.
Pump ors Ic 20.
Loss of service water for NUREG-0626(A.9)
Big Rock 1/1/81 NA NA Big Rock Point.
Point Ic
~ 21. Restart of core spray and LPCI huREG-0626(A.10)
GE 1/1/81 &
Same as OR NA systems on low level - design 1/1/82 3
and modification.
Ic
- 22. Automatic switchover of RCIC NOREG-0626(B.1)
GE 1/1/81 &
Same as OR NA system suction verify 1/1/82 procedures and modify design.
- 23. Central water level recording.
NUREG-0626(B.2) l GE I.D.2 I.D.2 NA III.A.1.2 III.A.I.2 4
III.A.3.4 III.A.3.4
- 24. Confirm adequacy of space cool-NUREG-0626(8.3)
GE 1/1/82 Same as OR NA Ing for HPCI and RCIC systems.
3
- 25. Effect of loss of AC power on NUREG-0626(B.4)
GE 1/1/82 Same as OR NA pump seals.
3 26.
Study effect on RHR reliability NUREG-0626(B.5)
GE II.E.2.1 II.E.2.1 NA of its use for fuel pool cooling.
3 C.3-4 a
1
~
TABLE C.3 (continu:d)
N Near-Tenn T
Operating Operating Operating C
Reactor License License P
Requirement Source Applicability Implementation Implementation Requirements
- 27. Provide common reference level NUREG-0626(8.6)
for vessel level instrumentation.
28.
Study and verify qualification NUREG-0626(B.7)
of accumulators on A05 valves.
- 29. Provide diverse initiation NUREG-0626(B.10)
signal for RCIC system if used for LOCA.
- 30. Study to demonstrate perform-NUREG-0626(8.13)
GE Isolation 4/1/81 NA NA jc ance of isolation condensers Condenser ors with non-condensibles.
- 31. Revised small-break LOCA methods NUREG-0565(2.2.2.a)
All 1/1/82 10 CFR 50, FP 3
to show compliance with 10 CFR NUREG-0611(3.2.1.a)
App. K 50, Appendix K.
NUREG-0626(A.12)
NUREG-0635(3.2.1.a)
(3.2.5.a)
- 32. Plant-specific calculations to NUREG-0565(2.2.2.b)
All 1/1/83 10 CFR 50, FP 3
show compliance with 10 CFR NUREG-0611(3.2.1.0)
App. K 50.46.
NUREG-0626(A.13)
NUREG-0635(3.2.1.b)
C.3-5 l
. e
TABLE C.3 (centinued)
N Near-Ters T
Operating Operating Operating C
Reactor License License P
Requiresent Source Applicabi11ty Implementation Impiesentation Requirements 33.
Provide experimental verifica-NUREG-0565(2.6.2.a)
tion of two phase natural WREG-0611(3. 2. 3. a )
circulation models.
NUREG-0635(3.2.3.a)
- 34. Evaluate ellaination of PORV NUREG-0565(3.5)
PWR II.C.1 II.C.1 NA lb function.
NUREG-0611(3.2.4.k)
NUREG-0635(3.2.4.e) 35.
RELAP-4 model development.
NUREG-0611(3.2.5)
PWR II.E.2.2 II.E.2.2 NA NUREG-0635(3.2.5)
Ib
- 36. Evaluation of effects of core NUREG-0565(2.2.2.c)
B&W I. C.1 I.C.1 NA flood tank injection on small-break LOCAs.
2
- 37. Additional staff audit calcula-NUREG-0565(2.4.2.a)
B&W I.C.1 I. C.1 NA tions of B&W small-break LOCA lb analyses.
- 38. Analysis of B&W plant response NUREG-0565(2.6.2.c)
B&W I.C.1 I. C.1 NA to isolated small-break 2
LOCA.
- 39. Analysis of plant response to NUREG-056S(2.6.2.d)
B&W I.C.1 I.C.1 NA a small-break LOCA in the 2
pressurizer spray line.
C.3-6
TABLE C.3 (centinued)
N T
Near-Term C
Operating Operating Operating p
Reactor License License Requirement Source Applicability Implementation Implementation Requirements
- 40. Evaluation of effects of water NUREG-0565(2.6.2.e)
B&W I. C.1 I.C.1 NA 2
slugs in piping caused by HPI and CFT flows.
~
- 41. Evaluation of RCP seal damage MUREG-0565(2.6.2.f)
B&W II.K.2.16 See Table C.2, MA and leakage during a small-item 16 2
break LOCA.
42.
Submit predictions for LOFT Test HUREG-0565(2.6.2.g)
B&W I.C.1 I.C.1 NA 2
L3-6 with RCPs running.
- 43. Subelt requested information NUREG-0565(2.6.2.h)
B&W I.C.1 I.C.1 NA on the effects of non-2 condensible gases.
- 44. Evaluation of mechanical effects NUREG-0565(2.6.2.1)
B&W II.K.2.15 See Table C.2,.
NA 2
of slug flow on steam generator item 15 tubes.
- 45. Evaluation of anticipated NUREG-0626(A.14)
transients with single failure to verify no fuel failure.
- 46. Evaluate depressurization with NUREG-0626(A.15)
other than A05.
C.3-7 o
l TABLE C.3 (continu:d)
N Near-Tern T
l Operating Operating Operating C
Reactor License License P
Requirement Source Applicability Implementation' Implementation Requirements
- 47. Response to list of concerns NUREG-0626(A.17)
GE 7/1/80 &
Same as OR NA 3
from ACRS consultant.
10/1/80
- 48. Test program for small-break NUREG-0626(B.9)
GE I.C.1 I.C.1 NA 2
LOCA model verification pretest II.E.2.2 II.E.2.2 prediction, test program and model
, verification.
- 49. 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&OTF recommendations.
2
- 50. 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 lb
- 51. Review of procedures NUREG-0611(3.4.2)
W, CE I.C.9 I.C.7 NA (NSSS vendors)
NUREG-0635(3.4.2)
I.C.9 Id 52.
Symptom-based emergency NUREG-0611(3.4.3)
W. CE I.C.9 I.C.9 NA procedures.
NUREG-0626(B.8)
GE 2
NUREG-0635(3.4.3)
- 53. 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 2
C.3-8
TABLE C.3 (continu2d)
N Near-Tere T
Operating Operating Operating C
Reactor License License p
Requirement Source Appilcability Implementation Implementation Requirements
- 54. Two operators in control race.
NUREG-0626(A.16)
GE I.A.1.3
. I. A.1. 3 NA Id
- 55. Simulator upgrade for small-NUREG-0565(2.3.2.c)
All I.A.4.1 1.A.4.1 NA 2
break LOCAs.
NUREG-0611(3.3.1.b)
NUREG-0626(8.11)
NUREG-0635(3.3.1.b)
- 56. Operator monitoring of control NUREG-0611(3.5.1)
W CE I.C.1 1.C.1 NA board.
NUREG-0635(3.5.1)
I.0.2 I.0.2 2
1.0.3 1.0.3
- 57. 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.3.3 I.A.3.3 2
1.A.2.6 I.A.2.6 58.
Identify water sources NUREG-0626(A.5)
GE 10/1/80 I.C.1 NA prior to manual 2
activation of ADS C.3-9 s
.._m
ENCLOSURE 4 Differences Between Proposed Staff and NTCP Applicants Group Categorizations of Items in TMI-2 Action Plan Action Item Proposed Staff NTCP Applicants Categorization Cat h !zation I.B.1 Management for Operations 1.
Organization and Management Long-Tenn Improvements 5
1 I.C.
Operating Procedures 6.
Verification of Operating Activities 2
2 9.
Long-Term Program Plan 4
1 1.D.
Control Room Design 4.
Design Standard 4
1 II.A.
Siting 1.
Siting Policy Rulemaking Ib 5
2.
Site Evaluation 4
5 II.B.
Degraded or Melted Cores 7.
Containment Inerting 4
1 II.D.
Reactor Coolant System Relief and Safety Valves 2.
Research 3
1 II.E.1 Auxiliary Feedwater System 1.1 Evaluation 3
4 II.E.2 Emergency Core Cooling System 2.3 Uncertainties in Performance Predictions 3
4 1
- See Table 1 for explanation.
i l
Differences Between Proposed Staff and NTCP Applicants Group Categorizations of Items in TMI-2 Action Plan c..
. Action Item Proposed Staff NTCP Applicants Group Categorization Categorization II.E.4 Containment Design
~~
4.1 Dedicated Penetrations 5
4
~
III.C Public Information 1.
Information Availability lb 1
III.D.2 Public Radiation Protection Improvement 2.1 Effluent Monitoring lb 2
e a
m Houston Lighting & Power Company cc:
R. Gordon Gooch, Esq.
Mr. E. A. Turner Baker & Botts Vice President of Power Plant 1701 Pennsylvania Avenue, N. W.
Construction'& Technical Services Washington, D. C.
20006 Houston Lighting & Power Company P. O. Box 1700 J. Gregory Copeland, Esq.
Houston, Texas 77001 Baker & Botts One Shell Plaza Houston, Texas 77002 Jack R. Newman, Esq.
Lowenstein, Newman, Reis & Axelrad 1025 Connecticut Avenue, N. W.
Washington, D. C.
20036 Mr. P. A. Horn Project Manager, ACNGS Houston Lighting & Power Company P. O. Box 1700 Houston, Texas 77001 Mr. Ray Matzelle Project Manager, ACNGS Ebasco Services, Inc.
19 Rector Street New York, New York 10005 Mr. Ray Lebre Project Manager, ACNGS General Electric 175 Kurtner Avenue San Jose, California 95125 Richard Lowerre, Esq.
Assistant Attorney General for the State of Texas Environmental Protection Division P. O. Box 12548 Capitol Station Austin, Texas 78711
L 2
r ccs (continued)
Ms. Carro Hinderstein.
8739 Link Terrace Houston, Texas 77025
[
t James Scott, Jr., Esq.
Texas Public Interest Research Group, Inc.
Box 237 UC University of Houston Houston, Texas 77004 i
7 Ms. Brenda A. McCorkle 6140 Darnell Houston, Texas 77074 Mr. John F. Doherty
]
4327 Alconbury Street Houston, Texas 77021 Sheldon J. - Wol fe, Esq.
1 Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C. 20555 l
Dr. E. Leonard Cheatum Route 3, Box 350A t
Watkinsville, Georgia 30677 r
Mr. Gustave A. Linenberger Atomic Safety & Licensing Board Panel l
U.S. Nuclear Regulatory Commission l
j Washington, D. C. 20555 i
i 1
i I
k t
n I
m y,
Mr. R. M. Butler Nuclear Projects fianager Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 cc: Mr. William Grif fin Stephen M. Leonard, Esq.
Project Engineer Assistant Attorney General Boston Edison Company Commonwealth of Massachusetts 800 Boylston Street One Ashburton Place,19th Floor Boston, Massachusetts 02199 Boston, Massachusetts 02108 Dale G. Stoodley, Counsel Henry Herrman, Esq.
Boston Edison Company 151 Tremont Street, 27K 800 Boylston Street Boston, Massachusetts 02111 Boston, Massachusetts 02199 Mr. & Mrs. Al an R. Cl eeton George H. Lewald, Esq.
22 Mackintosh Street Ropes & Gray Franklin, Massachusetts 02038 225 Franklin Street Boston, Massachusetts 02110 W. M. Sides Quality Assurance Manager Willian S. Abbott Boston Edison Company Attorney & Counsellor at Law 800 Boylston St.
50 Congress Street, Suite 925 Boston, Massachusetts 02199 Boston, Massachusetts 02109 Mr. R. A. Fortney B. N. Pushek EDS Nuclear Bechtel Power Corp.
220 Montgomery Street P. O. Box 3695 San Francisco, California 94104 San Francisco, California 94119 Andrew C. Goodhope, Chairman John D. Fassett Atomic Safety and Licensing Board Vice President and General U. 'S. Nuclear Regulatory Commission Counsel Washington, D. C.
20555 United Illuminating Company 80 Temple Street Dr. Dixon Callihan New Haven, Connecticut 06506 Union Carbide Corporation P. O. Box Y t'r. R. Ne hma n Oak Ridge, Tennessee 37830 Conbustion Engineering, Corp.
1000 Prospect Hill Road Dr. Richard F. Cole Windsor, Connecticut 06095 Atomic Safety and Licensing Board U. S. fiuclear Regulatory Connission W. C. Tallman, President Washington, D. C.
20555 i
Public Service Company of l
New Hampshire 1000 Elm Street 4
!4nchester, New Hampsh. ire 03105 i
i I
i 4 -
em
P Ib; iir. R. M. Butler cc: Richard S. Salzi.ian, Esq., Chairmati Atomic Safety and Licensing Appeal Board U. S. riuclear Regulatory Comnission 1
Washington, D. C.
20555 Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. fluclear Regulatory Commission Washington, D. C.
20555 i
Michael C. Farrar, Esq.
y ?.
Atomic Safety and Licensing Appeal Board a
U. S. fluclear Regulatory Comnission Washington, D. C.
20555
,N,/
s., 9 t
,me i
le o
t tas; hI i
I f4 h l'
'l p:
'd e%.
a vt F
en 1I
~
i l
y
~
' ll e.
e 4
i Portland General Electric Company j
CCs Mr.' Donald W. Godard, Supervisor Mr. William J.. Lindblad 4
Vice President i
Siting and Regulation Portland General Electric Company Department of Energy 21 i
Room lil, Labor and Industries Building pgrt an, Oregon 97205 i
Salem, Oregon 97310 Mr. E. G. Ward, Senior Project Manager l
Babcock & Wilcox Company P. O. Box 1260 Lynchburg, Virginia 23505 Frank Josselson, Esq.
One Southwest Columbia l
Portland Oregon 97258 Mr. H. E. Morris Bechtel Corporation P. O. Box 3976 San Francisco, California 94119 H. H. Phillips, Esq.
Corporate Counsel & Secretary Portland General Electric Company 2
121 Southwest Salmon Street Portland, Oregon 97204 Forelaws on Board c/o Lloyd K. Marbet 19142 S. Bakers Ferry Road Boring, Oregon 97009 Richard M. Sandvik, Esq.
Department of Justice 520 S. W. Yamhill Portland, Oregon 97204 Ms. Bernice Ireland Coalition for Safe Power Portad,bre 97220 i
i i
?
4
[;
-g.
I i
4
1)'l.
lccs(continued)
' William L. Itallmark, Esq.
Or,e Scuthwest Columbia Portland, Oregon 97258 Ka.hleen Shea, Esq.
Lcaenstein, Newman, Reis & Axelrad Suite 1214 1025 Connecticut Avenue, N. W.
Washington, D. C. 20036 Mr. J. Carl Freedman Box 553 Cannon Beach, Oregon 97110 4
Duke Pover Company ccs:
William L. Porter, Esq.
Mr. L. C. Dail, Vice President Asscciate General Counsel Design Engineering Department P. O. Box 33189 Duke Power Company P. O. Box 33189 Duke Power Company Charlotte, North Carolina 28242 Charlotte, North Carolina 28242 J. Michael McGarry, Ill, Esq.
Debevoise & Libennan 1200 Seventeenth Street, N.W.
Washington, D. C. 20036 William A. Raney, Jr.
Special Deputy Attorney General P. O. Box 629 Raleigh, North Carolina 27602 I
!!ary Apperson Davis, Chairman Yadkin River Committee Route 4, Box 261 Mocksville, North Carolina 27028 William G. Pfefferkorn, Esq.
2124 Wachovia Building Winston-Salen, North Carolina 27101 Elizabeth S. Bovers, Esq., Chairman Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Or. Donald P. deSylva Associate Professor of liarine Science Rosenstiel School of Marine and Atmospheric Science i
University of Miami Hiami, F1orida 33149 Dr. Walter H. Jordan 881 W. Outer Drive Dak Ridge, Tennessee 37830 l
9
a f
Mr. T. H. Ewing Mr. T. N. Ewing, Manager Black Fox Station Nuclear Project' Public Service Company of Oklahoma P. O. Box 201 Tulsa, Oklahoma 74102 cc:
Mr. Vaughn L. Conrad Andrew T. Dalton, Jr., Esq.
Public Service Company of Oklahoma 1437 South Main Street l
P. O. Box 201 Tulsa, Oklahoma 74119 Tulsa, Oklahoma 74102
[
Joseph R. Farris, Esq.
Paul M. Murphy, Esq.
Green, Feldman, Hall & Woodard Isham, Lincoln & Beale 816 Enterprise &;ilding One 1st National Plaza Tulsa, Oklahoma 74102 Suite 4200 Chicago, Illinois 60606 Sheldon J. Wolfe, Esq.
Atomic Safety and Licensing Board Joseph Gallo, Esq.
U. S. Nuclear Regulatory Commission Isham: Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue, N. W.
Suite 325 Dr. Paul W. Purdom, Director Washington, D. C.
20036 Environmental Studies Group Drexel University Dr. M. H. Robinson 32nd and Chestnut Streets Black & Veatch Philadelphia, Pennsylvania 19104 P. O. Box 8405 Kansas City, Missouri 65114 Mr. Frederick J. Shon Atomic Safety and Licensing Board i
Mr. Maynard Human U. S. Nuclear Regulatory Comission General Manager Washington, D. C.
20555 Western Farmers Electric Cooperative P. O. Box 429 Jan Eric Cartwright, Esq.
Anadarko. Oklahoma 73005 Attorney General 3
State of Oklahoma Mr. Gerald F. Diddle ATTN:
Charles S. Rogers, Esq.
General Manager 112 State Capitol Building Associated Electric Cooperative, Inc.
Ok-lahoma City, Oklahoma 73105 P. O. Box 754 Springfield, Missouri' 65801 Ms. Carrie Dickersen Citizens Action for Safe Energy, Inc.
P. O. Box 924
.C1aremore, Oklahoma 74107 Ms. Ilene H. Younghein 3900 Cashion Place Oklahoma City, Oklahoma 73112 i
w O
f E
Mr. J. E. Mecca
!:r. J. E. Mecca, Manager V. B. Deale. Eso.
Chairman Nuclear Licensing and Safety Atomic Saf ety 8. Licensi"o Board Puget Sound Power & Light Company V. S. Nuclear Regulatory Commission Puget Power Building Washington, D. C.
20555 Bellevue, Washington 98009 Dr. Frank F. Hooper, Mecter cc: fir. F. Theodore Thomsen Atomic Safety & Licensig Board Perkins, Coie, Stone, School of liatural Resources Olsen & Williams University of Michigan 1900 Washington Building Ann Arbor, Michigan 43109 Seattle, Washington 98101 Mr. Gustave A. Linenberger, Mecber l
g Mr. Robert Lowenstein Atomic Safety & Licensing Board Lowenstein, Newman, Reis U. 5. Nuclear Regulatory Comaission
~~
,j
& Axelrad Washington, D. C.
20555 Suite 1214 1*
1025 Connecticut Avenue, N. W.
Washington, D.C.
20036 R oger M. Leed, E sq.
Law Offices 1411 ath Avenue Seattle, Washington 98104 Mr. Lloyd K. Marbet c/o forelaws on Board 19142 South Bakers Ferry Road Boring, Oregon 97009 Mr. Nicholas D. Lewis, Chairman Energy Facility Site Evaluation Council 820 East 5th Avenue Olympia, Washington 98504 Honorable Richard Sandvik Department of Justice 500 Pacific Building 520 Southwest Yamhill Portland, Oregon 97204 e
9