ML20207T164: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 1,078: | Line 1,078: | ||
An important element of the applicant's model is the interruotion and the convective transport mechanisms by the disruption of core oeometry dur,ing | An important element of the applicant's model is the interruotion and the convective transport mechanisms by the disruption of core oeometry dur,ing | ||
. melt. Discussions focused on the nature of the mode'l and the sensitivity of its results to its underlying assumotions. Materials from the a*oplicants' presentation are included as Enclosure 3. , | . melt. Discussions focused on the nature of the mode'l and the sensitivity of its results to its underlying assumotions. Materials from the a*oplicants' presentation are included as Enclosure 3. , | ||
Questions arising in both meetings were formally submitted to tile applicant by letter dated October 23, 1986, from Steven M. l.ong to Robert J. Harrison. | Questions arising in both meetings were formally submitted to tile applicant by {{letter dated|date=October 23, 1986|text=letter dated October 23, 1986}}, from Steven M. l.ong to Robert J. Harrison. | ||
During a combined meeting of.the working groups at the end of the second dav, it was decided to publicly announce three additional meeting dates so that | During a combined meeting of.the working groups at the end of the second dav, it was decided to publicly announce three additional meeting dates so that | ||
[ additional discussions could be held, if necessary, durino the period when the NRC's review is nearing completion. The dates chosen were November 6, 12 and 19, 1986. | [ additional discussions could be held, if necessary, durino the period when the NRC's review is nearing completion. The dates chosen were November 6, 12 and 19, 1986. | ||
Latest revision as of 14:18, 5 December 2021
| ML20207T164 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/21/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Long S NRC, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19306D588 | List:
|
| References | |
| SBN-1237, NUDOCS 8703230271 | |
| Download: ML20207T164 (13) | |
Text
{{#Wiki_filter:. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
' SEABROOK STATION -
Engin:sring Offics New Hampshire Yankee Division ". November 21, 1986 SBN- 1237 T.F. B7.1.2, V2.2.1 [
. United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Steven M. Long, Project Manager
~ PWR Project Directorate No. 5
~
Division of PWR Licensing - A
References:
(a) Facility Operating License NPF-56, Construction Permit CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter, dated October 23, 1986, " Request for Additional Information for Seabrook Station, Units 1 & 2, Emergency Planning Sensitivity Study", S. M. Long to R. J. Harrison
Subject:
Emergency Planning Sensitivity Study
Dear Sir:
As requested, enclosed please find the information concerning Early Containment Overpressure Failures and a revised response to RAI 47 [ Reference (b)]. Very truly yours, b John DeVincentis Director of Engineering Enclosure cc: Atomic Safety and Licensing Board Service List B703230271 870313 PDR COMMS NRCC CORRESPONDENCE PDR P.O. Box 300 . Seabrook, NH 03874 . Telephone (603) 474-9574 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ J
I Dicni Curras,- Erquiro Peter J. Math:ws, Mayor
. M, ,. ' .Harsog & Weics
. City Hall 2001 S. Street, N.W. Newburyp3rt, MA 01950 i
' Suite 430 Washington, D.C. 20009 Judith'H. Mizner
- Silvergate, Gertner, Baker,
. Sherwin E. Turk, Esquire Fine, Good & Mizner Office of the Executive Legal Director 88 Broad St.
U. S. Nuclear Regulatory Commission . Boston, MA 02110. Tenth Floor Washington, DC 20555 Calvin A. Canney City Manager
. Robert A. Backus, Esquire City Kall 116 Lowell Street 126 Daniel Street P. O. Box 516 Portsmouth, NH 03801 Manchester, NH 03105 Stephen E. Merrill, Esquire Philip Ahrens, Esquire Attorney General Assistant Attorney General George Dana Bisbee, Esquire Department of the Attorney General Assistant Attorney General Statehouse Station #6 25 Capitol Street Augusta, ME 04333 Concord, NH 03301-6397 Mrs. Sandra Gavutis Mr. J. P. Nadeau Chairman, Board of Selectmen ~
Selectmen's Office RFD 1.- Box 1154- 10 Central Road Kensington, NH 03827 Rye, NH 03870 Carol S. Sneider, Esquire , Mr. Angie Machiros Assistant Actorney General Chairman of the Board of Sele.ctmen Department of the Attorney General Town of Newbury One Ashburton Place,19th Floor Newbury, MA 01950 Boston, MA 02108 Mr. nulliam S. Lord Senator Gordon J. Humphrey Board of Selectmen U. S. Senate Town Hall - Friend Street Washington, DC 20510 Amesbury, MA 01913 (ATTN: Tom Burack) Richard A. Hampe, Esquire Senator Gordon J. Humphrey Hampe and McNicholas 1 Pillsbury Street 35 Pleasant Street Concord, NH 03301 Herb Boynton) Concord, NH 03301 ( ATTN:
' Thomas F. Powers, III H. Joseph Flynn., Esquire L, Town Manager Office of General Counsel l Town of Exeter Federal Emergency Management Agency 10 Front Street 500 C Street, SW Exeter, NH 03833 Washington, DC 20472 Brentwood Board of Selectmen Paul McEachern, Esquire RFD Dalton Road Matthew T. Brock, Esquire Brentwood, NH 03833 Shaines & McEachern 25 Maplewood Avenue Gary W. Holmes, Esquire P. O. Box 360
- Holmes & Ells Portsmouth, NH 03801 47 Winnacunnet Road Hampton, NH 03842 Mr. Ed Thomas Robert Carigg FEMA Region I Town Office 442 John W. McCormack PO & Courthouse Atlantic Avenue
- Boston, MA 02109 North Hampton, NH 03862
- _ _ _ - . ._ . . - . . - _ _ . . ~ . _ . - - - . . _ . . _ _ _ _ _ . _ . _ . . - . . _ _.
. - bO'
' ~ *
- I Novemb:r 18, 1986 Page 1 of 6 SUPPLEMENTAL -INFORMATION REGARDING
, EARLY CONTAINMENT OVERPRESSURE FAILURE At a meeting on Wednesday, November 12, 1986, with the NRC and their contractor Brookhaven National Laboratory (BNL), certain assumptions regarding early containment failure, referred to as NUREG-1150 assumptions, were discussed. For scenarios which involved high pressure accident sequences where the RWST is not injected prior to vessel breach, a median probability of early containment failure on the order of 0.01 was indicated under these NUREG-1150 assumptions . , As discussed in Section 4.2.4 of the RMEPS report (PLG-0432) and presented at the meeting on November 12, 1986, our assessment of these assumptions indicates that they are not physically possible under the
.. specific geometric configuration of the Seabrook plant. We would, therefore, interpret the results of any analyses resulting from these-assumptions as a sensitivity study to explore the safety margins and the robustness of the conclusions submitted in the RMEPS report.
s-In this context, we would like.to submit the following information for ' your consideration. According to Figure 11.3-14 (attached), the containment pressure at which there is a 1 percent probability of containment failure is 163 psia. The solid curve for " wet" containment conditions is used because at this time in the accident sequence the temperature of the concrete containment shell has not increased significantly from the normal operating temperature, and it is actually lower than the temperature upon which the solid curve in Figure 11.3-14 is based. Thus, this curve can even be considered conservative for this evaluation. ! The dashed curve in Figure 11.3-14 shows the contribution to the total
- failure probability distribution which arises from gross (Type C)
- - containment failures. At 163 psia, it is concluded that the conditional
( probability of a Type C failure, given that the containment does fail, is L 2 x 10-4/0.01 or 0.02. Thus, the conditional probability of a Type B failure at this pressure is 0.98. Note that the same conclusion would be reached even if an arbitrary 1% strain failure criteria is adopted, since , the pressure at which a 1% deformation strain occurs is 190 psia, well above the 163 psia pressure for a 1% failure probability. 1
)
,,wr-- . , -- - - - - , - - , , ,,
_ . _ __._...u._.__. _ . . _ . . .. _a _ . ~ . __ ^~ 7' ' ' No'vember 18, 1986 Page 2 of 6 An early type B containment failure is represented in the SSPSA by release category S6BARV, by S6 in the RMEPS Study and by 56W in the WASH-1400 Sensitivity Study (PLG-0465). An early type C containment failure on the other hand would be represented by release categdry S1 in . the SSPSA and in RMEPS and by 51W in the WASH-1400 sensitivity study. The characteristics of accident scenarios in which the NUREG-1150 assumptions were applied, namely, high RCS pressure and no-RWST injection before vessel breach, are both explicitly represented by the plant damage state parameters, as shown in Figure 11.4-1 in the SSPSA. Plant damage states with numeral designators 3 or 7 meet these conditions. A consistent set of point estimate frequencies for both the plant damage states and the release categories is given in Table 4-2 in the WASH-1400 sensitivity study (PLG-0465), as follows: Plant Damage States 30 and 70 3.8(-5) Plant Damage States 3FP and 7FP 1.9(-5) Total numeral 3 and 7 Plant Damage States 5.7(-5) Release Category S1 5.2(-9) - Release Category S6 3.2(-7) g Assuming a 1% early containment failure probability, as described above, for the plant damage states with numerals 3 and 7 would result in an increase for release categories Si and S6 as follows: Frequency Increase for S1 = 5.7(-5) - (0.01) - (0.02) = 1.1(-8)/ year Frequency, Increase for S6. = Sq(-5) - (0.01) - (0.98) = 5.6(-7)/ year The new total frequency of these two release categories for this t NUREG-1150 sensitivity case would become:
"NUREG-1150" Frequency. of S1 = 1.7(-8)/ year "NUREG-1150" Frequency of S6 = 8.8(-7)/ year Thus, if all the weight is given to these NUREG-1150 assur.ptionr., the frequency of release category S1 would increase by a factor of 3.2 and
- the frequen'cy of release category S6 would increase by a factor of 2.8.
The impact of this change on the population risk is estimated in the two attached risk suninary tables. Table 1 represents the WASH-1400 methodology case from NUREG-0465 with the Seabrook specific containment
- failure characteristics as assessed in the SSPSA. Table 2 represents the i WASH-1400 methodology case combined with the NUREG-1150 assumptions for containment failure. Table 2 thus combines both the assumptions of the WASH-1400 source term methodology, as well as the NUREG-1150 assumptions
+ for early containment failure. It represents a very' conservative combination of two fundamental assumptions addressing the sensitivity of
- the results.
O o I
t y'r - ' '* J $ovember 18, 1986 Page 3 of 6 The results show that the NUREG-1150 assumptions regarding containment failure do not have a large impact on risk. The early fatality risk for the no evacuation case increases by 15%, due to the NUREG-1150 assumptions, and the risk decreases a little more slowly with etacuation distance. With a two mile evacuation, the risk of early fatalities is reduced to 2% of the no evacuation risk, whereas, for the the WASH-1400 case (Table.1), the two mile evacuation risk is 1% of the no evacuation risk. Overall, we conclude that the NUREG-1150 assumptions for containment failure do not have a large impact on the results and conclusions presented in the WASH-1400 sensitivity study (PLG-0465), with regard to risk or safety goals. Because of the rapid decrease in the early fatality risk with evacuation distance, it is anticipated that the conclusions with regard to the 200 rem curve are also not affected. Therefore, we conclude that: (1) The NUREG-1150 assumptions with respect to early containment failure are not credible in the context of the Seabrook specific design and configuration.
~
(2) Postulating these assumptions in the sense of a sensitivity analysis would not have a large impact on the results presented in the WASH-1400 sensitivity study. (3) All of the conclusions with regard to emergency planning would ' still be valid. l S
I
. . _ . , . ~ - . . - . - . .. -- - . . . . .:.... I
*jr- .
- j
'A
[ TOTAL FAILURE
- PR ESSUR E:-
;g
*.*..*.. == # ~ ~
/
y- /* BENIGN (TYPE 8)
~
. / / FAILURE -WET
/ / SEQUENCES
. / /
. /
[ /
/
/ oRoss (TYPE cs failure . WET
/ SEQUENCES l /
- l
~
l / l /
/
488// g to8 _ . s -
. /
3 : /
* -! /
.E a
/ -
y i -: I 8- : . c ,.< +!
- I i
- l 1
-: I i I -f
-mb2x/0
' I so" =- l l
" l
/
/
l .f69 M'E
s ' / ' ' ' ' ' '
i4o e iso zoo 22o 24o neo PM ESSUR E (PSIA) FIGURE 11.3-14. COMPOSITE CONTAINMENT FAILURE PROBABILITY DISTRIBUTIONS FOR BENIGN FAILURE, GROSS FAILURE, AND TOTAL FAILURE ' (FROM SSPSA PLG-0300) i 11.3-42 t
e .
= = = = = m = = = = a m m m m m m = = m = = = us m = = = z = = m = m a = = a n = as a a m m as m as = = a m as = = m as u m m m m m m m m m = m = m a m a = a m as's = = = m m m m m m m m m m m m as ., . . . .
RELEASE EVAC EARLY TOTAL -- ABSOLUTE RISK -- - PERCENTAGE RISK .4 - RUN CATEGORY DIST FREQUENCY FATAL'ITY CANCERS FATALITY CANCER FATALITY CANCERi
==================================================================================================mmt" NO EVACUATION CASES --- CONSEQUENCES --- ---- NEAN RISK ---- - PERCENT OF' RISK - .
I 447 S1W O 5.2E-09 '745.6 940.1 3.9E-06 4.9E-06 0.1 f. ..O 453 S2W O 2.OE-05 122.1 699.1 2.4E-03 1.4E-02 91.1 96.4 f 455 S3W O 1.4E-04 0.0 0.7 0.OE+OO 9.BE-05 0.0 0,7 j. 452 S6W O 3.2E-07 734.3 1285.5 2.3E-04 4.1E-04 8.8 2.8 I 454 S7W O 3.9E-08 0.0 14.2 0.OE+00 5.5E-07 0.0 .'O* S5 HAT O 1.1E-04 0.0 0.1 0.OE+OO 1.1E-05 0.0 0.1 i TOTAL 2.7E-04 . 2.7E-03 1.5E-02 100.0 '100.0 3
================= ========================== ==========================================m=====m==m==m
- ONE MILE EVACUATION CASES --- CONSEQUENCES --- ---- MEAN RISK ---- - PERCENT OF RISK -
447 S1W 1 5.2E-09 745.6 940.1 3.9E-06 4.9E-06 1.1 .O 456 S2W 1 2.OE-05 9.4 659.8 1.9E-04 1.3E-02 51.4 96.2 J 455 S3W 1 1.4E-04 0.0 0.7 0.OE+00 9.8E-05 0.0 0.7 I 457 S6W 1 3.2E-07 541.9 1264.9 1.7E-04 4.OE-04 47.5 3.0 - . 454 S7W 1 3.9E-OB O.O 14.2 0.OE+00 5.5E-07 0.0 .O
- SSHAT 1 1.1E-04 0.0 0.1 0.OE+00 1.1E-05 0.0 0.1 1 TOTAL ; 2.7E-04 3.6E-04 1.4E-02 100.0 100.0 i =========================b=====================================================================m==m.
j TWO MILE EVACUATION CASES --- CONSEDUENCES --- ---- MEAN RISK ---- - PERCENT OF RISK - , 447 S1W 2 5.2E-09 745.6 940.1 3.9E-06 4.9E-06 16.1 0.1 q ! 459 S2W 2 2.OE-05 0.0 440.4 0.OE+00 8.8E-03 0.0 95.3 4 455 S3W 2 1.4E-04 O.O O.7 O.OE+00 9.8E-05 O.O 1,.1 450 S6W '2 3.2E-07 63.3 986.5 2.OE-05 3.2E-04 83.9 3.4 454 S7W 2 3.9E-08 0.0 14.2 0.OE+00 5.5E-07 0.0 .O S5 HAT O 1.1E-04 0.0 0.1 O'.OE+00 1.1E-05 0.0 0.1 . j --------____-_---___------___--------_-----__--------------_-_--__-----_--_----- -_==--- - ----
; TOTAL 2.7E-04 2.4E-05 9.2E-03 100.0 100.0 ' --- =================================================================================,,=============
l --------- TOTAL RISK BY EVACUATION DISTANCE =-
- PERCENTAGE RISK -
I -- ABSOLUTE RISK --
- FATALITY CANCER FATALITY CANCER
-------------------------------------------=--- ==-
i TABLE 1. Risk Summary for the WASH-1400 Sensitivity Study (PLG-0465) NO EVAC 2.7E-03 1.5E-02 100.0 100.0 1 MI EVAC 3.6E-04 1.4E-02 13.6 94.5 Point Estimate Frequencies 2.4E-OS 9.2E-03 0.9 63.7 2 MI EVAC
====================================================m.
e
==================================================================UTE EARLY TOTAL -- ABSOL ===============================k RISK -- - PERCENTAGE RIS RELEASE EVAC CANCER; DIST FREQUENCY FATALITY CANCERS FATALITY CANCER FATALITY RUN CATEGORY =================================d
==================================================================N--- CONSEQUENCES --- ---- NEA RISK ---- - PERCENT OF RISK -- j NO EVACUATION CASES __----_---_-------=_ ----------------_--_---_ ---_- -
1.7E-OB 745.6 940.1 1.3E-05 1.6E-05 0.4 t, @.1 1 447 S1W O 78.7 91.8 O 2.OE-05 122.1 699.1 2.4E-03 1.4E-02 453 S2W 9.8E-05 0.0 0.6 S3W O 1.4E-04 0.0 0.7 0.OE+00 455 1.1E-03 20.8 7 '.'4 S6W O 8.8E-07 734.3 1285.5 6.5E-04 452 O.OE+00 5.5E-07 0.0 .O 454 S7W O 3.9E-08 0.0 14.2 S5 HAT O 1.1E-04 0.0 0.1 0.OE+00 1.1E-05 0.0 0.1 __=---
- - - - = _ _ _
------------------------------------------------------------------------------------100.0 TOTAL 2.7E-04 3.1E-03 1.5E-02 100.0j
=============================' '
=======================================================================K
--- CONSEQUENCES --- ---- MEAN RIS ---- - PERCENT OF RISK -
ONE MILE EVACUATION CASES -------------------------- +
---------------------------------------------------------------------- 1.9 0.1 1.7E-08 745.6 940.1- 1.3E-05 1.6E-05 447 S1W 1 27.7 91.4, 2.OE-05 9.4 659.8 1.9E-04 1.3E-02 456 S2W 1 0.0- O.7 ?
l 1.4E-04 0.0 0.7 0.OE+00 9.8E-05 455 S3W 1 70.4 7.7 :1 8.8E-07 541.9 1264.9 4.8E-04 1.1E-03 457 S6W 1 0.0 .O I 3.9E-OB O.0 14.2 0.OE+00 5.5E-07 454 S7W 1 1.1E-05 0.0 0.1.! SSHAT 1 1.1E-04 0.0 0.1 0.OE+OO -.-----
----------------------- --------------_ -==---------------------------------- _ _ - - - _ .
6.8E-04 1.4E-02 100.0 100.0 TOTAL 2.7E =a============================.
======================================================================ISK TWO MILE EVACUATION CASES --- CONSEQUENCES --- ---- MEAN R ----
-PERCENTOFRISK-f
---------------- ------------------------------------940.1 __ _ ==---------------------------------
1.3E-05 1.6E-05 18.5 0.2 l 447 S1H 2 1.7E-OB 745.6 0.0 89.9 2.OE-05 0.0 440.4 0.OE+00 9.8E-03 459 S2W 2 0.0 0.7 0.OE+00 9.BE-05 0.0 1.0 ' 455 S3W 2 1.4E-04 81.5 8. 9 , 2 8.8E-07 63.3 986.5 5.6E-05 8.7E-04 458 S6W 5.5E-07 0.0 .O 454 S7W 2 3.9E-08 0.0 14.2 0.OE+00 O 1.1E-04 0.0 0.1 0.OE+00 1.1E-OS. O.O O.1 [ SSHAT 6.8E-05 9.8E-03 100.0 100.0 TOTAL 2.7E-04 ==============g3==============
====================================================================== ------ -- TOTAL RISK BY EVACUATION DISTANCE ----------
--------==__-_:-----------------------------------------
' -- ABSOLUTE RISK -- ' - PERCENTAGE RISK -
FATALITY CANCER FATALITY CANCER' TABLE 2. Risk Summary for the WASH-1400 ------------------------------------------------------ Sensitivity Study Combined with 3.1E-03 1.5E-02 100.0 100.0 NUREG-1150 Assumptions for Early NO EVAC 1 MI EVAC 6.8E-04 1.4E-02 21.8 94.7 Containment Failure 9.8E-03 2.2 64.3i 2 MI EVAC 6.8E-05
======= ==============================================
. u--.. . -. . . . - . . . .. _ , . . _ - __ __ _
, to 7.- .
- 7. 5?- ... .
RAI 47
Address the risk from creep failure of the steam generator (S/G) tubes due to exposure to high temperatures during core melt sequences
- in which the reactor coolant system (RCS) remains at high pressure and the secondary sides-of the S/Gs are dry. Your discussion should reflect-the recent experiments and modeling ef forts that show 3-dimensional convective flows which transfer heat from the overheating core to other places within the RCS, _particularly into the upper plenum and from the upper plenum along the hot legs into the S/Gs and through the U-tubes.
Also include the influence of pressure driven flows resulting from reactor coolant pump (RCP) seal-LOCAs, PORV/ safety valve actuations,
" bumping" the RCPs, etc. Localized heating ef fects due to redistribution of fission products in the RCS should be included. ; s. What is the total probability of occurrence for the high RCS pressure core melt sequence with dry S/Gs?
- b. What is the estimated conditional probability that the S/G tubes will fail due to overheating before the pressure is relieved by failure of the RCS elsewhere?
- c. What is the ef fect of preexisting S/G tube leakage (within technical-specifications) on .che heating rate and temperature required for failure of the leaking tube (s).
- d. What release category would creep failures of the S/G tubes result in?
RESPONSE 47 The risk from creep failure of steam generator (SG) tubes is very small for the following reasons:
. o The frequency of high pressure core melt with dry steam generators s is very small.
o Given the postulated occurance of a high pressure core melt
.' with dry steam generators, creep rupture of the SG tubes is not M a credible failure mode.
- I
,' o A large number of tubes must f ail to produce an early large containment bypass. -
A simple sequence diagram in Figure i shows that three failures must occur for containment bypass to occur as a result of a high pressure melt seq uence. The three failures are (1) failure to recover water to the SG, (2) f ailure to depressurize primary system and (3) creep f ailure '. of SG tubes. Success of any one of these three ensures success (no SG tube creep failure). O
s a >
, ? r-
. ; .e .
' The potential for creep failure of the steam generator tubes for core melt
-dequences in which the steam generators are dry was evaluated using the
' best tools available including the MAAP 3.0 computer code developed in the IDCOR program. As a result of the technical issue resolution i I
process between IDCOR and the NRC, this code includes models for the ! natural circulation flows between an overheated core, the upper plenum, the hot legs and the steam generator tubes. The analytical updels used
' in the MAAP PWR program have been benchmarked with the recent published experiments carried out at Westinghouse under EPRI sponsorship. In addition, these analyses also include the influences of PORV/ safety valve actuations, as well as models for fission product release, transport ,
deposition and localized heating. Several variations of station blackout sequences were consicered: all assumed f ailure of main and emergency feedwater such that the secondary sides of the steam generators remained dry. The sequences studied include: (1) no RCP seal LOCA or manual PORV actuations (2) a 50 gpm per pump seal LOCA with no manual RCS depressurization (3) manual RCS depressurization when the core outlet temperature equals 12000F, and (4) several uncertainty analyses on key physical parameters in the system models. These analyses indicated that the steam generator tubes would not be subject to a sufficient temperature increase to result in creep rupture before failure of the reactor coolant system. In particular, since the secondary side temperature is limited to about 7000F due to L thermal inertia of the SG shell and heat losses to the containment , the SG tube temperatures only achieve temperatures of about-iiGG^2.~ This 700'I i is far less than that required for creep rupture. Based on information j provided in Appendix B of the attached draft report, creep, rupture of the SG tubes would not be expected. These conclusions are valid for all of the sequence variations considered as well as all of the uncertainties considered in the analysis which include variations in the core eutectic formation and slumping behavior, flows through the steam generator tubes, etc. l During station blackout sequences, the Seabrook operating procedures require ! that the operators monitor the f unctional restoration guidelines. These l guidelines would first lead the operator to consider restoration of l reactor coolant system inventory control which would be met with the , discovery that no electric power is available for this postulated sequence. Subsequently,,the restoration guidelines would lead the operator to consider procedures for restoration of a RCS heat sink. l The procedure for loss of heat sink calls for manual depressurization of the primary system using the PORVs. While this procedure is not specifically implemented for station blackouts and is only monitored, if new evidence subsequently turns up to support the view that creep rupture is a credible failure mode, the station blackout procedures 4 could be changed to require some appropriate method of RCS depressurization. The preferred method would be to blow down the secondary side of the steam generators using the SG PORVs. Such action would permit introduction of steam generator cooling via the firewster pumps (diesel driven). An alternative method would be to depressurize the primary system using the pressurizer PORVs. With such an action, the pressure difference imposed on the entire primary system pressure boundary is dramatically reduced, thereby eliminating any potential for creep rupture f ailures. I
- - , - - - , , --e -,n.,- , ,,,---n--_----.--_ _ - . -_..--,,-,_n... , _ - - . _ . .---..-.,__~.,,-__n. - - . , . . . - , , , , ~ - - , - . .
.A ' ?. F , ,. . ; .'.' ,
The action of " bumping" the RCPs cannot be accomplished without the return of offsite power. If one postulates of f site power being returned, the
- operator would first' rest' ore ECCS systems. This action alone will recover ;L core cooling and make bumping the RCPs unnessary.
- In sunmaary, extensive NAAP 3.0 analyses, which includes models for the pro-cesses in question, were carried out in response to this question. These -
analyses show that the steam generator tubes would not be threatened by the creep rupture mechanism due to either the natural circulation flows between the core, upper plenum, hot legs and steam generators or the pressure driven flows resulting from RCP seal LOCAs or manual RCS depressurization. Also, the calculations show that localized heating ef fects due to fission I product deposition are not sufficient to increase the temperature of the steam generator tubes to a level where creep rupture would be 1 anticipated. Consequently, if any such mechanism were anticipated, it would occur elsewhere in the primary system long before the steam generator tubes would be threatened. The mean annual frequency of early high pressure core melt sequences of interest is approximately 4.5 x 10-5 events per reactor-year. PDS Mean Annual Reference Frequencies i. 1.5 x 10-5 RMEPS Page 3-58 3D 8.9 x 10-6 RMEPS Page 3-60 i - 3FP 1.4 x 10-5 RMEPS Page 3-61 4A. SSPS A Page 13.1-28 1.7 x 10-7 ' 4C, 4D 2.8 x 10-6 SSPSA Page 13 1-28 4E 2.2 x 10-II SSPSA Page 13 1-28 1.2 x 10-7 SSPS A Page 13 1-28 4FP 8A 3.9 x 10-6 RMEPS Page 3-66; sequences 8A-27 through 30 and 8A-34 4.5 x 10-5 through 37 There are many specific accident sequences that comprise the above plant damage states. These sequences broadly include transient and loss of of fsite power sequences with failure of main and emergency feedwater and failure or inability to feed and bleed and transient without scram sequences. The above results for PDS 8A consist of 8 sequences involving station blackout and emergency feedwater f ailure in which ef forts to recover containment heat removal states are successful. In the containment i event tree analysis, all the "A" are assigned a high chance l of no containment f ailure, the "C" and "D" states a high chance of long term overpressurization, the "FP" states a high chance of small bypass
! and the "E" states a high chance of large bypass. Hence, in terms of relative consequences, the " A, C and D" states would experience the l'
greatest increase in consequences if a SG tube failure were assumed to result from creep failure during high pressure melt sequences. I
!_,_ ~ - , _.-_,. .,_.__,._.,_,,u,,..-,,,,,-_,,___,,_, _.____~,,___,,.,,,,,,_,_,.,__,,_____,.-,__d___________
_ .. .__ .- - .. _ _ . - - . __. ._ .~
. tv IN - ,Egely'digh pecssura s:quenc:s cro of intorcst b:ccusa s:quencas with energency feedwater failure (i.e. dry S/Gs) are modeled as early melts fi.e. plant damage states 3 and 4). The one exception applies to 8 sequences in RMEPS where cont,ainment heat removal recovery _was considered.
- ' These particular recovered sequences were assigned to PDS 8A. PDS 3F
' and 4y are not of interest because a large containment bypass (release category 56) already exists. PDS 3FP and 4FP are not of interest.
because a release path (S2) already exists. , , a l The above frequency of early high pressure core melt is conservative for three reasons. '
- 1. There are still potential recovery actions to ensure wet S/Gs not yet considered. For example, the dominant sequence (3D-1 on RMEPS page 3-58) involves a loss of sain feedwater transient and failure of the solid state protection system (mean annual frequency = 8.3 x 10-6). Solid state protection system f ailure is assumed to result in no auto initiation of safety equipment such as emergency feedwater. Emergency feedwater and other safety equipment can be started manually from the Control Room but these actions were conservatively neglected in the PSA.
- 2. There are early high pressure melt sequences with wet S/Gs in some of these plant states (i.e. emergency feedwater available and operating). For example, sequence 3D-4, a non-recovered station blackout and the operators don't depressurize S/Gs. Other such sequences include 4A-2 and 3, and 3A-29. (Exclusion of these sequences would not signif-icantly reduce the total estimated above).
y
- 3. No credit is taken for operator actions to manually depressurize which '
reduces pressure (i.e., riot high pressure core melt). Also, there is some chance the PORVs may fail to close. , 1 i The analyses indicate that the steam generator tube temperatures and the hot legs are both well below the levels where creep rupture would occur. In addition, it is likely that the operator would be instructed to manually depressurize the RCS when the core oa'elet temperature exceeded 12000F. This action would decrease the primary system pressure such that the stresses on the stesa generator tubes and the hot legs would both be reduced to levels less than that observed under normal operation. Consequently, the estimated conditional f requency that the plant conditions 1 for the hypothesized creep rupture of steam generator tubes would occur is dependent upon the likelihood that the operator would fail to manually ! depressurize the primary system. With modified procedures and adequate ' training, the frequency of operator failure to depressurize could be i reduced below 10-Z to 10-3 per demand. This would lower the frequency of creep failure potential conditions to the 10-7 to 10-8 range.
~
Given the occurrence of these conditions, the probability of creep rupture is a matter of our state of knowledge about the laws of physics that govern heat transfer to the SG tubes as opposed to a statement about. the relative frequency of a random process (which we make about the likelihood of achieving the necessary plant conditions in terms of l " frequency"). Due to cooling of the steam generator tubes by,the secondary side steam, the SG tube temperatures are well below (approximately l 700 Y ^0G4 6v r) that required for creep rupturet Due to the very strong dependence of creep rupture on temperature, 7 this consideration means ! that creep rupture would not occur even if high pressures are maintained. l _ i #%og )m,g ,, novcas o oc catre,q pcecte % Ca$c Cen@ red . m v _ r.- -e-.- n,,w.m._,.,~,m. -,e ,_ m.,_, _ _ _ _ _ ,.m.,.,m-
_~ ~ - -. 1,4 .
* [.
Despite the uncertainties in our models and data,'we are quite confident that errors as large as several hundred degress on the low side of the correct valve are not credible.3 To express our confidence in the models and data, we assign a 99% chance that failure of SG tubes will not occur before reactor vessel melt through or piping nozzle failure. The effect of a pre-existing steam generator tube leakage (within technical specification - 1 gpm per steam generator), would be a small flow rate compared to that created by the 50-gallon per minute flow assumed for the i pump seal I.0CA case. Since the major influence of an additional flow would be to provide higher temperatures in the steam generators, this is bracketed by the results of the pump seal LOCA case which showed no major influence on the steam generator tube temperatures. Given the assessment of the primary system response, potential for creep rupture of the steam generator tubes is extremely unlikely. Consequently, no specific calculations were carried out for the actual release categories since it is not risk significant. If specific questions were to arise regarding such releases, these would be analyzed with the MAAP 3.0 PWR code. If one postulates creep rupture failure of steam generator tubes, the pressure inside the previouly dried out and isolated stream generator secondary side
!- would increase until the steam generator PORVs setpoint is reached at I which time these valves would lif t and modulate until reator vessel melt 7
through occurs and the RCS depressurizes into the cone.ainment. There are no ' existing release categories / source terms analyzed for Seabrook or other PWR plants that adequately represent this scenario. During the periods of SG PORV opening, there would be a high leak rate bypass condition directly' from the RCS to outside the containment. However, after vessel melt 1 through, the leak rate out this path would be low corresponding to any low pressure leakage through the reclosed PORV. This leak path could be enhanced if the SG safety valves also lif t and f ail to reseat properly; however, it is believed unlikely that the safety valve setpoint would be reached. If a source term were developed for this scenario, it would i probably resemble S2 with the addition of an early puf f to cover the relief valve opened period of the release. Depending on the sequence, there may or may not be a long term overpressurization component to ,
- the source term.
I i
'd*"
l /e doWJ & nefed M in o" case sen- re'*%)r % i vnce.wg analysce kmpemb<n wem minw ed in te h Sb f gene <a b s, N b the. het (e.1 p;g eas pn ac4ec) l to M by enep<upfue wh;le sb,n genereder % . I fe.mpe.ralv. es redned wh Ica, A values Aqved h M h CCC#. Dep<nw when c4 %. p,.c.
- sys km S e e g h o W 1- I q AW wed eVWn QMee(n$ $r NE 6 NOM gene f* .
_..7...,...,
.. . _j. .
.. .? *. .
3,
- c. EABROOK STATION
- Engineering Office
'"$1iENLa5 ') ,
e amm J ua Pubuc Service of New Hampshire New Hampshire Yankee Division November 24, 1986 SBN-1241 T.F. B7.1.99, B7.1.8 United States Nuclear Regulatory Commission Washirigton, DC 20555 Attention: Mr. Vincent S. Noonan, Project Director . PWR Project Directorate No. 5 '
References:
(a) Facility Operating License NPF-56, Construction Permit CPPR-136, Docket Nos. 50-443 and 50-444 '
Subject:
Seabrook Station Probabilistic Safety Assessment (SSPSA) Update .
Dear Sir:
This letter is to inform you that New Hampshire Yankee -(NEY) is proceeding on a schedule to file a request related to emergency planning process options prior to the end of 1986. i We request, therefore, that all steps be taken to continue the L NRC's review of our technical submittal. It would be very helpful to l have the results of the NRC's review prior to our formal filing. 4 t Very truly yours, l John DeVincentis Director of Engineering i j cc Atomic Safety and Licensing Board Service List ~ 8612h0594861124 3 l PDR 3 DOCK 0500 F I.od
'Ro ,
. .g _ .. g ,
--.w -.. . - . ,. . , . .
*^
(( - Diane Curran, Esqu1(~ Peter! Mathews , Mayor Harmon & Weiss City Hall
~~
'2001~S. Street, N.W. Newburyport, MA 01950 Suite 430 Washington, D.C.
20009 Judith H. Mizner 4 . Silvergate, Gertner, Baker, Sherwin E. Turk, Esquire _ Fine, Good & Mizner -
~
Office of the Executive Legal Director 88 Broad St. - U. S. Nuclear Regulatory Commission Boston, MA 02110
- Tenth Floor Washington, DC 20555 Calvin A. Canney City Manager Robert A. Backus, Esquire City Hall
, '116 Lowell Street . 126 Daniel Street P. O. Box 516 Portsmouth, NH 03801 Manchester, NR 03105 Stephen E. Herrill, Esquire l Philip Ahrens, Esquire Attorney General l Assistant Attorney General George Dana Bisbee, Esquire i Department of the Attorney General Assistant Attorney General Statehouse Station #6 25. Capitol Street i Augusta, ME 04333 Concord, NH 03301-6397 Mrs. Sandra Gavutis Mr. J. P. Nadeau - Chairman, Board of Selectmen Selectman's Office RFD 1 - Box 1154 10 Central Road Kensington, NR 03827 Rye, NR 03870 Carol S. Sneider, Esquire Mr. Angie Machiros Assistant Attorney General Chairman of the Board of Selectmen Department of the Attorney General Town of Newbury - One Ashburton Place,19th Floor Newbury, MA 01950 Boston, MA 02108 Mr. William S. Lord Senator Gordon J. Humphrey Board of Selectmen U. S. Senate Town Hall - Friend Street Washington, DC 20510 Amesbury, MA 01913 ! (ATTN: Tom Burack) Richard A. Hampe, Esquire Senator Gordon J. Humphrey Hampe and McNicholas 1 Pillsbury Street
- 35 Pleasant Street .
Concord, NH 03301 Concord, NR 03301 ( ATTN: Herb Boynton) 7 Thomas F. Powers, III H. Joseph Flynn, Esquire Town Manager . Office of General Counsel Town of Exeter Federal Energency Management Agency 10 Front Street 500 C Street, SW Exeter, NE 03833 Washington, DC 20472 Brentwood Board of Selectmen Paul McEachern, Esquire RFD Dalton Road Matthew T. Brock, Esquire Brentwood, NR 03833 Shaines & McEachern 25 Maplewood Avenue l Cary W. Holmes, Esquire P. O. Box 360 l Holmes & Ells Portsmouth, NH 03801 47 Winnacunnet Road Hampton, NH 03842 Mr. Ed Thomas Robert Carigg FEMA Region I Town Office 442 John W. McCormack PC & Courthouse Atlantic Avenue ' Boston,_MA 02109 North Hampton, NH 03862
. s, .
~ -
Mainistrative Judge Helen Hoyt, Chairperson Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Administrative Judge Sheldon J. Wolfe, Chairman Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Esmeth A. Luebke Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1 Dr. Jerry Harbour Atomic Safety and Licensing Board Panel
- U.S. Nuclear Regulatory Commission l
Washington, D.C. 20555 - 4 1 e e l 4 f 1 i 9
a = d' ne. ( ( 7 UNITED STATES
! o NUCLEAR REGULATORY COMMISSION 3 y gI wasumaTom, p.c.aossa
%..... 2 5 NOV 1986 Docket No.: 50-443 APPL.ICANT: Public Service Company of New Hampshire FACII.ITY: Seabrook Station, Unit 1
SUBJECT:
SUMMARY
OF MEETING HEl.D ON NOVEM8ER 12, 1986 TO DISCUSS SEA 8 ROOK EMERGENCY Pl.ANNING SENSITIVITY STUDY
REFERENCE:
Seabrook Station Risk Management and Emergency Planning Study and Seabrook Station Emergency Planning Sensitivity Study. Submitted by letter from John DeVincentis to Vincent Noonan, dated July 21, 1986. A publicly noticed meeting was held on November 12, 1986, at NRC offices in Bethesda, Maryland. The NRC staff was represented by members of the Office of Nuclear Reactor Regulation, and Brookhaven National 1.aboratory. The Applicant was represented by members of the Public Service Company of New Hampshire, Pickard, l. owe and Garrick, Inc., Fau'ske & Associates and Westinghouse Electric Corporation. A list of attendees is included as Enclosure 1. .. The purpose of the meeting was to discuss issues affecting the level of confidence in PSNH's conclusions that could be established by Brookhaven's review of the referenced documents. The discussions' focused on the dose probability vs. distance parameterization of public risk. It was agreed that the region of interest lay in the distance range of a few miles and the probability range near the values shown by NUREG-0396 for a distance of 10 miles. (The PSNH results ghow the risk at 1 mile from Seabrook to be below the NUREG-0396 value at 10 miles.) BNI analyses are not yet complete enough to determine whether explicit differences identified in their review would challenge the PSNH conclusions, but those differences that have been quantified to date have not negated the PSNH conclusion. . There was also a discussion concerning confidence that all significant risk contributors have been identified and quantified. Because the Seabrook study resulted in reducing the overall risk by reducing the estimates for several
- known risk contributors, the question was raised as to whether other events that may have been neglected in previous studies because of low probabilities I might still have probabilities high enough to be significant contributors to j the Seabrook results. There was some confidence tentatively expressed by 1
Brookhaven personnel that all risk contributors significant to the region of interest delineated above had been identified. However, there may be some i difficulty in adeouately quantifying some of the potentially significant risk contributors.
%).2A O$5b t
BbPP- .
T _ _ . ~ . - . - - - - - - b . 4' ( (
~2-One potentially significant risk contributor not included in the referenced study is rupture of steam generator tubes during core melt due to convective transport of heat from the core to the steam generators. This was the sub.iect of an earlier meeting at Brookhaven on October 17, 1986. An additional presentation on this subject was made by Fauske & Associates personnel during the current meeting. Their conclusion was that the tubes would not reach temperatures high enough to cause creep failure. Copies of the slides from this presentation are included as enclosure 2.
2 The final topic of the meeting was a presentction by Westinghouse personnel concerning the potential for direct containment atmosphere heating by high pressure ejection of core debris at the time of vessel failure. Physical modeling results were presented for the Zion plant configuration to demonstrate that the fraction of the ejected debris that was aerosdlized ranged from 0.003 to 0.052. The slides from this presentation are included as Enclosure 3.
/ [ ,3 w StevenM.l.ong,ProjehManager PWR Project Directorate No. 5 Division of PWR l.icensing-A 4
~
- 4. -
.Y (- (-
ENCt.0SURE l' MEETING ATTENDANCE Steve I.ong NRC Vincent S. Noonan NRC Goutam Bagchi NRC Trevor Pratt 8NI.
~
Bob Youngblood BNI. Mohen Khatib-Rahbar BNL Warren f. yon NRC/DPl.A/RS8
' Scott Newberry NRC/DPl.A/ FOB Victor Benaraya NRC/PAF0 Don Hickman NRC/PAF0 John DeVincentis NHY/ENG R. E. Henry Fauske & Assoc. Inc.
Fred Torri - Pickard,l. owe & Garrick, Inc. Jim Moody NHY Karl Fleming Picard, l. owe & Gai rick, Inc. David A. Maidrand Asst. Pro.j Mngr - YNSD R. J. l.utz, Jr., Westinghouse Electric Keith Woodard Pl.G Marc Kenton Fauske & Assoc. Bill Sanchez , NHY Engineering Sarah Davis NRC/DSR0/RRAB Richard Barrett NRR/DSR0/RRAB Robert E. Sweeney NHY 8ethesda Office i.eonard Soffer . NRC/NRR/DSR0 Ernie Rossi NRC/NRR/PWR-A i i.. . - , . _ ~ _ . . _ _ _ _ ____ ____.,_ _ _ . _ ,_.__ _ ___. _ . _ . _ , . . _ _ _ . _ . _ - _ _ _ . _ _ _ _ , . -
ENCLOSLSE 2 e - (:... MAAP ANALYSES TO ASSESS THE POTENTIAL FOR TEMPERATURE-INDUCED STEAM GENERATOR FAILURES 1, No Operator Action a, Base Case, b, . Seal LOCAs,
- 2. Operator Action a, With turbine-driven AFW (not shown-sequence does not progress),
b, . With failure of AFW and manual depressuri-zation of primary system when core tempera-tures reach 1200*F,
- 3. Uncertainty Analyses of Base Case
, c. High core melting temperature (3000 K),
- b. High core-upper plenum flow (low friction l factors), .
. c. Low steam generator flow (low fraction of tubes carrying flow away from inlet plenum),
- d. Stuck-open secondary relief, i
- e. No core blockage,
\ . l . _ _ . - . - _ _ _ _ _ - _ _ - -. . .
. . _ = .. _ _ _ - _ _ _
4
*5 '
PEAK SG INLET PLENUM GAS TEMPERATURE AT MAXIMUM AP (*K)
- 1. Base case 860
- 2. ' Seal LOCA 865 3, Manual depressurization 680
- 4. High eutectic temperature 880
- 5. High upper plenum flow 870
,6.. Low SG flow 980
- 7. Stuck secondary relief 850 ,
- 8. No blockage . 1040 i .
i e 4 L J
4, 1 e' (i CALCULATION OF STEAM GENERATOR TUBE TEMPERATURES
- 1. MAAP calculates primary side gas temperatures at inlet to SG tubes and overage SG tube wall temperatures, ,
- 2. To calculate peak SG tube wall temperatures, need to. compute the ratio of 'the heat transfer coeffi-cients on the primary side of the tube to that on the secondary. .
- 3. Both heat transfer coefficients are driven by the difference in temperatures near the inlet of the tubes carryincJ out flow compared to temperatures elsewhere; thus can efficiently use scalin9 argu- ,
ments to compare them, 1 . E
< J t
- . . . - . . - .- .-.u_. . . . - . . .- -
(. ( CALCULATION OF STEAM GENERATOR TUBE TEMPERATURES (cont'd)
- 4. Primary side flowrote given by (see FAI/86-39 for nomenclature)
Wf=pfgp D ga (1 - a)2
= 3.4 kg/sec at time to peak gas inlet temperatures (vs. MAAP:3.3)
- 5. Secondary side flows given by similar expression; ratio of heat transfer coefficients is then:
~ 2' i
~.9 -
1
( i. CALCULATION OF STEAM GENERATOR TUBE TEMPERATURES (cont'd)
- 6. For approximately ecual heat transfer coefficients, tubs temperature is the average of the primary and secondary side gas temperatures, -
4 i I l . d E
~
-. . . _ _ _ . . _ _ _ . ~ . _ _ , _ - _ _ . _ _ _ _ _ _ ___. _ _ _ _ , _ _ . - . . . _ _ _ _ _ _ _ . -
4 (. i . l- T, - L 5 n a 3 1 V m , m Tp .. inlet outlet plenum plenum i e t
- j e .
i ,i l Natural circulation flows on the inside y
! and outside of a tube carrying fluid I from the inlet to the oQtlet plenum.
[. l
, - - . . . , , . - - - . . , _ . . . . - - . - - . _ . - , . . . . . - .-..___-_.,_,,...m.. _,_______m. _ . , _ , , , _ , , _ ,,__.,.,,_m_
-.yg,9.6 ,6w*P- 4 SON 4*+* '* * '
( ( l f '
)
STEAM GENERATOR TUBE STRUCTURAL INTEGRITY
- 1. Tube Degradation 1.1 Property Evaluation 1.2 Thinning and Cracking l.3 Denting 2.',
Creep Rupture 1.1 Property Evaluation ,. 1.2 Quantification and Conclusions - l3
. . - - . . . - . . - ~ . . . . . . . . _ . . . . . - - . - .A - - .
lc - (- ( l PROPERTY EVALUATION FOR TUBE DEGRADATION e Flow stress proportional to yield stress + ultimate stress for ductile fracture, e Flow stress ratio ef(T) , ey(T) + "u(T)
- f. o l
# ll #yll o l * #Ull o) e Burst strength at elevated temperature -
e Pburst(T) = Pburst(T g )
- f(g
,f(T) y g
e Extensive data at 600 F can .thus be applied to higher temperatures. ( J
e-(j '. ( i . . INCONEL-600 DUCTILE FRACTURE PROPERTIES t Temperature Flow Stress Ratio
't 600 F 1.0 1000 F 0,90 1350 F 0.56 -
e ' s t i .- 4 I l i i l 1
~
E wmw~----g,~ - - www_ _- ym mwn _p-g e- w w -m- w,w s , mm m._ --w---
_ . . . . . . - . . . . . . - . . . _ . ~ . . , . . ~ . - - i' (, '(
- l TUBE WITH CRACKING DEFECTS e EDM slots simulate cracks 1.5 inch long slot 55'60% wall depth o Burst pressure = 5 ksi e 5 ksi
- 0.56 = 2.8 ksi.a 1350*F e This exceeds any possible, AP across the tubes l
E
- ~
(; ; TUBE DENTING AND THINNING e Elliptical wastage ' s Dentfng at support plates simulated 0.75 inch length; angle varied 0.04 to 0.05 inch denting depth e Bur.st pressure > 5 ksi all cases e ' 5 ksi
- 0.56 = 2.8 ksi a .1350*F -
s This exceeds any possible AP across the tubes [k
. /E~
a
~
L --
(5 t TUBEDEFECTCONCLl[SIONS e Thinning l Cracking Denting plus thinning All examined e Burst pressure exceeds any possible tube AP when the effect of temperature on properties included O
E
~
~
( J 1
. .. _ _ _ _ _ _ . _ _ __ _ _ _ .1
~ -
(- (.- l PROPERTY EVALUATION.FOR CREEP RUPTURE i ,; e Data for Inconel and SS-316 Indicates great creep behavior s'imilarity e Tube wall hoop stress $.10 ksi e At 1350*F, rupture time Just under 1000 hours e Short rupture time data: i 1500*F, 10 k'si 10 hours .. i l' l t
~
l L J l
( t ( CREEP RUPTURE QUANTIFICATION L e Larson-Miller parameter quantifies temperature, time combination e LMP = T * (A + log t )
- B r
e Inconel data maps onto SS-316 data using LMP abcissa e Using LMP, 1000 hour rupture at 10 ksi requires 1280 *F to 1340 *F: This agrees with all Inconel data
- ~
~
( J l
V (:; f CREEP RUPTURE CONCLUSIONS s i . ! e Inconel creep rupture data is consistent and quan- ! tifiable e Rupture time and temperature combination cannot be achieved for Seabrook SG tubing G E \ ( J e _, _ _ , , . . ,_-_s_ , .
I ;
,;* i; 1 ! l i l
dII r
- h. '
Il _ 0" l 0 0' e k.0 0, P n 8 O" I y o c n 1 o I F lo 0 , c 0e i n y 6 ru 1 t 6 o r 93 1 0 e p 0 0 m 3 \ 4 e g\\ 1 t
\\ \
\\ 0 n g
3 1 0 V' h \ tI 0i 2 1 s t e T 0 \
\ 6 s 1
/ 0 4s 0 4 3 i 4et i 0 4 ei n 0 po 1 yt Ts 0 0'
0 h'r' O" y . C 0
" 0 iO O '"'
l l o o ' 3 8 1 c n I
- 0 F 6 f <
0 e , 1 6 t 3 1 u
\ l o
9 0 3 r*
\
V%
\
% w 0 e 0 p 4 me 1
t r 0Y 1 3
\
j 6 s 0 n g 4s iI 0i t
\ \N 4e ei n pa l
2 se 1 T
' y yt T s 0
0
\ }0 0' 1
1 4
. -- ' 0 0 0 4 0
4 1 l 8 " E oh 4= i; i :,>
( Isdocot 'ss3 sis o o "e i e o N n ; y g i ; I t
, e t I I I I I f r I f f
- I I ) i TI I l l l l I
i o o lj ) o
- e g i r r i i r a
y
//
i i f i i>
'i i
/ / f I z' atti4 f i '
f i I
\\ > I I > l l =
.c$$b $ $$
~
g "o m L. l l l r .l, l i M is i ! f F' I I 0 f' 3 s s i I I I i > wg I / / / / l. g C H a
. ; I l' l ) { M eE O h i.
l C W m < # 4 3 ,3" .
"o m
3 ,
+ ,
2
, , , < i , i ,
- a. '
+ i i r -
3 8'* d I / / l c ill / / / / -l / a. m ll /I, / l r W e f f o J . J - o sisi. , e til! ll l l 11 l I!! ' l e o o o o " o o - o adm'ss381s 1
. , . , . . . , - ,,p.,-- -----~~-v-n--~'vv "Y~' " ' ' * ' ' ' * ' * " ~ ' ~ ' " ~ '
"~'
l - 1 l. Master Rupture Curve for 316 Stainless Steel 10 0 - - - - -- -- - 2 3 -- - - - - -- r ';' ~ '- i -- - - 1 ' i - I su 'ti 11.x u g tg As gx
~/' 'y ASME Code Case N 47
- m Lesson Millot data / .
*k[
l '. m. 0 for 18Cs flNo S S *
.'gg I
- o i ll
'I i ._
hv
}
i 10 14.' i 700 K 1a00 ari - i t-._a X 755 K 1900 *F) I ^ 0 . Gil K (1000 *f I
- INCONEL 600 * -
V },
~
j () . S22 K (1200 *F)
- I A 1033 K (1400 *F) y V - 1089 K (1500 *F) ,
- G)
, s._ , Ch - j
)
i __ . . . I _. . .. . . . l .... l ;....._t. 1 L .L... .
. l i_. _L .. ..
' l l
.15 20 26 30 35 40 45 5'O Larson-Miller parameter T(20+1ogtr ) x 10 3 .g.
Relesence F R Lasson enri .l Milles. A Time *Temposaluse Rotationship los Rupluie and Creep Sisess' Tsansaction of Ilso ASMI. July 1967, pp. 765-776. , j W
] ,
l
~ '
G C CONCLUSIONS
- 1. Base case peak steam generator tube temperature is 750 K and 'Is only 850*K in worst-case uncertainty analysis.
- 2. Tube' integrity analysis indicates that temperatures of abeut 1100*K are required to fail tubes. ,
Thus considerable marg'in exists. ,
~
( J
ENCLOSURE. 3 gx eue eup _ _ me _ eum g a N / ;
\
,- 3
\ . .
]
> \
, 1 Q. ..E.
C f I
/ 0
/ D
/ 5
__ _ _ _ _ _ - - g
- u
. ; .e r.z @
Ji E A
- p e,
~
.f l f:V
-_ a
_.__,_._,..--..~..,_....,..._.,,...,w.
l l l ZION CAVITY SIMULATION EXPERIMENTS i i Test Floor of lioner Surface of Vert ic'al .m
. Section Catch Volume Catch Volume 1lalls " .
l . J j Lip 6.07 ~0 17.8 76.1 i j Steam Generator Geometry f18. 0 7.38 2fl .11 17 j Reduction Area 76.6 ~0 16.5 ~7 I 3D 97.fi - 2.37' O.208 0
! 'Out of doorway next to seal table wall. '
l
- i e
I i
- c. ..
(,- . W//#/A h '
\
s Hm f - Z> W< W1 s' Z \\\\\\\\\ \\ ' W m
~f .
03 - 3 Y e g a. D CO l-I 1
1 i .
. i i i i.
? SEAL l TABLE Vl, V/j N ' ! TRANSPARENT I PLATE .m SUPPLY i , w A l l i !
.7 1 ,
l ! l
._e.., - M - . .2. ,u A
,_, _ = - - - - -.._
,_w mamm m, y ,e.J mv 9M49 6 4 emaa&M _
4
. = _ g .
g\y TRANSPARENT PLATE
;= 4
//
e
-- . __.,--y.- 9.--,.y.,- _
.y.r,y_,.,-- ,,m.w,_..- ..w,,,y,.,r- ,e.,,,,,w,-w,-.-m
= 3 6 -
g S '
~
l I . I- 1 l , i I I l h l i I i . I l l l l
,' l l
SEAL i I ; i TABLE ' i I ; l
< l l
I
,kj I
I
' .l DOOR. I i r"i l l STEAM BIOLOGICALj i ' '
( IGENERATOR [ DOOR SHIELD I. i'i i l i : I 1 I I I SUPPLY TUBE _ l l- I .. O g e e b o 6 6 I . l t l
~
(.: (? DOOR. l - l 1 i l KEYWAY l SCREEN IN OPENING 1
/ TOP SURFACE 4
! 'l ! SUPPLY [ l
+
TUBE l
.f DOOR g l i -
i_ .___. 1 l . , SEAL BIOLOGICAL SHIELD [ + TABLE' LIP , O+ _ L l~ STEAM GENERATOR b I l O l l - _ . . - . . - - . - - - _ - . . - - . . - . .- ._ __. - - - - - -. : . . -... - ,_, - ....,_ -- -.
. _ _ . _ _ . _ . . _ _ _ . _ . . . --- - - - - - ---- 1 i
e- .
*S
.g - e
(' .
\-
1
. a r.'*
l' 2.7 m 7 t' l I i L! '0;";C::
.i U
i e l
. j
- 5.8 m
- _ AI E E E Y E N Eam n
3 b ummu
,- f , ,-,
t / i. f- + ' 2.7 m s . l O.
- w. -'
if an > c c 3 3i en HIPS T4st Apostatus Ptsced in the Esportnerrt interactton Chareer l l
. . _ . _ , . . . . . . . . _ . ,. ,._-..-..-.m--- - - - - - - _ ~ . - - - - - - - - - - - -- - - - - - - - - -
.o e
s-G. i
. 1 SNL HIPS TESTS 1
- 1. HIPS-7C and -8C: 1/10 scale Zion cavity open- !
ended can'inement room. ,
- 2. ~ 97% of debris on floor or pad immediately outside.
- 3. 0.3 - 5.2% aerosolized ( < 10 micron).
4 e O e e e O 9
-- - ,w ------e.-,-s.3--w,,.e-,,.m.,i.em.,w, , eq+ g gg.,,9a - - .- , - -,gpy,,,,___ _ ,, , o _
.c .
i . . (. . V-Mr. Robert J. Harrison.
~
Public Service Company of New Hampshire Seabrook Nuclear Power Station cc: Thomas Dignan, Esc. E. Tupper Kinder. Esq. John A. Ritscher, Esq. G. Dana Bisbee, Esq. Ropes and Gray Assistant Attorney General 225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State Hosue Annex Concord, New Hampshire 03301-Mr. Bruce 8. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Commission Post Office Box 700 Dr. Mauray Tye, ,Presf Ment Seabrook, New Hampshire 03874 Sun Valley Association 209 Sumer Street Mr. John DeVincentis, Director Haverhill, Massachusetts 01839 Engineering ar.d I.fcensing Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 . 116 1.owell Street Manchester, New Hampshire 03105 Mr. A. M. Ebner, Project Manager United Engineers & Constructors Wfiliam S. Jordan, III- 30 South 17th Street Diane Curran Post Office Box 8223 Hamon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW - Suite 430 Washington, D.C. 20009 Mr. Philip Ahrens, Esq. Assistant Attorney General State House, Station #6 Augusta, Maine 04333 Carol S. Sneider, Esq.
. Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Hall One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire Post Office Box 330 0. Pierre G. Cameron, Jr., Esq.
Seabrook, New Hampshire 03874 General Counsel , Public Service Company of New Hampshire , Seacoast Anti Pollution t.eague Post Office Box 330 Ms. Jane Doughty Manchester, New Hampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region I U.S. Nuclear Regulatory Comission Mr. Diana P. Randall 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 ! Richard Hampe, Esq. New Hampshire Civil Defense Agency 107 Pleasant Street Concord, New Hampshire 03301 ~
.-- - - - - ~ ^ ~ ~~ ~ ~
. p:;.
Public Service Company of New Hampshire Seabrook Nuclear Power Station cc: Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Hall Chairman 126 Daniel Street Board of Selectmen Portsmouth, New Hampshire . 03801 Town of Salisbury, MA 01950 Ms. l.etty Hett . Town of Brentwood Senator Gordon J. Fumphrey RFD Dalton Road " ATTN: Tom Burack Brentwood, New Hampshire 03833 U.S. Senate Washington, D.C. 20510 Ms. Roberta C. Pevear Mr. Owen 8. Ourgin, Chairman Town of Hampton Falls, New Hampshire Drinkwater Road Durham Board of Selectmen Town of Durham Hampton Falls New Fampshire 03844 Durham,-New Hampshire 03824 Ms. Sandra Gavutis Charles Cross, Esq. Town of Kensington, New Hampshire Shaines, Mardrigan and RDF 1 McEaschern East Kingston, New Hampshire 03827 25 Maplewood Avenue Post Office Box 366 Chairman, Board of Selectmen Portsmouth, New Hampshire 03801 RFD 2 South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Rye Nuclear Interv'ention Mr. Angie Machiros, Chairman Committee Board of Selectmen c/o Rye Town Fall for the Town of Newbury 10 Central Road Newbury, Massachusetts 01950 Rye, New Fampshire 03870 Ms. Cashman, Chairman Jane Spector Board of Selectmen Town of Amesbury Federal Energy Regulatory Town Fall Commission Amesbury, Massachusetts- 01913 825 North Capital Street, NE Room 8105 Washington, D. C. 20426 Honorable Peter J. Matthews
- Payor, City of Newburyport Mr. R. Sweeney l Office of the Mayor New Hampshi're Yankee Division City Hall Newburyport, Massachusetts 01950 Public Service of New Hampshire Company 7910 Woodmont Avenue Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 Town of Exeter 10 Front Street Exeter, New Hampshire 03823 Mr. William 8. Derrickson Senior Vice President Public Service Company of Mr. Richard Strome Director New Hampshire I
State Civil Defense Agency Post Office Box 700, Route I State Office Park South Seabrook, New Hampshire 03874 107 Pleasant Street Concord, New Hampshire 03301
_._..__.7 - - - ~ - - eg K 8 h %> . Gj . . UNITED STATES j o ' NUCLEAR REGULATORY COMMISSION
-f WASHINGTON, D. C. 20555 a
%,...**/ -
WE Docket No.: 50-443 APPL.ICANT: Public Service Company of New Hampshire FACII.ITY: Seabrook Station, Unit 1
SUBJECT:
SUMMARY
OF MEETING AND SIMUI.ATOR TOUR HELD ON OCTOBER 15, 1986 TO FACILITATE NRC REVIEW OF THE SEABROOK EMERGENCY PLANNING SENSITIVITY STUDY
REFERENCE:
Seabrook Station Risk Management and Emergency Planning Study and Seabrook Station Emergency Planning Sensitivity Study. Submitted by letter from John DeVineentis to Vincent Noonan, dated July 21, 1986. A publicly noticed meeting was held on October 15, 1986, at the Seabrook Station in New Hampshire. The NRC staff was represented by members of the Office of Nuclear Reactor Regulation and Brookhaven National I.aboratory. The Applicant was represented by members of the Public Service Company of New
. Hampshire and Pickard, lowe and Garrick, Inc.
A list of attendees is included as Enclosure 1. , j The purpose of this visit was to allow the NRC staff and its consultants to examine the control room operating environment and procedures to facilitate its ongoing review of the referenced doments. .-
- During the morning the Seabrook simulator training staff presented and 1
discussed a new training module designed to assist the Seabrook operating staff in recognizing the occurrence of a loss of coolant accident (1.0CA) through an interfacing system, with emphasic on the RHR system. During the afternoon, the NRC personnel and consultants visited the simulator to visually examine the in,dications and controls available to the reactor operators. Procedures pertinent to emergency conditions were also examined. During the visit, simulations of two types of I.0CA sequences were run without operator intervention to demonstrate timing of events and some indications of 1.0CAs outside containment. (The Seabrook simulator is not now programmed to simulate event V.) One of the sequences was rerun to demonstrate operator recovery actions. The meeting was concluded following discussions of check valve testing procedures and indications for leaking valves, s / 4
.4% $f-l /m-Steven M. l.ong, Project Manager PWR Project Directorate No. 5 Division of PWR licensing-A
[ Jpp>~
-e ~.-+n.- ,...c.--,,..- -
.. _ _. - - - - . . . - - . - - - - - - --- - ~- -- ~ ' ^ ~ ~~ ~ ~ ^ ~ ^ ~
, 'M '
- s.
- ATTENDEES David A, Maidrand YNSD, Asst. Project Manager Bob Youngblood Brookhaven Natl. Lab Jim Moody NHY Tsong-lun Chu B NI.
Bill luckus BNL, Human Factors Don Hickman NRC Steven long NRC, Project Manager John Tefft NHY Frank Bellini YAEC - Licensing - Ralph Ferrell NHY, licensing Coordinator Tony Cerne NRC, Senior Resident Dave Rsucitto NRC, Resident Inspector 9
+
G t e l
-w -
A
,. . t. .
(. Y Mr. Robert J. Harrison - Public Service Company of New Hampshire Seabrook Nuclear Power Station
,5 CC:
Thomas Dignan, Esq. E. Tupper Kinder Esq. John A. Ritscher, Esq. G. Dana Bisbee, Esq. Ropes and Gray Assistant Attorney General 225 Franklin ' Street Office of Attornev General Boston, Massachusetts 02110 208 State Hosue Annex Concord, New Hampshire 03301 Mr. Bruce 8. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Commission Post Office Box 700 Dr. Mauray Tye, President Seabrook, New Hampshire. 03874 Sun Valley Association 209 Summer Street Mr. John DeVincentis, Director
- ~
Haverhill, Massachusetts 01839
~ Engineering and licensing Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 t.owell Street ,
, Manchester, New Hampshire 03105 Mr. A. M. Ebner, Project Manager United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Post Office Box 8223 Hamon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430-Washington, D.C. 20009 .
- 'Mr. Philip Ahrens Esq.
Assistant Attorney General State House, Station #6 Augusta, Maine 04333 Carol S. Sneider, Esq. Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Hall . One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire Post Office Box 330 D. Pierre G. Cameron, Jr., Esq. Seabrook, New Hampshire 03874 General Counsel Public Service Company of New Hampshire Seacoast Anti Pollution League Post Office Box 330 Ms. Jane Doughty Manchester, New Hampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region i U.S. Nuclear Regulatory Comission Mr. Diana P. Randall 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Hampe, Esq. New Hampshire Civil Defense Agency 107 Pleasant Street Concord, New Hampshire 03301
- . . _ . - . - _ - . . _ - .- . _ _ . - . . - =
- - . - . . - -- --- -~
.- .?\
- m ..
Public Service Comp fC of New Fampshire Seabrook9uclear Power Station
,i .
CC: Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Fall Chairman 126 Daniel Street Board of Selectmen Portsmouth,.New Hampshire 03801 Town of Salisbury, MA . 01950 Ms. I.etty Pett Town of Brentwood Senator Gordon J. Fumphrey ATTN: Tom Burack RF0 Dalton Road U.S. Senate Brentwood, New Hampshire 03833 Washington, D.C. 20510 Ms. Roberta C. Pevear Mr. 0 wen B. Durgin Chairman Town of Hampton Falls, New Hampshire Drinkwater Road Durham Board of Selectmen Town of Durham Hampton Falls, New Hampshire 03844 Durham, New Hampshire 03824 Ms. Sandra Gavutis Charles Cross, Esq. Town of Xensington, New Fampshire
' Shaines, Mardrigan-and -
ROF 1 McEaschern East Kingston, New Hampshire 03827 25 Maplewood Avenue , Post Office Box 366 i Chairman, Board of Selectmen Portsmouth, New Hampshire 03801 RFD 2 South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman . Rye Nuclear Intervention Mr. Angie Machiros, Chairman Committee Board of Selectmen c/o Rye Town Fall for the Town of Newbury 10 Central Road - Newbury, Massachusetts 01950 Rye, New Hampshire 03870 - Ms. Cashman, Chairman Jane Spector Board of Selectmen Federal Energy Regulatory Town of Amesbury Commission Town Fall Amesbury, Massachusetts 01913 825 North Capital Street, NE Room 8105 Washington, D. C. 20426 Honorable Peter J. Matthews Mayor, City of Newburyport Mr. R. Sweeney Office of the Mayor hw Hampshire Yankee Division b City Fall l: Newburyport, Massachusetts 01950 Public Service of New Fampshire Company 7910 Woodmont Avenue Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 ? Town of Exeter 1 10 Front Street Exeter, New Hampshire 03823 Mr. William B. Derrickson . Senior Vice President Mr. Richard Strome, Director Public Service Company of New Hampshire State Civil Defense Agency Post Office Box 700, Route 1 State Office Park South Seabrook, New Fampshire 03874 107 Pleasant Street Concord, New Fampshire 03301
--- -~ ~ "~ ~~ '~~
. L . ._ ... . -
- . . - - - - - - - " -: ^
./.
- 4 4ce . -
L - p 'o, 4 . UNITED STATES f -7 4 , , .
'*"*' '4E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
, .D' s
- c. i s . .n'f,,,,/
- NOV 2 6IQ Docket No. 50-443 APPL.ICANT: Public Service Company of New Hampshire
- l FACII.ITY: Seabrook Station, Unit 1
SUBJECT:
SUMMARY
OF MEETINGS HEl.D ON OCTOBER 16 and 17,1986 1 TO DISCUSS SEA 8 ROOK ENERGENCY Pl.ANNING SENSITIVITY STUDY
REFERENCE:
Seabrook. Station Risk Management and Emeraency Planninc.Studv and Seabrook Station Emergency Planning Sensitivity Study. Submitted by letter from John DeVincentis to Vincent Noonar, dated July 21, 1986. Publicly noticed meetings were held on October 16-17, 1986, at Brookhaven , National 1.aboratory in New York. The NRC staff was represented by members of the Division of PWR I.icensing-A and Brookhaven National I.aboratory (9NI.). The Appl.icant was represerited by members of the Public Service Company of New Hampshire, Pickard,l. owe and Garrick, Inc., Structural Mechanics Associates, Fauske & Associates, and Westinghouse Electric Corporation. ' The purpose of these meetings was to facilitate the NRC's oncoing review of , the information in the referenced documents. There were two distinct sub.1ects covered by two separate working groups. A group which focused on details of containment strength calculations met b'oth days. A second group met only on October 17 to discuss convective transport of heat from the melting core to other parts of the reactor coolant system (RCS)." 1.ists of attendees are ! included as Enclosures I and 2. The group dealing with containment strenoth issues discussed in detail the containment strength calculation report prepared by Structural Mechanics Associates (SMA) for Pickard, l. owe and Garrick, Inc. (Pl.G). The SMA report was incorporated into the probablistic safety analysis study performed by Pl.G . The entire meeting was devoted to the discussion of the SMA report by Sle.] 2 % Y.l.(.pl
%pp.
3 L' ( (i-examining the methods used, the underlying assumptions regarding the variability estimates and results obtained. A number of items of clarification needed by the BNI. staff were discussed, and these action items were later forwarded to the I.fcensee in a letter from Steven M. l.ong to Robert J. Harrison dated October 23, 1986. The group dealing with convective transport of high temperatures inside the RCS during core melt heard presentations by Westinghouse and Fauske personnel. Physical model exoeriments at Westinghouse facilities in Pittsburgh were described, and computer modeling'of the convective flow phen'omena for hioh pressure core melt sequences at Seabrook was presented. The applicant concluded that the heat transport phenomena would not raise the steam generator tubes to a temperature sufficiently high to cause creep failure. An important element of the applicant's model is the interruotion and the convective transport mechanisms by the disruption of core oeometry dur,ing
. melt. Discussions focused on the nature of the mode'l and the sensitivity of its results to its underlying assumotions. Materials from the a*oplicants' presentation are included as Enclosure 3. ,
Questions arising in both meetings were formally submitted to tile applicant by letter dated October 23, 1986, from Steven M. l.ong to Robert J. Harrison. During a combined meeting of.the working groups at the end of the second dav, it was decided to publicly announce three additional meeting dates so that [ additional discussions could be held, if necessary, durino the period when the NRC's review is nearing completion. The dates chosen were November 6, 12 and 19, 1986.
- , i. .
, . . me Steven M. l.ong, pro.iect Manacer PWR pro.1ect Ofrectorate No. 5 Division of PWR I.fcensing-A l
l
--, ,,. . . - . . .----------c. - - . - - , - - - . , - - - . - - - - . . . . . , , ,
- ~ ~ ~ - - -- **
_, .a _- ..~ - - - - . - - - - - - - - - 4 < ( ' (. ,
~
Mr. Robert J. Harrison
' Public Service Company of New Hampshire Seabrook Nuclear Power Station cc:
Thomas Dignan, Eso. E. Tupper Kinder, Esq. - John A. Ritscher, Esq. G. Dana Bisbee, Eso. Ropes and Gray -Assistant Attorney General s 225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State Hosue Annex ' Concord, New Hampshire 03301 Mr. Bruce B. Beckley, Project Manager
, Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station j, Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Comission Post Office Box 700 i.~
Dr. Mauray Tye, President Seabrook, New Hampshire 03874 Sun Valley' Association 209 Sunmer Street Mr. John OsVincentis, Of rector Haverhill, Massachusetts 01839 ' Engineering and I.fcensing _ Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 1.owell Street Manchester, New Hampshire 03105 Mr. A. M. Ebner, Project Manager . United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Post.0ffice Rox 8223 Hannon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430 .
' Washington,-D.C. 20009 -
Mr. Philip Ahrens, Esq. i- Assistant Attorney General l- State House, Station #6
. Augusta, Maine 04333 Carol S. Sneider, Esq.
Office of the Assistant Attorney General
. Environmental Protection Division Mr. Warren Hall One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire Post Office Box 330 0. Pierre G. Cameron, Jr. , Esq.
Seabrook, New Hampshire 03874 General Counsel
. Public Service Company of New Hampshire
- Seacoast Anti Pollution t.eague Post Offic~e Box 330
, Ms. Jane Doughty Manchester, New Hampshire 03105 i' 5 Market. Street
- 4 Portsmouth, New Hampshire 03801 Regional Administrator, Region I
- ~ U.S. Nuclear Regulatory Commission Mr. Ofana P. Randall 631 Park Avenue
, 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Hampe, Esq. New Hampshire Civil Defense Agency , 107 Pleasant Street Concord, New Hampshire 03301
t
-(
Public Service Company of Seabrook 5uclear Power Station New Hampshire
. l cc:
Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Hall Chainnan 126 Daniel. Street Board of Selectmen Portsmouth, New Hamoshire 03801 Town of Salisbury, MA 01950 Ms. I.etty Hett Senator Gordon J. Fumphrey Town of Brentwood ATTN: Tom Burack RFD Dalton Road U.S. Senate Brentwood, New Hampshire 03833 Washington, D.C. 20510 Ms. Roberta C. Pevear Mr. Owen 8. Durgin, Chairman Town of Fampton Falls, New Hampshire Durham Board of Selectmen Drinkwater Road . Town of Durham Fampton Falls, New Hampshire 03844 Durham, New Hampshire 03824 Ms. Sandra Gavutis . Charles Cross, Esq. Town of Xensington, New Hampshire Shaines, Mardrigan and RDF 1 McEaschern East Kingston., New Hampshire 03827 25 Maplewood Avenue
. Post Office Box 366 Portsmouth, New Hampshire 03801 Chairman, Board of Selectmen
.RFD 2
, South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Rye Nuclear Intervention Mr. Angie Machiros, Chairman Connittee
- Board of Selectmen c/o Pye Town Hall for the Town of'Newbury 10 Central Road Newbury, Massachusetts 01950 Rye, New Hampshire 03870 Ms. Cashman, Chairman Jane Spector Board of Selectmen Federal Energy Regulatory Town of Amesbury Commission Town Fall .
825 North Capital Street, NE
. Amesbury, Massachusetts 01913 Room 8105 Washington, D. C,. 20426 i Fonorable Peter J. Matthews ,
Mayor, City of Newburyport Mr. R. Sweeney Office of the Mayor New Hampshire Yankee Division City Hall Public Seryice of New Fampshire Newburyport, Massachusetts 01950 Company 7910 Woodmont Avenue Mr. Donald E. Chick Town Manager Bethesda, Maryland 20814 Town of Exeter
'10 Front Street Mr. William B. Derrickson Exeter, New Hampshire 03823 Senior Vice President Public Service Company of Mr. Richard Strome, Director New Hampshire State Civil Defense Agency Post Office Box 700, Route 1 State Office Park South Seabrook, New Hampshire 03874 107 Pleasant Street Concord, New Hampshire 03301
1
-.-----2-- -- -
t
. i l
( f.. l l
?
L I ENCI05URE 1
!. ATTENDANCE
~
SEARROOK CONTAINMENT STRENGTH { OCTOBER 16-17,1986
!. NAME AFFil.IATION
- Goutam Bagchi NRC/NRR/PWR-A
~
Kamal 8andyooadhvay B NI.
' Charles Hofmayer B NI.
Howard Hwang B NI. Paul Bezler BNI. Gordon Thompson Mass. Attorney Gen 1. Fred Torri Pl.G Robert White New Hampshire Yankee Frank Bell,ini Yankee Atomic Elec r: Ralf Peek Univ. Cal., Berk 1.ey L Don Wesley 'iTS l a i
}
l
.. - . . - .-- . . .-------.w . . . . - - . . - --_. . . . . . . - . . ~.
-5 a ,
- (c. ' ('-
ENCI.0SURE ?
, ATTENDANCE 5/G TU8E Fall.URE OURING CORE MEl.T OCTOBER 17, 1986 Steve f.ong
- NRC/NRR/0Pl.A Steve Follen ankee Atomic Jim Moody NNY Bob Youngblood Brookhaven National I.ab Pete Davis PRD Consulting David A Maidrand Asst. Pro.i. Mgr. YNSO -
i Bill Cloutier f.ead Systems Eng YNSO Martin Plys Fauske & Associates Robert Fenry Fauhke & Associates Marc Kenton Fauske & Associates Bob I.utz Westinghouse Electric , Mohsen Khatib-Rahbar B NI. Trevor Pratt B NI. Possein Nourbakhsh B NI. Nam Cho , 8 NI. Tsong l.un Chu B NI. Warren C. I. yon NRC/NRR/0Pl.A/RSB George Bozoki B NI. Joanne Feinz BNI. Jae Jo B NI. Ken Perkins BNI.
o,
'( ENCLOSUltE 3 SEABROOK STEAM GENERATOR INTEGRITY ANALYSIS-Martin G. Plys Marc A. Kenton Robert E. Henry Fauske 8 Associates, Inc.
Burr Ridge, Illinois Peter Kirby -
- - Westinghouse Electric Corporation ,
l Pittsburgh, Pennsylvania , T*, *
*pL,e, r-Presented at Brookhaven National Laboratory I Upton, New York October 17, 1986 E
( - J
, - - . . - , ,-..-.,.._,_--,-....-,--...,n. _ , , . ,,,.-,,..,.,ny.g,,,, .,,.a. , , , , , - . - . , , . , , - . , , - . - _ .
l - l: ( ( ., [ ANALYTICAL APPROACH ._- i .
. Objective i , Determine the thermal resnonse of steam aenerator ; tubes under severe accident conditions.
Secuences Considered Since steam cenerators must be dry to experience any sianificant thermal transients, station black-
. out conditions were used in the analysis.- -
Key System and/or Ooerator Resoonses Analvzed
- w. . a. Station blackout without operator actions or
'^
oump seal LOCA. b.. Station blackout with the cumo seal LOCA and no coerator QCtions. 1 i c. Station blackout with nossible onerator
! actions, i
- d. The influence of key uncertainties, l
I p
, /2 N .
Y
.(
(. .
~
i POSSIBLE OPERATOR ACTIONS FOR STATION BLACK 0UT CONDITIONS o knitiate steam turbine-driven 'auxiliarV feedwater flow. e Restore emeraency AC cower. l . , v. . e Shed all non-essential loads,
. :.s.,.
e Ooen the Power Operated Relief Valves (PORVs) when core temperatures exceed 1200 F.
,.s - '
...r ., ~.
u E ( - J l
,~
(: (1 [ D
! j. l IMPORTANT RESPONSES BROUGHT ABOUT BY OPENING PORVs AT 1200 F CORE TEMPERATURE e Deoressurize the crimary system such that accumu-lators inject water and help maintain core coolina.
e Deoressurize the crimary system such that stresses ~ on all primary system comoonents are substantially reduce'd. e Flow out of the PORV overrides circulation such T.:. . , . that high aas temoeratures are not imnosed on the _ steam aenerators, includino the tubes. E
)
(
'C STEAM GENERATOR TUBE INTEGRITY CONCERNS DURING STATION BLACK 0UTS p
e During unmitigated station blackout sequences, the presence of high pressures and no makeup lead. to strong natural circulation flows between the core and the upper plenum of the reactor vessel, e Since a loop seal exists in the pump bowls so that no flow can pass there, high temperatures in the upper plenum will initiate counter-current natural circulation between the steam generator inlet plena . and th'e RV upper plenum, e The resulting increased temperature in an. Inlet plenum leads to natural flows out to the outlet 7, c ,, plenum through some tubes and a return flow to the !.__ inlet plenum through other tubes.
, o High temperatures in the inlet plenum or tubes raise concerns 'that steam generator tube failures O could result.
E ( ~ J
( ! 1 [ ' '
)
Waa e J [ (TOTAL FLOW) ouT" TUBE < =
-BACK' TUBE
( : L i .
~
n e J TSEC = . 1 e
' ~
h. Wst-fTv - TUP c
" ~
W L Tc gt f e Hot leg and steam circulation flow, generator natural
- ff
,-n--, -me,,,.,.w-, ,-c-- .w-,- .,,,-,v---- ,,-n,
}- ( ' .(
~
OVERVIEW 0F MAAP NATURAL CIRCULATION MODELLING .E
. e Gas and wall temperatures in primary system control j volumes computed by conventional lumped parameter models: 15 gas control volumes,17 heat sinks (two dimensional).
- e Natural circulation flows computed by 6uasi-steady momentum balances and continuity eductions. -
e Steam generator inlet plenum temperature computed
.,._ , quasi-statically in the hot leg natural circulation
~
calculation. I j . l E
-)
(.; ( i b DOME WALL i
! DOME GAS NODE RV WALL 's 1
DOME PLATE
,f_
7 yUPPER CORE
/ 7 BARREL UPPER PLENUM e -
GAS NODE '~. % ' . N NUPPER PLENUM CORE- \ INTERNALS GAS NODE 7 DOWNCOMER GAS NODE
- v. .
I Y~ LOWER CORE BARREL i RV WALL M \ E' ( J : l l [ l 1 l
.. ~- - . - - - _ . . . .-
s {j. (.
~
S/G GAS NODE SHELL HOT TUBES : COLD TUBES N / L-HOT TUBES % COLD TUBES
. GAS NODE N , p / GAS NODE COLD LEG PIPE 4
COLD LEG GAS NODE !v. ~ . j HOT LEG PIPE j l1
/
HOT LEG A GAS NODE INTERMEDIATE LEG PIPE V INTERMEDIATE LEG GAS NODE [
#2
( '
)
,--,-----.-w,---.,~,n-,-- ,.,__.,--a.,_ - , . - - - - , - - , , , - - - - , - .
;(
s . g I . COMPARISON OF CORE-UPPER PLENUM FLOWRATES IN THE WESTINGHOUSE EXPERIMENTS TO l MAAP MODEL (IDCOR 85-2) 1 4 Experimental Model .
~
28 kw water test .
. 54 .50
.9 kw SF 6 test' . 016 .017 9
F. -
.S.,*
e. e
=.
E' e
-----en,,-e-ww.___-~ _, we , w a m w - a,.-ev _mw.,,--g,-g-,---.-,,erm,s-,,.yn,w--r.
- .l .
- s. :9 .. ,
! c-l ZION THLB: CROSS-FLOH RESIST. INCL. ' ! STENGING RSA AINTER PtBdVM-CORE NC FLOM ;
3
) @O -
iiiiiii . , ii .... . . . . . ... . . . . . . . . _ l- . 1 - ~
- l - !
i -
} -
- r ,
Uo i - gt : Analytic Model NC Flow : '! s : : o : : e ] 4 M - o - r - mm - _ t
.d 4 MAAP NC Flow :
i,
@ o j L -
m. I. n - m 1 i E. - i - .
~
3 i v- -
- 3 -
I
- o :
. m _ _., _
l o v Q g. . . _: ; l 8000 9000 1-OOE+04 1 1OE+04 ...,I,2OE404 l' l ' TIE SECS > l Fig. 3.3 Comparison of analytic model results to MAAP - calculated natural circulation l flows when cross-flow resistance included. ~ l . I l l I
.q e ,
i 1 COMPARISON OF HOT LEG-STEAM GENERATOR NATURAL l CIRCULATION MODEL TO EXPERIMENTAL DATA i 1 . Experimental Model Prediction Quontity Measurement. n o = 6' no = 12 no = 24 ! Q (kW) 2,43 2,0 2,6 2,9 I '
+ 30 30,7 29,2 28,4 TH ( C)
Tc ( C-) + 19 24,2 21,7 18,8 '! Tco ( C) + 10-11 , 9,4 11,2 12.,8 is the number of tubes carrying the out flow.
*no l
l
\ . ,
- d. -
l .,E L t . J , i- i' i i i ,
f T 'i i v v L
/
s g K k 3 H 0 4 3 6 7 ' g( K 0 5 8
/
,mi '
1 K / 0 - 0 - 7 - N -
., I T= .
K E - A R K - E U 0 P T 6 7
~
FA OR E
~-
s-( EP /- g-8 MM I k-TE T 4. - E 2-HR TO , T B_ T A Rh A4 SET N ES NE O I T GA K )k 0a
*s
/
M C 0e g l I K I D ES N AE 0 6 8p 1( k 8 1 OTA 1 CSB 1
MAAP ANALYSES TO ASSESS THE POTENTIAL FOR TEMPERATURE-INDUCED STEAM GENERATOR FAILURES .-
- 1. No Operator Action
- a. Base Case.
b, Seal LOCAs, 2, Operator Action
- a. With turbine-driven AFW (not shown-sequence
- does not progress). -
- b. With failure of AFW and manual depressuri-zation. of primary system when core tempera- .
tures reach 1200*F, 3, Uncertainty Analyses
- v. .
> s. , - .
_ a. Depressurization case with high core melting temperature (3000 K),
- b. Base case except high core-upper plenum flow (Iow friction factors),
- c. Base case except low steam. generator flow (low fraction of tubes carrying flow away from inlet plenum).
E ( J \ i __m-_- . . . - _ . - - - _ . . . . - - - - . . - - - - -
4 (3-SEABROOK UNMITIGATED TMLB' CALCULATIONS (Base Case) 7*.
*A 5f*
L s b E
.........g ..... .g.........;4 . . . . . . . .
- g. 4 4 . . . . c "'
._. o
_ _ x ce 3 e 2 E i W y -
\n -
l-- E g : e e_ . y : : - r_ S. , - g :
- m n
9 t t tt t t t t t t t 9 9 9 t t t t t t t t t t tt t t t I f f f f 9 9 9 . t f" S2 E S1 I 0s-0 0' s OIMM 'SSVW H31WM ABVONO-)3S .1S
1 % G., (. il N C, . l _. . . . . . . . 1 . . . . . . . . . I . . . . . . . . . i . . . . . . . . ,. N o.
- x
. x
- m 3 . .
- e. .
n m :
- ~ un .
t _E
- s
- o
. : o L
- o
- v -
- o o
"t , , . .
t t t
- t t t ' f f f f f f f f T t t t t t t t t I t t t I t t t t t f- g OE si of s o
, Ogx %f *3 BASS 3Bd SAS Ah!WWIBd D
h m- -w~ --e.--~m- qre.w---rw,,,ww. ,,m._ , v me m e, w m . --.mm--e-+-. r-~--- ~~ * ~
(.~ . d si.....g......gu......g.......gi.......g......e o
~."
_ ' .Of _x
- _- oc
- e p
o _ _.- e.n. . a _ i _ e i : : c _ m _ i ec e5 ~ 01
- W p
og .
.C 2 :
- : s o
g g : .- w . e_ e : L,-- - >o _
- o. _
g a, _ u _ _ l . Iffff,ffffff?f?f,fffffII?8 ,Iff?'*ff I !
- I f f, f f f * ? ! I f '"
, "I f f f f f ff88 Q
OEI Oct 08 09 O& OE -O
, OIX SM '3H03 NI SSW1 8319M .
-{
. ~ . . . -- - . , . . - _ _ , - - - . . ~ , . , - - - . . - , . , - . - . _-. _._._. - - .- -.,_._,--- ___ _ . . .
(.. x . n a........I..** .
.........,.... , ,,,,........n
- e o ;
y
--- m
.i,
- : l -
_ r [ ~ W : - u: c : i cc _ o cm -i c,' . H M-i . W -
- tW l .
r M : 7 r.- g _ cc . __ -
. e :
-[D
*J.*,-.
t,1.;. _ - 0, .
- .a i _
- I~
_ : s
, . . , . . . , i , , , , . . r , . , . . , . , , , . . . . ._. . i , . . . . , .- s OS O& CE og 0I -
o. S G ' M O L:1 W D N _ M d c! D - 3 E C 3 l i
l
, J l
G; (. \ e a CN e gisissisi 6446666.a ..... 46 4... 6 . ..i.... . 6446 66 64,...i...., C
~ t
.y -
x l _ i
- _p-
- I p
_ !i : l C
- ! d : _
t : i E l % ) 1
. 1 E '-
m
. w -
- I .
m - i . c : - 1) x - 1 t . o -
"W
', ~
CD 3 .
,j -
) _ ,
- ' :l I :
'J H :' u1 I
- C -
i r - C _ 4 : m g f.n 8
.ns.--%
7' gg : .!- h% -
. g. , .
w: mF i r----v'- - 8 ,: A m. _= .- b mam_a. W-
% .2 i72 l c:
=
- ___ m. n m
~~
p -- g-u E N- m 1 E U?. .
- : ; s
_ e. . g ,,,...o, . ,,.,,., .,,...., ....,,.., .:,,,..,, L 9 S V E E T *O S 9M 'MO1.-f SV9 - 0 o
. - - - _ , - - - . . , , , .-.m...em,_._,,,_m.,._,_y_ _ _ - _ _ , . _ . _ _ .
y,,__,_ .,__,.,m,,m__ _ _ _ - _ , , _ . _ _ _ _ _ _ _ _ _ _ _
(
- (. . .
i 1 l .. t n 6 6 i 6 1 6 6 6 6 6 6 6 6 6 6 6 6 6 .6 6 6 6 . 6 6 i -,n O
~
.' x
_ _ ~ gg _ _ C _ cc . e _ _ i.i . r _ E _ . p .
- v. .
m
>'.- w _ _
W - _ 9 .
~
, q .
. 1 .
3 E E I 'O.
, 01x 3 dW31 300N 3803 IS3.LLOH . i..............
,p.4eM e i m--._ep. , - .
^
n%+ -' *+4 - A ud'*'* *" *** %" # ' '*W ' 4 * (. . .. (. g ,... ...,......,..,........., ........,.........,,,,,,,,, g o "
~
- O
- 'i .
- H .X C .: - l ' ,cc
, : o
. .i
- _ d,-to
_ i m n
= "
. j r :: - ; ;y W : n- :
LD -
. 1 C : :
W . . i r - 1 A .4 D : g
-j
- l : t
- 2. _
.g.
H : L
- g- -
4'O
~
(C m W
- a, . :
- ;~ r n -
5 : .
~ :
Cr. : cc. :. . _l b' n.
. e_ _ ;
.:. * , - u.., =m-: :
w, _ _
-~ r
_ H_ JC _ . A_ .37 m _ - 2 - y? -i 3R 1 !- : : a _ _ r :- :; O.-,,,,,..,l.
.,,....,1,,,,.,..I,,,,,,I,,,,.,,,,[,,.,,,,,.10 _
OOE OSZ 002 OSI 00I OS -O SM 'SSUW N39080AH - i 4
- --- --.,.-,.-,.-..,.-_n, - - - _ - - - - - . - ,,----,_,n,_.,---.,---.,---.._-.-___,--,- _ . - _- - - -----,,- -- -.. -
PRESSLRE. PA x 10 *
- 0. 5 10 15 20 o........J.;.........,,,,,,,...
E o : w -- c i d -
~
A -- s .:
- x. :
m :- - I
~;
E $ . r, c . m E- . :: 4 e: . w- i :
-o : -
- w -
a
. tn - .: 5
. w :
s
. t !8
-i th : ::
- I
.m : .
X : - A ,v :,.,,,- . . , i , , , , , , , , , i , , , , , , , , , , , , , , , , , , ,- - I g 500 600 700 800 900
. \_ SG PLENUM TEMP, K 1
n e
~~ ~ - ' ' ~'
. , , . . . .. . , _ , _ .-.-.-+ - --- t-~~
M- na .- d .,a a _ s s
, , m W- * ** ** # '"
O i e SEGROOK OPERATOR-INDUCED DEPRESSURIZATION CASE 6 9 0 1 T'. . {
- h ', s
- Y" 0
E
).
1 _m.-.__, - . _ _ _ - - __, .-_.- __,._ , , _ _ _ _ ,_ _ . _ _ _ _ , _ , . , . , _ , _ _ _ , _ _ _ . . . - . _ , . _ _ _ _ _ _ , _ . - . _ _ _ _ . _ - _ ~ _ - - - - - _ _ _
- _ __- - .- - - =. .
=
( C
......... ................... ....... 3 n e x
. 4 : ca.
~
c*
- E l M.
q-
- e J :
1- n
- 14 .
E : ~ ftJ t
, u :
m. E E ! H H : : o-CC +_ .
- : o t ,
t <= i
. : o o
- i. v.
- o
" : o N.
- : o a-:1 ,,, .., .,,,,,,.1,,,,,,,,,i,,,,,,..: ,
- .o -
03 S1 01 s 0
, OIx Vd '3EES3Bd SAS AWWIBd t
Q.. (- o" s........i.........i.........i.........i.........i........._ no - x J u, _ _ o m o n ll _ _ w _ _ _T m : o y : . m 2 _ _ W w : :
- c. : : -
o : C p 2 - o :
- c. :
m - tlC T. t' r w m : : e - W g y n L,,,,i...,,,,,,!,,,,,,,,,I,,,,,,,,,I,,,,,,,,,i,,,,,,,, e' OEI 001 08 09 Ok 02 O'
, OIx 33 3803 NI SSWW M3. LUM v-m,www-->mw, w- g-y-e -
C_ - l.
-4 ..i. i.6 g4 . . 4. .
6l... 4 . . 6 . g4 . . . , , ,
,,,,6 , , , , , , u '~m "
o i :..g
- m. !
a : E o : : o : n e :- E
- m. -
C Q :- "W Q. 2 . g ~ mi :
- m. E
.E : m8 E
'2 e- .
m
.:. . . . ~o -
m : 1 _- _ m : - 2 :
~
- m
~
W . m :
- m
- m-n.
H : 6
, , , , , , , , i , , , , , , , , , i , , , , , , , , , i , , , , , , , , , i . , , , , , , , ,:
3 OS Ok OE OE OI -O-S'SM ' Mold WON 37d dD-3HO3
8 .. . .
.~ .
(... (a c f'3 nn s 3 a s e a s 4 6 ig a a 6 4 6 a s aig a 4 4. 6 6 6 g.4. 4, 6 6. g . 4 6 6 4 4 6 4. g 4 4 6 61, 6 6 g ,4 6 6 4 4 6 6,
. O 5 . X Am
- 1 3-L : - :
- a N : -
,e :
~
-1 30 '
[2: Q
- 5 "W l CL : :
- : In .W
.Q, : E
- A3 -
- mp T
3 . H :
- J 3m "
e- . . .Q : , -2*.,- c:: p: 3 m .
- n r-38< 2
- m l.
o,i 3- -1 3m o -
.I -
i a W. w -
- N
' 3 3 E
C ,,,,,,,,l.,,,,,,,,l,,,,,,,,,I,,,,,,,,,1,,,,,,,,,i,,,,,,,,,l,,,,,,,, g 4 9 S k E E I O'
~
S'SM 'HOl.d SUS l l
,, m..wsde
(. @. , m m .... . . . .. ..g.. . ....g .(._i :- "o C.
.... .., 4g....
- ,- ^
t
;c i co
- :l
- . . 1- , , . .
- u. ~
~
l
.C -
a W
- . - p;-
4 t, t
> ~
a J l -es CC : : C : : cf# 0 :
.g .
CC C_. U -
- o. g l
g p L : l -- i r :. -- <-- :p
,o
- 7 -
\
$ F
-4 10e
.e_ ..,.
. , . Os W-
-- CD . : :
cE L<
- h.
tr, ' c _hst m: : m: 1 ]f9 d _ _1 w : : e _- _-
.m - _
D , , , , . . , ,1 , , , , , . . . 1 , , , , , , , . 1 , , , , , . . , I , , , , , . . , . I . . . . , , , . 3 0 OCE OSZ 002 OSI 001 OS -O. SM 'SSWW N330BCAH l p ..m. . ---e== "~~~
v - (.- t.
>l 'dW3.L WON 37d DS 006 008 004 009 009 a -
I _............. ..... ..... ........ .. e
.n -e x
. :m
_ :. ,e e : : n : A : II : W _- - v g : I : e : - i U i l 2 Tl~i 4 _.- N
- g -
- - 5 o
m - i
~
- r. m ._
m
>b- : :
. l _
-- H : :
e m : w : : m :
- e
~
b :
~
Pt o .
. _ s
-,,,,,,,,,e ,,,,,,,,u,,,,,,,,,u, , , , , , , , _
e' OE ST OT S -0
, OIx Ud '3N1SS3Hd I
I l I
"-*N- * - ~
^' ~
g -* -
e . . (m. ('. . . i { N
>..i+.ij. . .....g C, .
l
- ........,,,,,,,,,,,,,,,,,,,,N
- C 2
X L 3C U, I J :W s . L : P
.m : t - a i i n 2 _. ,
"W U 5 3 .
m _1
- . W E : -
=
E H . 3 ,. N
~ o
.:. 5. , - $, - CD 3
. : C s :,
W - d : e< 3 . O,
~
C L ~ c v . 3 : C
- L 1 -
I o l l O:,,,,,,,,l,,,,,,,,,,,,,,,,,,,,,,J,,.,,l,,,,,,.,,.3 g , 054 CC4 0S9 @ g' s gg 3 *MW3cM3138n1 SS . l l
- M - a a - A - - 2 -
M w.mem =
- 4 h,
4 9 e e
. !a
. N i
C, . . L
. 4 g iiI44 5 1 44 4 6 6 4 4 6 6 + 4 a a .
,g 4 4 446 e a . . .g *
~
X
- c::
- ()
<j : .
i e - W - M
- W
. () <
1 4 . \
- =
l- ..
- - ( 1 -
3
- .a W -
W - m - h,j
~
W CD " (T : = m
~
W W - g : : o-m 1 [- - C3 g . v_ y : : C
.:. S - e :
Q , y- 15 : w a' : : . l : C o
! [- T
- C W M
- : o iE-m.
^.
a
~
- C
~
\. Ch.,,,,,..!,,,.,...l,,,,..,,,l,,,,,,,,,I,,,,,,...I,,..~h O'I 06-0 08-0 04-0 09-0 OS'O Ok-O e JWL4 IS3 W31SAS ABUWIBd e
, , , _r-,, __,_,.~-,-___v.--
- . . . ~ _ . . - - . - .
e i
\
t'. , . .
,s. '
(',.., .i., 6 t
- i
'k o, I s...,. .
..i3.... ...., ........i j. . . . . . . , . . . . . . . . . .
- : 'O -
l t t. ,. .- X i ,.
. cc*
. Et - -
- i 1 -
.- \
~w i p- . _. .
.Lt: .
g i ll . - . o y l . , . N
', ' 36 ,
>" o : : - eA wm - w' .1 2P C : '
H .. - t g :
- M g -
y - . v~ o CC
.: C - 'N i m
~
O y - w - i t -
. c -
O .
- g :
s (f; - - O v i
- o 1
e
! l -
N 1 1 o ,t. -
- C;,,,,,,,,I,,,,,,,,,f...,,,,,,f,,,,,,.,,Ig.
f l 000! 006 008 001. 009 00S 9
9 .. -
* ,, 0 " '
(p (E 1 [ ' ' l
SUMMARY
OF RESULTS
- 1. In the bcse case, peak stecm generator temperatures prior to vessel failure occur in the inlet plenum and are s 850*K, l
- 2. Seal LOCA case very similar to base case,
- 3. When the operator opens the pressurizer PORVs, -
depressurization occurs very rapidly due to the . small water inventory. Accumulator discharge
._ occurs approximately 1400 seconds later, Stecni generator temperatures. are low (4 700 *'K) prior to '
. depressurization below 7 MPa, Temperatures in-crease after complete depressurization but remain L generally lower than'the base case, -
6 . ' T, c. Steam generator
~
- 4. temperatures in the uncertainty
._ _ cases are significantly higher only in the low steam generator flow case where peak temperatures
. cre approximately 150*K higher. -
J ll . R q e E
. _ _ _ . . _ _ . , , . , _ _ . , . . . _ - - , _ . . - , . , . ~ _ . . _ , _ . _ , . . . . . , , . . . . . . . _ _ . _ , _ . _ - , - _ . , . _ , _ , . _ . - - , , . _ _ . . _ - , _ _ . _ _ , , _ _ _ _ - . . _ _ , , , . _ _ _ _ _ _ -
. . . . _ _ __- - _ _ _ _ _ . . ~_ . .
/-bh m
- y,gA, SAL!.Y A. MACK. LICSW l'11 BEVERLY ROAD b BROOKUNE. MASSACHUSETTS 02167 December 12, 1986 Nuclear Regulatory Commission 17i7 H Street, N.W.
, Washington, D.C. 20515 ATTN: Lando Zech, Chaiman .
Dear Mr. Zech:
I am writing to ask that the Nuclear Regulatory Commission carries out
~
a comprehensive, independent investigation into ' alleged safety violations at the Seabrook nuclear power plant before it considers granting the utility a low-power testing license. Fomer employees at the plant have recently come forward and testified. to a long list of alarming conditions and procedures at the construction i site. These include epidemic levels of drug and alcohol abuse on the job, l electrical cables along the inside of containment vessel walls that give l off sparks and ignite small fires, a clogged and inadequate fire protection system, improper mixtures used in the containment cement, empty beer cans and bottles dropped into wet containment cement (which may create air pockets), improper training procedures for various jobs, including delicate welding work, and much more. By now everyone is aware that
- accidents can and will happen at nuclear power plants. At any moment during operation a cooling system, a fire pro-taction system, or a containment building could be tested to its limits, and the health and lives of thousands of people would depend on the integrity of the original design and construction of the plant. -
i Please know that we citizens are aware of the allegations being made p by Seabrook construction workers, and that they will not be satisfied with L the Comission undertaking anything less than a well-designed, well-monitored, L and independent investigation of these claims. [ Thank you for giving your attention to this matter. L Sincerely, b' Sally A. Mack - SAM /ldt 2'7G)L3 bL6 1,_ _ , . - - , _ . _ . . _ _ , ~ _ - . _ . . _ , _ , _ _ . _ _ . . . _ . . _ . _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
- m. . - ._ ___u_...._... . _ . _ . . _ _ . . . . _ . . _ . . _ _ . . . . . . . . . _ _
,7_,_....-
e
, w
(: *< UNITED STATES OF AMERICA . h,'; ] '
'* ~ '
NUCLEAR REGULATORY COMMISSION
- ATOMIC SAFETY AND LICENSING BOARD .g g g g Before Administrative Judges
Helen F. Hoyt, Chairperson (Fr " Emeth A. Luebke 00Cm .:
. Jerry Harbour SERVED DEC 231986 In the Matter of Docket Nos. 50-443-OL 50-444-OL PUBLIC SERVICE COMPANY (ASLBPNo. 82-471-02-OL)
-OF NEW HAMPSHIRE, _e_t,t a_1 (Offsit'e Emergency Planning)
(Seabrook' Station, Units 1 and 2)' ) December 23, 1986 MEMORANDUM AND ORDER Applicants' Petition Under 10 CFR 2.758 and 10 CFR S0.47(c) with Respect To The Regulations Requiring Planning For A Plume Exposure Pathway Emergency Planning Zone In Excess Of A One-Mile Radius together with supporting documents was filed with this Board on December 19, 1986. t As provided by 10 CFR 2.758(b), any other party to this proceeding may file a response,to Applicants' petition by counter-affidavit or otherwise. All responses from the NRC Staff and parties will be filed
;. for delivery in hand to the Board no later than close of business on January 27, 1987. After examination of the responses, the Board will ,
determine if oral arguments are deemed necessary. FOR THE AT MIC SAFETY a AND LIC SING BOARD t l' ' M*f Helen F. Hoyt, Chairpersp' Administrative Judge
'2b l 2- D &17 .
l +rp .
, _ . _ . . . - . . . -- - - ^~ ^ ~' ~ ~^
- a -
7" UNITED STATES OF AMERICA - NUCLEAR REGULATORY COMMISSION In the Matter of I PUBLIC SERVICE COMPANY OF NEW : HAMPSHIRE, ET AL. Docket No.(s) 50-443/444-OL (Seabrook Station, Units 1 and 2) : - CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing LB Memorandum and Order have been served upon the following persons in accordance with the requirements of 10 CFR section 2.712. Administrative Judge Adelnistrative Judge Alan S. Rosenthal, Chairman Sary J. Edles Atomic Safety and Licensing Appeal Atcaic Safety and Licensing Appea,l Board Board U.S. Nuclear Regulatory Coseission U.S. Nuclear. Regulatory Consission Washington, DC 20555 Washington, DC 20555 Administrative Judge Howard A. Wilber Administrative Judge Atomic Safety and Licensing Appeal Helen F. Hoyt, Chairsan Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Coesission' U.S. Nuclear Regulatory Consission Washington, DC 20555 hashington, DC 20555 Administrative Judge Administrative Judge Enneth A. Luebke Jerry Harbour Atomic Safety and Licensing Board Atcaic Safety and Licensing Board U.S. Nuclear Regulatory Consission U.S. Nuclear Regulatory Cossission Washington, DC 20555 Washington, DC 20555 Edwin J. Reis, Esq. Diane Curran, Esc. Office of the General Counsel Harmon & Weiss U.S. Nuclear Regulatory Consission 2001 S Street, N.W. Washington, DC 20555 Washington, DC 20009 Thomas S. Dignan, Jr., Esq. Robert A. Backus, Esc. Races b Gray Backus, Meyer & Solomon 225 Franklin Street 116 Lowell Street Boston, MA 02110 Manchester, NH 03106
~~
,._...._.__~.._. _ . - _ _ _ . _ . . . __ . _ _ . . - . . - . -
+ .,
(. . ' '~ Docket No.(s) 50-443/444 wt k. . LB Memorandus and Order I l Paul McEachern, Esq. Gary W. Holmes, Esq. Shatnes & McEachern Holmes & Ells 25 Maplewood Avenue, P.O. Box 360 47 Winnacunnet Road Portsmouth, NH 03801 Hampton, NH 03842 Judith.H. Mizner Charles P. Grahaa, Esq. Silverglate, Gernter, Baker, Fine, McKay, Murphy and Graham Good and Mitzner 100 Main Street 88 Broad Street Asesbury, MA 01913 Boston, MA 02110 Jane Doughty H. Joseph Flynn, Esq. Seacoast Anti-Pollution League Assista11 General Counsel 5 Market Street Federal inergency Management Agency Portsmouth, NH 03801 500 C fittnet, S.W. Washington, DC 20472 Edward A. Thomas George D. Bisbee, Esq. Federal Energency Management Agency Assistant Attorney General 442 J.W. McCoraack (POCH) Office of the Attorney General Boston, MA 02109 25 Capitol Street Concord, NH 03301 Roberta C. Pevear Carol S. Sneider, Esq. State Respresentative Assistant Attorney General Town of Hampton Falls Office of the Attorney General l Drinkwater Road One Asnburton Place, 19th Floor Hampton Falls, NH 03844 Boston, MA 02108 The Honorable Philip Ahrens, Esq. Edward J. Markey, Chairman l Assistant Attorney General ATTN Linda Correia l Office of the Attorney General Subcommittee on Energy Csnservation and State House Station, #6 Power Augusta. ME 04333 House Committee on Energy and Commerce Washington, DC 20515 Richard A. Hampe, Esq. J. P. Nadeau I Haape & McNicholas Board of Sels.;tsen l 35 Pleasant Street to Central Street Concord, NH 03301 Rye, NH 03870 l l . . . , . ,.
. E
(=- ;- Docket No. (s) 50-443/44. JL ' LB Memorandus and Order
, l Allen Lasport \
Willias Armstrong Civil Def ense Director Town of Brentwood Civil Defense Director 20 Franklin Street Town of Exeter Exeter, NH 03833 ' to Front Street Exeter, NH 03833 Sandra Gavutis, Chairman Board of Selectmen Calvin A. Canney City Manager RFD #1 Box 1154 City Hall Kensington, NH 03827 126 Daniel Street Portsmouth, NH 03'8'01 L Anne Goodman, Chairman Board of Sstectmen William S. Lord 13-15 Newmarket Road Board of Selectmen Durham, NH 03824 Town Hall - Friend Street Amesbury, MA 01913 Peter J. Matthews Mayor of Newburyport City Hall Michael Santosuosso, Chairman Newburyport, MA 01950 Board of Selectmen South Hampton, NH 03827 1 Angie Machiros, Chairman Board of Selectmen Stanley W. Knowles, Chairaan 25 High Road Board of Selectsen Newbury, MA 01950 P.O. Box 710 North Hampton, NH 03862 Norman C. Katner Superintendent of Schools Judith H. Mizner, Esq. School Administrative Unit No. 21 Silverglate, Gertner, Baker, Fine. Alumni Drive Good and Mizner Hampton, NH 03842 88 Broad Street Boston, MA 02110 The Honorable 6 cdon J. Humphrey l- ATTN: Janet Coit United States Senate l' L?ashington, DC 20510 i Dated at Washington, D.C. this ' 23 day of December 1986 j/d, ,
... . ....l Offic f the Secretary of the camassion
@$eE 6 *
. , - - ,,- - - - - , . , , . - -------s,,,m.-.,, _ . - ,
+
,_... _ _m m. -- - - . . - - - - _ . - - -_ _-- - -- - - - -
e 7 l (c. [ o_ UNITED STATES
' ! o NUCLEAR REGULATORY COMMISSION
{ $ WASHINGTON, D. C. 20555
- b.
- 3 8. ESS g
- s e * * ,o Docket No. 50-443 g ff ($ (/0A MEMORANDUM FOR: Vincent S. Noonan, Director PWR Project Directorate No. 5 Division of PWR I.icensing-A FROM: Victor Nerses, Projcect Manager PWR Project Directorate No. 5 Division of.PWR L.icensing-A
SUBJECT:
FORTPCOMING SEABROOK UNIT 2 CONSTRUCTION PERMIT MEETING
- DATE & TIME: Tuesday, January 6, 1987 10:30 a.m.
1.0 CATION
U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Room 110-8 Phillips Building, Bethesda, Maryland PURPOSE: To discuss the actions to be taken to withdraw the *
' construction permit application.
PARTICIPANTS: PSNH-NHY NRC G. Gram V. Nerses, et al. R. Sweeney, et al _
/
~
tor Ne , roject Manager
~
PWR Proft ectorate No. 5 Division)ct D I.icensing-A of PWR cc: See next page
- Meeting between the NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Policy", 43 Federal Register 28058, 6/28/78. Those interested in attending this meeting should make their intentions known to the Pro.iect Manager, V. Nerses at (301) 492-8535, by no later than January 5, 1987.
7 70LO7 %22,
, pp. kJ C Al
f
.-.. (= (-
Mr. Robert J. Farrison Public Service Company of New Fampshire Seabrook Nuclear Power Station cc: Thomas Dignan, Esq. E. Tupper Kinder, Esq. John A. Ritscher, Esq. G. Dana Bisbee, Esq. Ropes and Gray Assistant Attorney General 225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State Fosue Annex-Concord, New Fampshire 03301 Mr. Bruce B. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector ' Post Office Box 330 Seabrook Nuclear Power Station Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Commission Post Office Box 700 Dr. Mauray Tye, President Seabrook, New Hampshire 03874 Sun Valley Association 209 Summer Street Mr. John DeVincartis, Director Haverhill, Massachusetts 01839 Engineering e...J 1.icensing Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 1.owell Street
. Manchester, New Hampshire 03105 Mr. A. M. Ebner, Project Manager United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Post Office Box 8223 Harmon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430 Washington, D.C. 20009 Mr. Philip Ahrens, Esq.
Assistant Attorney General State House, Station #6 Augusta, Maine '04333 Carol S. Sneider, Esq. Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Fall -
, One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire ,
Post Office Box 330 D. Pierre G. Cameron, Jr., Esq. Seabrook, New Fampshire 03874 General Counsel Public Service Company of New Hampshire Seacoast Anti-Pollution f.eague Post Office Box 330
, Ms. Jane Doughty Manchester, New Fampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region I U.S. Nuclear Regulatory Connission Mr. Diana P. Randall 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Hampe Esq.
New Hampshire Civil Defense Agency 107 Pleasant Street Concord, New Hampshire 03301
,- . (; , (. ! l 9 Public Service Company of Seabrook Nuclear Power Station 1- New Hampshire cc: . Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent. City Hall Chairman i l 126 Daniel Street Board of Selectmen Portsmouth, New Hampshire 03801 Town of Salisbury, MA 01950 l Ms. I.etty Hett' Senator Gordon J. Humphrey l Town of Brentwood ATTN: Tom Burack RFD Dalton Road U.S. Senate Brentwood, New Hampshire 03833 Washington, D.C. 20510 Ms.-Roberta C. Pevear Mr. Owen B. Durgin, Chairman Town of Hampton Falls, New Hampshire Durham Board of Selectmen Drinkwater Road Town of Durham Hampton Falls, New Hampshire 03844 Durham, New Hampshire 03824 Ms. Sar fa Gavutis Charles Cross, Esq. Town o- Jensiogtonr, New Hampshire Shaines, Mardrigan and RDF 1 . McEaschern East Kingston, New Hampshire 03827 25 Maplewood Avenue Post Office Box 366 Portsmouth, New Hampshire 03801 Chairman, Board of Selectmen RFD 2
-South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Rye Nuclear Intervention Mr. Angie Machiros, Chairman . Committee .
Board of Selectmen c/o Rye Town Hall for the Town of Newbury 10 Central Road Newbury, Massachusetts 01950 Rye, New Hampshire 03870 h Ms. Cashman, Chairman Jane Spector Board of Selectmen Federal Energy Regulatory Town of Amesbury Commission Town Hall- - 825 North Capital Street, NE L Amesbury, Massachusetts 01913 Room 8105 Washington, D. C. 20426 Honorable Peter J. Matthews Mayor, City of Newburyport Mr. R. Sweeney Office of the Mayor New Hampshire Yankee Division i City Hall Public Service of New Hampshire Newburyport, Massachusetts 01950 . Company 7910 Woodmont Avenue Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 Town of Exeter 10 Front Street Mr. William 8. Derrickson Exeter, New Hampshire 03823 Senior Vice President Public Service Company of Mr. Richard Strome, Director New Hampshire State Civil Defense Agency Post Office Box 700, Route 1 State Office Park South Seabrook, New Hampshire 03874 107 Pleasant Street . Conccrd, New Hampshire 03301 ,
. - .~ - - ~ . - - ~ . - - . - . . - . . . -- - -
# 'o, UNITED STATES
! a NUCLEAR REGULATORY COMMISSION i ,I wasumaTow. o. c.20sse
^
\,*...*/ 0 6 JAN 1987 Docket No. 5n 443 j MEMORANDUM FOR: Vincent S. Noonan, Director PWR Project Directorate No. 5 Division of PWR Licensing-A FROM: . Victor Nerses. Project Manager PWR Project Directorate No. 5 Division of PWR Licensing-A -
SUS.1ECT: FORTHCOMING MEETING WITH PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE TO DISCUSS OP. AFT BROOKHAVEN NATIONAL LABORATORY REPORT ON SEABROOK* 04TE & TIME: Wednesday, January 14, 1987 10:00 a.m.-5:00 p.m.
' LOCATION: Phillips Ruilding 79?O Norfolk Avenue, Room P110-R Bethesda, Maryland PURPOSE: ' To discuss the Brookhaven National Laboratory (BNL) draft l report on their technical review of, the Seahrook l Emergency Planning Sensitivity Study.
PARTICIPANTS: NRC DSNH-NNY BNL S. Newberry D. Maidrand, d d T. Pratt, et al S. Lono V. Nerses, g g Victor Nerses, Project Manager
- PWR Project Directorate No. 5 Division of PWR Licensing-A cc: See next page
- Meetings between the NRC technical staff and appliants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Policy", 43 Federal Register ?8058, 6/78/78. Those interested in attending this meeting should make their intentions known to the Pro.iect Manager, V. Nerses at (301) 492-8535, by no later than January 13, 1987 l
?l& }@@$
3rP
, - . . - .~ - - - ---- ~ ~~ ~ ~ ~
e r .4 Fr. Robert J. Harrison Public Service Company of New Hampshire Seabrook Nuclear Power Station cc: Thomas Dignan, Esc. E. Tupper Kinder, Esq.. John A. Ritscher, Esq - G. Danc Bisbee, Esq. Ropes and Gray Assistant Attorney General 225 Franklio Street Office of Attorney General Boston, Massachusetts 02110 208 State Hosue Annex Concord, New Hampshire 03301 Mr. Bruce 8. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector Post Office Box 330
, Manchester, New Hamoshire 03105 Seabrook Nuclear Power Station c/o US Nuclear Regulatory Commission Dr. Mauray Tye, President Post Office Box 700 Seabrook, New Hampshire 03874 Sun Valley Association 209 Summer Street- Mr. John DeVincentis, Director Haverhill, Massachusetts 01839 Engineering and Licensing Robert A. Backus Esq. Yankee Atomic Electric Company O'Neil, Backus and Spielman 1671 Worchester Road Framingham, Massachusetts 01701 116 Lowell Street Manchester, New Hampshire 03105 Mr..A. M. Ebner, Project Manager United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Harmon, Weiss & Jordan ' Post' Office Box 8223 Philadelphia, Pennsylvania 19101 20001 S Street NW Suite 430 Washington, D.C. 20009 -
Mr. Philip Ahrens. Esq. Assistant Attorney General State House, Station #6 Augusta, Maine 04333 Carol S. Sneider. Esq.
~ Office of the Assistant Attorney General _
Mr. Warren Hall Environmental Protection Division Public Service Company of One Ashburton Place Boston, Massachusetts 02108 New Hampshire Post Office Box 330 D. Pierre G. Cameron, Jr., Esq. Seabrook, New Hampshire 03874 General Counsel Public Service Company of New Hampshire Seacoast Anti Pollution League Post Office. Box 330 Ms. Jane Doughty Manchester New Hampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Diana P. Randall
- 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Hampe, Esq.
New Hampshire Civil Defense Agency i 107 Pleasant-Street Concord, New Hampshire 03301
_ . . _ _ - ---- - - ' - ~ ~ ~ ~
~
.? 3 ,- Public Service Company of New Hampshire Seabrook Nuclear Power Station cc: Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Hall . Chairman 126 Daniel Street Portsmouth, New Hampshire 03801 Board of Selectmen Town of Salisbury, MA 01950 ets, t.etty Hett Town of Brentwood Senator Gordon J. Humphrey RF0 Dalton Road ATTN: Tom Burack Brentwood, New Hampshire 03833 U.S. Senate Washington, D.C. 20510 Ms. Roberta C. Pevear Town of Hampton Falls, New Hampshire Mr. Owen 8. Durgin, Chainnan Drinkwater Road - Durham Board of Selectmen Haepton Falls, New Hampshire 03844 Town of Durham Durham, New Hampshire 03824 Ms. Sandra Gavutis Town of Kensington, New Hampshire Charles Cross, Esq. RDF 1 Shaines, Mardrigan and McEaschern l East Kinoston, New Hampshire 03827 25 Maplewood Avenue Post Office Box 366 Chairman, Board of Selectmen Portsmouth, New Hampshire 03801 .
.RFD 2 South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Mr. Angie Machiros, Chairman Rye Nuclear Intervention Committee Board of Selectmen c/o Rye Town Hall I.
' for the Town of Newbury Newbury, Massachusetts 01950 10 Central Road Rye, New Hampshire 03870 Ms. Cashman, Chairman Jane Spector Board of Selectmen Town of Amesbury Federal Energy Regulatory Town Hall Commission Amesbury, Massachusetts 01913 825 North Capital Street, NE Room 8105
, Washington, D. C. 20426 Honorable Peter J. Matthews
- Mayor, City of Newburyport Office of the Mayor Mr. R. Sweeney City Hall New Hampshire Yankee Division Newburyport, Massachusetts 01950 Public Service of New Hampshire
!. Company . 7910 Woodmont Avenue Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 Town of Exeter 10 Front Street Exeter, New Hampshire 03823 Mr. William 8. Derrickson Senior Vice President Mr. Richard Strome, Director Public Service Company of New Hampshire ! State Civil Defense Agency Post Office Box 700, Route 1 i State Office Park South Seabrook, New Hampshire 03874 107 Pleasant Street Concord, New Hampshire 03301 l l I
fl (AljL'. (
- UU'E T UNITED STATES OF AMERICA 1%
NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD '87 JAN -7 P4 :42 Before Administrative Judges: c y ,- Helen F. Hoyt, Chairperson acc.. ' . . - Emeth A. Luebke 4" Jerry Harbour SERVED JAN 081987 In the' Matter of ) Docket Nos. 50-443-OL 50-444-OL PUBLIC SERVICE COMPANY (ASLBPNo. 82-471-02-0L) 0F NEW HAMPSHIRE, et d . (OffsiteEmergencyPlanning) (Seabrook Station, Units 1 and 2) January 7,1987 MEMdRANDUMANDORDER (Supplement to Board Order of December 23,1986) On December 23, 1986 this Board directed parties to file in-hand responses no later than January 27, 1987 to Applicants' Petition under i 10 CFR 2.758 and 10~CFR 50.47(c) with Respect to the Regulations Requiring Planning for a Plume Exposure Pai.hway Emergency Planning Zone in Excess of a One-Mile Radius. Objections to and motions for reconsideration of the schedule provided in our Memorandum and Order dated December 23, 1986 were filed by the Town of Hampton (TOH) on December 24,1986,- the Massachusetts Attorney General (Mass), on December 30, 1986 and the New England Coalition on Nuclear Pollution (NECNP) on December 31, 1986. The NRC 77Q.LLSN')L55
. N f@
_ , _ _ _ _ _ . , _ . _ _ _ _ _ _ . _ _ _ .____m______ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - " - - - - - - - - - - - - - - ^
7
.g s . - - ~
g c. 2 Staff -on December 22, 1986, in response to Applicants' petition. - proposed that parties be allowed to submit schedules for responses to the petition by January 20, 1987 and that the Board schedule a pre-hearing conference during the week of January 26, 1987, "to discuss and schedule for further proceedings on Applicants' petit. ion." On January 5,1987 NRC Staff's Motion for Reconsideration of Licensing Board Order of December 23, 1986 was filed in which the Staff states its
" technical input will be of crucial importance to a proper detennination by the Licensing Board and by the Commission of the'important issues raised by the Petition." The Staff seeks reconsideration of the December 23, 1986 Order by requesting that a proposed schedule for reply to Applicants' petition be established and that January 20, 1987 be the due date for such schedules.
The Board finds that the authority vested by the provisions of 10 CFR 2.758 is to review the petition and any responses to determine if l the petitioning party has made a prima facie showing that the ,; application of the specific Conmission rule or regulation would not a
- - serve the purposes for which the rule or regulation was adopted and that
, the rule or regulation should be waived or an exception granted. This Board is not directed to conduct an evidentiary proceeding or to decide if a waiver or exception should be granted; this power is reserved to the Commission. Our duty and obligation is to review the petition and
Q. ( .y . 3 any responses and determine if a prima facie showing has been made by the petitioner. The Board affinns that responses will be filed in-hand by close of business on January 27, 1987. We have directed that responses address the Applicants' petition on the issue of whether a prima facie showing for a waiver of the 10-mile EPZ has been made. The Board expects all parties to diligently work to complete their responses by January 27, 1987. If, however, any party cannot complete its response by Janu-ary 27, then that party will provide to this Board by close of business on January 27, 1987, its partially completed response and advise the . Board of a reasonable date certain on which its written response can be completed. In view of the technical nature of the issue, the Board will determine the prima facie issue at hand through written pleadings. No oral hearings to supplement written responses are anticipated. IT IS SO ORDERED. FOR THE ATOM SAFETY AND LICENS GB0$RD k} Helen F. Hoyt, Chairpersory" i Administrative Judge Dated at Bethesda, Maryland this 7th day of January 1987. Although prima facie is not defined in 10 CFR 2.758, one Licensing Board has found it " reasonable to equate ' 3 rima facie' showing with
' substantial' showing." Carolina Power & .ight Company and North Carolina Eastern Municipal Power Agency (Shearon Harris Nuclear Power Plant), LBP-85-5, 21 NRC 410 (1985). We believe, however, prima facie to mean evidence of a sufficient nature that would cause reasonable minds to inquire further.
M A _ _ _ _
a
, s
(':':NUCLEAR UNITED STATES OF AMERICA REGULATORY COMMISSION i-i In the Matter of I l PUBLIC SERVICE COMPANY OF NEW l Docket No.(s) 50-443/444-OL HAMPSHIRE, ET AL. I (Seabrook Station, Units 1 and 2) 1 I I CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing M&O (Suppl. to Bd Order 12/231 have been served upon the following persons in accordance with the requirements of to CFR section 2.712. , Administrative Judge Administrative Judge Alan S. Rosenthal, Chairman Gary J. Edles Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Board Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Administrative Judge Howard A. Wilber Administrative Judge Atcaic Safsty and Licensing Appeal Helen F. Hoyt, Chairman Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Consission U.S. Nuclear Regulatory Canaission Washington, DC 20555 Washington, DC 20555 Administrative Judge Administrative Judge Emmeth A. Luebke Jerry Harbour Atcaic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Consission U.S. Nuclear Regulatory Casaission Washington, DC 20555 Washington, DC 20555 l l~ Edwin J. Reis. Esq. Di'ane Curran, Esq. Office of the General Counsel Harmon & Weiss U.S. Nuclear Regulatory Commission 2001 S Street, N.W. Washington, DC 20555 Washington, DC 20009 i l Thomas 6. Dignan, Jr., Esq. Robert A. Backus, Esq. l Ropes & Gray Backus, Meyer & Solomon l 225 Franklin Street 116 Lowell Street Boston, MA 02110 Manchester, NH 03106 l I
1 .... . . . - . . . . . _ - . - . . - . . - . . . . - - - . . . . L , 98 t Docket No.(s) 50-443/(I 0L ([~ M&C (Suppl. to Bd Order 12/23)
/
Paul McEachern Esq. Gary W. Holaes Esq. Shaines & McEachern Holmes & Ells 25 Maplewood Avenue, P.O. Box 360 47 Winnacunnet Road Portsmouth, NH 03801 Hampton, NH 03842 Judith H. Mizner Charles F. Graham, Esq. Silverglate, Gernter, Baker, Fine, McKay,, Murphy and Graham Good and Mitzner 100 Main Street 88 Broad Street Asesbury, MA 01913 Boston, MA 02110 Jane Doughty H. Joseph Flynn, Esq. Seacoast Anti-Pollution League Assistant General Counsel 5 Market Street Federal Emergency Management Agency Portsacuth, NH 03801 500 C Street, S.W. Washington, DC 20472 Edward A. Thomas George D. Bisbee, Esq. Federal Energency Management Agency Assis. tant Attorney General 442 J.W. McCormack (POCH) Office of the Attorney General Boston, MA 02109 25 Capital Street Concord, NH 03301 Roberta C. Pavear Carol S. Sneider, Esq. Itate Respresentative Assistant Attorney General Town of Hampton Falls Office of the Attorney General Drinkwater Road One Ashburton Place, 19th Floor Hampton Falls, NH 03844 Boston, MA 02108
' The Honorable Philip Ahrens, Esq. Edward J. Markey, Chairman -
Assistant Attorney General ATTN: Linda Correia Office of the Attorney General Subcosaittee on Energy Conservation and State House Ctation, 46 Power Augusta, ME 04333 House Committee on Energy and Commerce Washington, DC 20515 Richard A. Haape, Esq. J. P. Nadeau Hampe & McNicholas Board of Selectmen
, 35 Pleasant St.reet to Central Street Concord, NH 03301 Rye, NH 03870 o
O m-. .ia .. ... o ui iii.
- - - . . = . - - - . _ . . . . . .- - - -
Docket No.(s) 50-443/( . -0L MEO (Suppl. to Bd Order 12/23) 1 Allen Lampert . William Armstrong Civil Defense Director Civil Defense Director Town of Brentwood Town of Exeter 20 Franklin Street to Front Street Exeter, NH 03833 Exeter, NH 03833 Sandra Gavutis, Chairman Calvin A. Canney-Board of telectmen City Manager RFD 01 Box 1154 City Hall Kensington, NH 03827 126 Daniel Street Portsmouth, NH 03801
- Anne Goodman, Chairman William S.* Lord Board of Selectmen Board of Selectmen 13-15 Newmarket Road Town Hall - Friend Street Durham, NH 03824 Asesbury, MA 01913 Peter J. Matthews Mafor of Newburyport Michael Santosuosso, Chairman City Hall . Board of Selectmen . Newburyport, MA 01950 South Hampton, NH 03827 Angie Machiros, Chatraan Stanley W. Knowles, Chairman Board of Selectmen Board of Selectmen 25 High Road P.O. Box 710 Newbury, MA 01950 North Hampton, NH 03862 Norman C. Katner Judith H. M1:ner, Esq.
Superintendent of Schools Silverglate, Gertner, Baker, Fine, School Administrative Unit No. 21 Scad and Mizner Alumni Drive 88 Broad Street Hampton, NH 03942 Boston, MA 02110 The Honorable Bordon J. Humphrey ATTN: Janet Coit United States Senate Washington, DC 20510 Dated at Washington, D.C. this 8 day of January 1987 j/-s
. ___ ____[______ _ _______
Offic the Secretary of the canission
(F V ~
, s
~
. : s.. '
.~.c-. ..2, x ..w .
. .w- n -+
' t.
J. '
. " x. .,:.d; ri -
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION .g ATOMIC SAFETY AND LICENSING BOARD ta h
- Before Administrative Judges: SOCa: :i.
Helen F. Hoyt, Chairperson Enuneth A. Luebke Jerry Harbour SERVED JAN 0 91987 In the Matter of ) Docket Nos. 50-443-OL
) 50-444-OL.
PUBLIC SERVICE COMPANY ) . (ASLBPNo. 82-471-02-OL) 0FNEWHAMPSHIRE,etal. ) (Offsite Emergency Planning) (Seabrook Station, Units 1 and 2) ) January 9,1987 MEMORANDUM AND ORDER (Modifying Board Order of December 4 - 1986) Various parties have submitted requests for the Board to modify 1.ts hearing schedule of December 4,1986 on offsite is' sues raised by the NHRERP. Events have overtaken many of the stated bases for modifica-t tions set out by the parties whose petitions or motions will not be
~
reviewed herein. The Board believes that in the best interests of all parties and the Board, we should clear the deck for,a period of seve:al weeks to permit the 'arties p an unencumbered period to respond to Applicants' petition unoer 10 CFR 2.758 and 10 CFR 50.47(c) to reduce the plume exposure pathway emergency planning zone to one mile. The resulting hearing schedule reafsfon will allow the Board time to consider pending contentions and responses and further advance the date for discovery to commence. As we noted in our January 7,1987 Memorandum and Order, the parties are directed to respond to the issue
. g of whether a prima facie showing for a waiver has been made by the 4pp. Applicants' petition.
.L w I- .
,- 2 In revising the hearing schedule, we have used the same time frames between the various events leading to comencement of hearings as were l
set forth in our December 4,1986 order. We begin with the next' event in the sequence leading to the hearings which is the Board's ruling on contentions and the comencement of discovery. We encourage the parties to respond to requests for information prior to commencement of discovery on February 13, 1987 whenever possible. The new dates are as t follows: Date Deadlines i February 13, 1987 Board Order ruling on contentions, discovery comences. March 6, 1987 Discovery closed (last discovery . request due). March 19, 1987 Answers to last interrogatories due within 14 days after the close of discovery. March 26, 1987 Deadline for motions for sumary disposition on late-filed Rev. 2 Contendons admitted or for other contentions as to which circumstances have changed such that sumary disposition is now appropriate. April 16, 1987 Response oppo~ sing or supporting motions due within 20 days. April 27, 1987 Opposing parties'may file responses to new facts and arguments presented in statements supporting motions for sumary disposition. May 11, 1987 Board Order ruling on =ction: for sumary disposition. May 21, 1987 Prefiled testimony due 10 days after Board ruling on motions for sumary disposition.
- l
.t +,
3 No sooner than Hearings commence. May 28, 1987 (Date depends on arrangements for spaceandlocation.) The Board again directs that service of papers relating to offsite emergency planning contentions be effected by express mail or personal delivery in any instance where nomal service would not result in actual receipt of those papers on or before a deadline for the filing of those papers. As has been thih Board's custom,. the date for filing of any pleading means that the pleading be delivered in hand to the parties and ^
~4kis Board on that date.
i IT IS SG ORDERED.. I - FOR THE AT MIC SAFETY AND LIC SING BOARD , A ' Helen F. Hoyt, Chairper
- Administrative Judge I'
l [ Dated at Bethesda, Maryland this 9th day of January 1987. l. l l. l l i-
- a. . . - . . ~ . , . - - . - . - . . . - - - - . . a -- .- -- ~-:
. 4
~ '
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the' Matter of ; PU*LIC SERVICE COMPf.NY OF NEW ; Docket No.(s) 50-443/444-OL HAMPSHIRE, ET AL. l (Seabrook Station, Units 1 and-2) : i .; i 4 CERTIFICATE OF SERVICE 4 - I hereby certify that copies of the foregoing M&O (Modifying Order of 12/41 4 have been served upon the following persons in accordance with the requirements of 10 CFR section 2.712. 1-
- Administrative Judge Administrative Judge Alan S. Rosenthal, Chairman Gary J. Edles Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Scard Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Administrative Judge Howard A. Wilber Administrative Judge 1 Atomic Safety and Licensing Appeal Helen F. Hoyt, Chairman Board Atoate Safety and Licensing Board U.S. Nuclear Regulatory Commissi.on U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Administrative Judge Administrative Judge Esseth A. Luebke Jerry Harbour Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Consission i Washington, DC 20555 Washington, DC 20555 i
, Edwin J. Reis, Esq. -
Diane Curran, Esq. . Office of the General Counss! Harmon & Weiss U.S. Nuclear Regulatory Commission 2001 S. Street, N.W. Washington, DC 20555 Washington, DC 20009 Thomas 6. Dtgnan, Jr., Esq. Robert A. Back'us, Esq. Ropes & Gray Bac,kus, Meyer & Solomon 225 Franklin Street 116 Lowell Street Boston, MA 02110 Manchester, NH 03106
_ ., a .. _ ... . . . . - . - - - - - ~ - - - ~ ' - - - - - - ~ "
.. ~. . . ' Docket No.(s) 50-443/444-OL M&O (Modifyino Order of 12/4)
Paul McEachern, Esq. Gary W. Holmes. Esc. Shaines & McEachern Holmes & Ells 25 Maplewood Avenue P.O. Dox 360 47 Winnacunnet Road Portsmouth, NH 03801 Hampton, NH 03842 4 Judith H. Mirner Charles P. Graham, Esq. Silverglate, Gernter. Baker, Fine, McKay, Murphy and Grahaa Good and Mitzner 100 Main Street 88 Broad Street Amesbury, MA 01913 Roston, MA 02110 Jane Doughty H. Joseph Flynn, Esq. Seacoast Anti-Pollution League Assistant General Counsel 5 Market Street Federal Emergency Management Agency Portsmouth, NH 03801 500 C Street, S.W. Washington, DC 20472 Edward A. Thomas George D. Bisbee, Esq. Federal Energency Management Agency Assistant Attorney General 442 J.W. McCormack (PQCH) Office of the Attorney General Boston, MA 02109 25 Capitol Street Concord, NH 03301 Roberta C. Pevear Carol S. Sneider, Esq. State Respresentative Assistant Attorney General Town of Hampton Falls Office of the Attorney General Drinkwater Foad One Ashburton Place, 19th Ficor Hampton Falls, NH 03844 Boston, MA 02108 The Honorable Philip Ahrens, Esc. Edward J. Markey, Chairman Assistant Attorney General ATTN Linda Correia Office of the Attorney General Subcommittee on Energy Conservation and State House Station, #6 Power Augusta, ME 04333 House' Committee on Energy and Commerce Washington, DC 20515 Richard A. Hampe, Esq. J. P. Nadeau Haape & McNicholas board of Selectmen. 35 Pleasant Street 10 Central Street Concord, NH 03301 Rye, NH 03870
F^
, . --- -- -- - ' ' ' '" ' ~ ~ ~ ~ ' ' ~
~
, " Docket No.(s,) 50-443/444-OL M&O -(nodif yino Order of 12/4) 4 Allen Lampert William A r r.s t r o n e Civil Defense Director Civil Def ense Director Town of Brentwood Town of Exeter 20 Franklin Street 10 Front Street Exeter, NH 03633 Exeter, NH 03833 Sandra Gavutis, Chairman Calvin A. Canney Board of Selectmen ,
City Manager RFD #1 Box 1154 City Hall Kensington, NH 03827 126 Daniel Street Portsmouth, NH 03801 Anne Goodman, Chairman William S. Lord Board of Selectmen Board of Selectmen 13-15 Newmarket Road Town Hall - Friend Street Durham, NH 03824 Amesbury, MA 01913 Peter J. Matthews Mayor of Newburyport Michael Santosuosso, Chairman City Hall . Board of Selectmen Newburyport, MA 01950 South Hampton, NH 03827 Angie Machiros, Chairman Stanley W. Knowles, Chairman Board of Selectmen Board of Selectmen 25 High Road P.O. Box 710 Newbury, MA 01950 North Hampton, NH 03862 Norman C. Katner Judith H. Mizner, Esq. p Superintendent of Schools Silverglate, Gertner, Baker Fine, School Administrative Unit No. 21 Good and Mizner Alumni Drive 88 Broad Street i Hampton, NH 03942 Boston, MA 02110 [ The Honorable l Gordon J. Humphrey - 1 ATTN Janet Colt United States Senate Washington, DC 20510 i Dated at Washington, D.C..this , l- 9 day of January 1987 l dl, bE
.) 4.L . . . J.- <
Offic he Secretary of the maission
~+n -
..K
. 24. _
'.; 4 T~"
Y . I-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
?? JAN -9 P4 :23 COMilSSIONERS: .
GFF .:. 4-
. Lando W.- Zech, Jr., Chainnan 90 Cab . . *U Thomas M. Roberts. ' ' ~ ~
James X. Asselstine Frederick M. Bernthal Xenneth M. Carr SERVED JAN 0 91987 In the Matter of
) Docket Nos. 50-443-OL-1 PUBLIC SERVICE COMPANY OF ) 50-444-OL-1 NEW HAMPSHIRE, E &. . ) (Onsite Emergency Planning
) and Safety Issues)
(Seabrook Station, Units 1 )
.and 2)
.t ORDER The Comission has decided to review ALAB-853 sua sponte to consider a single issue: whether as a matter of law or policy a utility applicant should be required to submit a radiological emergency plan (either a governmental plan or a utility plan) for the entire emergency planning zone (EPZ) for the facility before any operating ifcense may be issued. The n Commission specifically notes that our taking review does not indicate any position on the merits of the issue. Since the Appeal Board!s interpretation of 10 C.F.R. 50.33(g) in ALA8-853 would be subject to being
- modified or overruled by the Comission, we view it 'as appropriate to resolve the issue now so that a decision on low power ifcensing can be made with Comission guidance in hand. It is undeniable that this matter engages oroad public concern. Accordingly we find that the Commission 87eg %%
(fT -
.. . 2-itself properly should consider and deliver the final agency decision on this issue and should do so before any low power license is issued. In light of the sp;:ellate record already made on the interpretation of 10 C.F.R. 50.33(g) before the Appeal Board, the Comission does not require briefs at this time. However, the following posissive briefing schedule is established for any party who wishes further to develop before the Comission its position on this issue. Page limits on filings are indicated in parentheses. All filings shall be served by hand or by overnight express. By January 21, 1987, any party, including staff if applicable, advocating revision of ALAB-853 may file. (20 pages) By January 27, 1987, any party, including staff if applicable, advocating upholding.ALAB-853 may file a response. (20pages) By February 3,1987, any party, including staff if applicable, advocating revision of ALAB-853 may file a re71y. (10 pages) The Licensing Boards may, of course, make any necessary adjustments to their schedules that fairness dictates.to accomodate the Comission's expedited briefing schedule. The Comission by this order stays the Director of Nuclear Reactor , Regulation (NRR) from authorizing low power operations at the Seabrook facility until the Comission's review is complete. Comissioner Carr disapproved this order and would not have taken review. 4
. . _ . _e ,
It is so ORDERED. [4 or the omission ht% . p
'+9 of ggg i SMUEL J. (RhK i Secretary df the Comission ; Dated at Washingtcn, D.C.
this 9th day of Jarusary,1987. O
.. _m_.._ . . . - _ _ _ . _ . _ _ _
y W. ?. - , *
. UNITED STATES OF AMERICA NUCLEAR REGULATORY' COMMISSION In the Matter of :
PUBLIC SERVICE COMPANY OF NEW Decket No.(s) 50-443/444-OL-1 HAMPSHIRE, ET AL. l < (Seabrook Station, Units l'and 2) : CERTIFICATE OF SERVICE I hereby cert'ify that copies of the foregoino Commission Order (re ALAB-853) have been served upon the following persons in accordance with the recuirements of 10 CFR section 2.712. , Administrative Judge Administrative Judge Alan S. Rosenthal, Chairman Gary J. Edles Atomic S'fety a and Licensing Appeal Atomic Safety and Licensing Appeal Board Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Consission Washington, DC 20555 Washington, DC 20555 Administrative Judge , Howard A. Wilber Administrative Judge .' Atomic Safety and Licensing Appeal Sheldon J. Wolfe, Chairman . Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commissi~on U.S. Nuclear Regulatory Commission' Washington, DC 20555 Washington, DC 20555 Administrative Judge Administrative Judge Emmeth A. Luebke Jerry Harbcur Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Consission U.S. Nuclear Regulatory Commission
- Washington, DC 20555 Washington, DC 20555 Edwin J. Reis, Esq. Diane Curran, Esq.
- t. Office of the General Csunsel Harmon & Weiss
(: U.S. Nuclear Regulatory Commission 2001 S Street, N.W. Washington, DC 20555 Washington, D.C 20009
- Thomas 6. Dignan, Jr., Esq. Robert A. Backus, Esq.
- Ropes & Gray Backus, Meyer & Solomon 225 Franklin Street 116 Lowell Street Boston, MA 02110 Manchester, NH 03106
' ~
j .
-.,,,,,,,,,-,,.--,,n-,wy,y,-- , .-,,,-.--..--,-y,y-, .-.-s-,- .---,---
.-_ _ . . . . . _ . - m. _ .m_ .___ _ _ . . . . . .
o .
; . Docket No.(s) 50-443/444-OL-1
. Commission Order (re ALAB-853) ,
Paul McEachern. Esq. Gary W. Holmes, Esq. Shaines &,McEachern _ Holmes & Ells 25 Maplewood Avenue. P.O. Box 360 47 Winnacunnet Road Portsmouth. NH 03801 Hampton, NH 03042 Charles P. Graham. Eso. Jane Doughty McKay, Murphy and Graham Seacoast Anti-Pollution League 100 Main Street 5 Market Street Amesbury, MA 01913 Portsmouth, NH 03801 H. Joseph Flynn, Esq. Edward A. Thomas Assistant General Counsel Federal Emergency Management Agency Federal Emergency Management Agency 442 J.W. McCormack (POCH) 500 C Street, S.W. Boston, MA 02109 Washington, DC 20472 George D. Bisbee, Esq. Roberta C. Pevear '
- Assistant Attorney General State Respresentative Office of the Attorney General Town of Hampton Falls 25 Capitol Street Drinkwater Road Concord, NH 03301 Hampton Falls, NH 03844 Carol S. Sneider, Esq. Philip Ahrens, Esq.
. Assistant Attorney General Assistant Attorney General Office of the Attorney General Office of the Attorney General One Ashburton Place, 19th Floor State House Station, 46 , Boston, MA 02108 Augusta, ME C4333 The Honorab~1e Edward J. Markey, Chairman R-ichard A. Hampe, Esq.
l ATTN: Linda Correia Hespe & McNicholas Subconcittee on Energy Conservation and 35 Pleasant Street Power Concord, NH 03301 House Committee on Energy and Commerce Washington, DC 20515 J. P. Nadeau Allen Lampert Board of Selectmen Civil Defense Director 10 Central Street Town of Brentwood L Rye, NH 03870 20 Franklin Street Exeter, NH 03933
..j_ ~ .- _ -----.------.:------~-,e-r 1 ".
Docket No.(s) 50-443/444-OL-1 Coenission Order (c'e ALAB-853) Willian Armstrong Sandra Gavutis, Chairman Civil Defense Director Board of Selectmen l Town of Exeter RFD #1 Box 1154 10 front Street . Kensington, NH 03927 Exeter, NH 03833 Calvin A. Canney Anne Goodman, Chairman City Manager Board of Selectmen City Hall 13-15 Newmarket Road 126 Daniel Street Durham, NH 03824 j Portsmouth, NH 03801 . Peter J. Matthews Board of Selectmen Mayor of Newburyport Town Hall - Friend Street City Hall Amesbury, MA 01913 Newburyport, MA 01950 Angie Machiros, Chairman Michael Santosuosso, Chairman Board of Selectmen
- Board of Selectmen 25 High Road
.; South Hampton, NH 03827 Newbury, MA 01950 Stanley W. Knowles, Chairman The Honorable Board of Selectmen Gordon J. Humphrey P.O. Box 710 ATTN Janet Coit North Hampton, NH 03862 United States Senate Washington, DC 20510
. Dated at Washington, D.C. this -
9 day of January 1987 -
,g j Offite f the Secretary of th Commission
( 9 m
- -~ _ - . , .
_ _ ._ - - --- ~
' lh . JAN 2287 10:06 HRC MILLSTONE 1 P02 p% umruo stems
[y \ NUCLEAR REQULATOMY COMMIss10N anonou s .n j e 439 PAftM AVENUE y, ,1 4, j MING OF PRUSSI A. PENNSYLVANIA t 9495 'g gI j Docket Nos: 50-443; 50-444 , g }, . JAN 0 S 1987 Public Service of New Hampchire f ATTN: Mr. Robert J. Harrison P. O. BoxPresident 330 and Chief Executive Officer
, Manchester New Hampshire 03105 Gentlemen:
Subject:
NRC Meeting with Seabrook Licensee i This refers vania on Decemberto a16,meeting 1986 held at the Region I office in King of Prussia, Pe tatives of PSNH. The meeting was conducted at the licensea's reques - are listed in Enclosure 1. Attendees as Enclosure 2. A public meeting notice was published and is attached At this meeting, the licensee indicated that a formal submittal to the NRC l fore the end of the week.ing their Seabrook Station Emergency Planning Sen mittal would be reviewed in the Regf90 f97 ini'Drantion nnly anti or any proposals in this regard were within the purview of NRR and the Atomic Safety 18, 1986,and Licensing Board (ASLB) convened for Seabrook licensing. On December i in the plume exposure pathway emergency planithe licensee did make th
% zone to a one-mile radius.
Additionally, the Regional Administrator inquired wheth and Power had been submitted on the docket. Subsequent discussion with the lican-see indicated that all past and future responses will sub.sitted as pub 11c docu The New Hampshire Yankee (NHY) Senior Vice President also discussed recent N organizational changes and licensee plans regarding Seabrook Unit 2. . No reply to this letter is required. is appreciatod. Your cooperation with us in this matter is
. Sincerely, (AL C4, n EdwardC.Wenzingeyr, hief Projects Branch No. 3 Division of Reactor Projects
Enclosures:
As Stated f s s. 9 70L4 GL6'7 ' 3;:2P
- - = - - - - - - - -
JgH 22 '87 10:07 NRC MILLSTONE i PO'3 - ENCLOSURE 1 MEETING ATTENDEES_ DECEMRFR 16. 1996 E Attendees ' T. Murley Regional Administrator J. Allan,, Deputy Regional Administrator J. Gutierrez, Regional Counsel T. Martin, Director, Division of Radiation Safety and Safeguards (DRSS) E.Bellamy R. Wenzinger, Chief, Projects Branch No. 3, Division of Reactor Projec T. Elsasser,Chief, ChiefReactor Emergency ProjectsPreparedness F.ction 3C, DRPand Radiological Protection Branch W. Lazarus,, Chief. Emergency Preparedness Section, DRSS A. Carne, Senior Resident Inspector D. Ruscitto, Resident Inspector Licensee Attendees W. J. DeDerrickson, v incentis, Director SeniorofVice President, Licensing, NHY New Hampshire Yankee (NHY) Other Attendees , K.Pollutiun) 511baugh, Harmon and Weiss (representing New England Coalition on Nuc .
~
D . 9 t h
- - - . . - - - ~ - . - - - . . ~ . -
. - . . . . . . . - . -.n.. , - - . - . . . - . - . . . . - . .
- - JRN'22 '87 10
- 08 NRC MILLSTONE 1 PO'4
,e ENCLOSURE 2 DEc o s 1986 U.S. NUCLEAR REGULATORY C0>91ISSION No. 46-140 REGION I NOTICE OF LICENSEE MEETI'NG .
Licenses: Public Service Company of New Hampshire Facility: Seabrook Station, Unit 1
. Docket No.: 50-443 Time and Date: '2:00 p.m., December 16, 1986 Location:
Region I Office, King of Prussia, PA (Main Conference Room)
Purpose:
Licensee-Requested Management Meeting to Discuss Plant Status and Schedule, Licensee Emergency Planning Initiatives, and Organizational Changes NRC Attendees: T. Murley Regional Administrator J. Allan , Deputy Regional Administrator W. Kane,, Director, Division of Reactor Projects (DRP) T.(DRSS) Martin, Director, Division of Radiation Safety.and' Safeguards S. Collins Deputy Director, DRP
; E. Wenzinger, Chief, Projects Branch No. 3, DRP
- R.Protection De11any.Branc,h, Chler Emergency DRSS Preparedness and Radiological T. Elsasser, Chief Reactor Projects Section 3C, DRP A. Corne, Senior Resident Inspector D. Ruscitto, Resident Inspector Licensee Attendees:
W. Derrickson, Senior Vice President, New Hampshire Yankee (NHY) J. DeVincentis, Director of Engineering, NHY Note: Attendance by NRC personnel at this meeting should be made known by 4:00 p.m., December 15, 1986, via telephone call to T sapse, Region I at FTS
- - Prepared By /* *
[ - T. C. . Chief, RP5 3C i DJstribution: j V. Ste11o,7r. , Executive Director for Operations J. Requirements Sniezek, Deputy Executive Director for Regional Operations and Generic . J. Taylor, Director, Office of Inspection and Enforcement J. Pset1w, Director, Division or inspection Programs, IE H. Thompson, Director, Division of PWR Licensing A V. Noonan V. Herses,,Licensing Director, Project ProjectMar.agerDirectorate No. 5
' Public Document Room (POR)
Local Public Hearing Document Service List Room (LPOR) e 9 6 _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ - _ _ _ _ . _ . _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ .}}