ML20215B976
ML20215B976 | |
Person / Time | |
---|---|
Site: | Seabrook |
Issue date: | 09/30/1986 |
From: | Atomic Safety and Licensing Board Panel |
To: | |
References | |
CON-#486-1129 OL-1, NUDOCS 8610100013 | |
Download: ML20215B976 (300) | |
Text
c ORIG $AL UNITED STATES NUCLEAR REGULATORY COMMISSION IN THE MATTER OF: DOCKET NO:
PUBLIC SERVICE COMPANY 50-443-OL-1 0F flew HAMPSHIRE, ET AL 50-444-OL-1 (SEABROOK STATION, UNITS 1 & 2)
O . .
LOCATION: PORTSMOUTH, flew HAMPSHIRE PAGES: 325 - 519 DATE: TUESDAY, SEPTEMBER 30, 1986 7~A J/
/Sc/h/1n b,iDrl'c 'ry %'c : <ne & ,
ACE-FEDERAL REPORTERS, INC.
Official Reporters
.W. 444 North CapitolStreet Washington, D.C. 20001 cM 43 02)3G3M p@d0ISkN I
NATIONWIDE COVERACE
_ . _ _ . _ _ _ m._ J
325 UNITED STATES OF AMERICA Sim 1-1 1 NUCLEAR REGULATORY COMMISSION
(~] '
2 BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 3
_______________x 4 .
In the Matter of: :
5 PUBLIC SERVICE COMPANY OF : Docket Nos. 50-443-OL 6 NEW HAMPSHIRE, ET AL. : 50-444-OL
- Onsite Emergency Planninc 7 (Seabrook Station, Units 1 & 2 : and Technical Issues 8 ----------------X 9 Howard Johnson's Motor Lodge Interstate Traffic Circle 10 Salons A & B Portsmouth, New Hampshire 11 Tuesday, September 30, 1986 12 The hearing in the above-entitled matter py 13
(_,1 reconvened, pursuant to recess, at 9:00 a.m.
14 BEFORE:
15 SHELDON J. WOLFE, Chairman 16 Atomic Safety and Licensing Board
! Nuclear Regulatory Commission g 17 Washington, D.C. 20555 h 18 EMMETH A. LUEBKE, Member 0 Atomic Safety and Licensing Board d 19 Nuclear Regulatory Commission y Washington, D.C. 20555
!" 20
, JERRY HARBOUR, Member
! 21 Atomic Safety and Licensing Board.
Nuclear Regulatory Commission l Washington, D.C. 20555 22 23 24 k- 25 l
326 Sim 1-2 1 APPEARANCES:
2 On Behalf of the Applicant:
3 THOMAS G. DIGNAN, ESQ.
KATHERINE A. SELLECK, ESQ.
4 Ropes & Gray 225 Franklin Street 5 Boston, Massachusetts 02110 6 - On Behalf of the NRC:
7 SHERWIN E. TURK, ESQ.
ROBERT PERLIS, ESQ.
8 Office of the General Counsel Nuclear Regulatory Commission g Washington, D.C. 20555 10 On Behalf of the State of New Hampshire:
33 GEORGE DANA BISBEE, ESQ.
Senior Assistant Attorney General 12 Office of the Attorney General State House Annex
/
13 Concord, New Hampshire
/
14 On Behalf of the Seacoast Anti-Pollution League:
15 ROBERT A. BACKUS, ESQ.
JANE DOUGHTY, ESQ.
93 Backus, Meyer & Solomon
, 111 Lowell Street j j7 Manchester, New Hampshire 03105 2
- 18 vu uehalf of the C nunonwealth of Massachusetts:
gg CAROL SNEIDER, ESO.
3 a Assistant Attorney General
! 20 Department of the Attorney General 3 One Ashburton Place, 19th Floor d
g Boston, Massachusetts, 02108 3
i On Behalf of the New England Coalition on Nuclear Pollution:
23 DIANE CURRAN, ESQ.
Harmon & Weiss
-S 20001 S Street, S.W.
'~'
Suite 430 Washington, D.C. 20009 L >
I 327 W I g g E T_ E E T_ E 2 OPENING STATEMENT:
3 Mr. Dignan Page 331 4
WITNESSES VOIR DIRE DIRECT CROSS REDIRECT RECROSS BOARD 5
Newell K. Woodward )
6 358 450 George S. Thomas )347 344 451 481 Joseph M. Salvo ) 479 482 7
Harold Walker 491 495 8
o EXHIBITS 10 IDENTIFIED RECEIVED 11 NECNP Exhibit Number 1 361 473 12 NECNP Exhibit 2 372
() 13 NECNP Exhibit 3 NECNP Exhibit 4 372 376 473 NECNP Exhibit 5 384 473 14 NECNP Exhibit 6 427 473 NECNP Exhibit 7 428 473 15 NECNP Exhibit 8 440 473 NECNP Exhibit 9 445 473 16 NECNP Exhibit 10 517 NECNP E::hibit 11 517 17 L,3,1 - I,,E Q g g U_ E E E ,T_ Q l9 DOCUMENT FOLLOWING PAGE 20 Testimony of Messrs. Woodward, Thomas and Salvo 357 21 Cross-Examination Plan of NECNP 475 22 Cross-Examination Plan of NkC Staff 478 Professional Qualification of Mr. MacDonald 486 23 Testimony of James A. MacDonald and G. S. Thomas 487 O(, 24 Testimony of Donald J. Perrotti and
- * ' " * " " ' " ' - Gordon R. Bryan 489 25 1 ,
327-A uW I LAY -
I N_ D 0 C_ U M E_ N T S_
2 DOCUMENT FOLLOWING PAGE 3 Supplemental Testimony of Harold Walker 494 4
5 6
7 8
9 10 11 12
- ~
kJ 13 14 15 16 17 18 19 20 21 22 23 x _,/ 24 Ace-Federal Reporters, lac.
25 1
2
328 1
Sim 1-4 1 P R O C E E-D I N G S
( 3 2 JUDGE WOLFE: All right, the evidentary hearing
'v 3 is resumed.
4 A query to all parties. Have all parties 5 handed to the Board their cross-examination plans upon 6 all three issues?
7 MS. CURRAN: I still have another set to hand 8 to the Board.
9 (;Ms . Curran handed the documents to Judge 10 Wolfe.)
11 JUDGE WOLFE: And you are handing to the Board?
12 MS. CURRAN: The cross-examination plan for 13 the NRC witnesses and Contention IB2.
( 's JUDGE WOLFE: And you are?
34 15 MS. SNEIDER: Ms. Sneider.
g3 JUDGE WOLFE: And what are these, Ms. Sneider?
3 j7 MS. SNEIDER: This is the cross-examination
- g3 plan for SALP Contention 6.
a e
j g3 (Ms. Sneider handed the documents to Judge a
l 20 Wolfe.)
g d JUDGE WOLFE: All right, the Commonwealth of 21 h
- Massachusetts has handed their cross-examination plans 22 23 f r SAPL Supplemental Contention 6, copies of which I hand to our Board members.
(n,) 25 MS. DOUGHTY: SAPL also has a cross-examination
,c *
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..:. . .,a :, u. . ; , , ..
329 Sim 1-5 -
Mr. Backus has:it. lI! assume they are here.
1 plan.
2 ' JUDGE WOLFE: Any other~ cross-examination 3 plans?
4 Have you, Mr. Turk, submitted all of your
.5 cross-examination plans?
6 MR. TURK: Yes/.we have; ' ,"
7 JUDGE WOLFE: And, Mr. Dignan, you have 8 cross-examination plans?
9 MR. DIGNAN: I'have submitted no cross-examina-10 . tion plans at all.
11 JUDGE WOLFE: You do not intend to cross-12 examine?
- 13 MR. DIGNAN: No.
d 14 JUDGE WOLFE: Mr. Bisbee?
MR. BISBEE: I have submitted none, and I 15 16 have no intention of cross-examining on these issues.
s 17 JUDGE WOLFE: All right.
.h -
18 MR. BACKUS: Are~you awaiting cross-examination J 19 Pl ans from us?
a 3
20 JUDGE WOLFE: Yes.
d (;Mr . Backus handed documents to Judge Wolfe.)
21 3
2 JUDGE WOLFE: All right, we have the cross-22 examination plans by those parties who are going to cross-23
- ""I""*
24 At the conclusion of the respective parties' 25
~
330 Sim 1-6 1 cross-exa'mination, in' the event that I am forgetful, and 2 I am occasionally forgetful,tso would the parties' counsel
- V 3 indicate that cross-examination has been completed and 4 request me.to incorporate into the record copies of their 5 cross-examination plans.
6 As you know, copies have not been given to 7
'other counsel, but they are to be made part of the record 8 after the completion of the individual counsels' cross-g examination.
10 MR. BACKUS: Mr. Chairman, I am informed j,
by the. members of the audience that they having difficulty 12 hearing. I don't know if anything can be done about that, 13 but it just requires that we all attempt to speak up. I 14 don't think those microphones are providing any benefit to the people in the back.
15 e a r a ra sed 16 3
4
- g back there, you can't hear?
e FROM THE-FLOOR: Can't hear, sir.
g 18 0
JUDGE WOLFE: All right.
- l - 19 a
l 20 Mr. Dignan, you had started your opening g
f 21 statement. Would you please begin anew.
! MR. DIGNAN: Your Honor, at the time we recessed yesterday.
(Disturbances from the audience.)
24 JUDGE WOLFE: Now let's stop the comments
-+
w_, a +
}
. 331-Sim.1-7 1' from the audience, please. Everyone.should speak directly
(~s. 2 into t' heir microphones so that the audience can hear. No N
ss !. .
l 3 other comments-now. l 4 Please proceed.
5 MR. DIGNAN: Your Honor, at the time that.
6 .we recessed yesterday I had briefly described the three 7 reopened contentions, and I was continuing.
8 The fourth contention before you is a 9 contention numbered SAPL Supplemental Contention 6. This to contention-is the subject of an evidentiary hearing for 11 the first-time.
6 12 Partial summary disposition has been granted s -13 with respect to this contention, and the only issue O 14 remaining for trial under the contention is the issue of 15 whether or not there still exists reasonable assurance 16 that the health and safety of the population located near
, h 17 the plant will be protected during the period of operation 2
- 18 prior to the first refueling outage even if certain a
3 ig additions to the safety parameter display system, .otherwise a
20 known as the SPDS, which had been suggested by the staff
'd of the Nuclear Regulatory Commission, are not made until 21 22 that outage.
23 It has been agreed that the order for hearing 24 at this session will be as follows:
( 25 The first issued tried will be the environmental
L 332 Sim 1-8 1 qualifiaction issue followed by the SPDS issue and, finally, there will;.be testimony with respect to,the EAL issue.
.%'() '. 2 3 Turning first to the enviromental qualification 4 issue. The applicant will;present a panel of three 5 witnesses. The first of these is Mr. Joseph M. Salvo,.who 6 is seated at my right in the center of the table. He is 7 the senior mechanican engineer with Yankee Atomic Electric 8 Company in Framingham, Ma'ssachusetts.
9 Mr. Salvo holds a bachelor's and master's to degree in mechnaical' engineering from Northeastern Univer-ij sity, as well as a master's degree in applied management 12 fr m Leslie College. He is a registered professional 13 engineer in the Commonwealth of Massachusetts and the State
.fh 14 f New Hampshiro and is a member.of-the American Society f Mechnaical Engineers.
15 16 Mr. Salvo began his engineering career at s
j 37 Stone and Webster as an engineer in the Engineering 2
$ 18
. Mechanics Division, during which time he was responsible 3
jg for computer modeling and finite element analysis.
)
a E In 1977 he joined Gall Incorporation where g 20 he held the position of Senior Engineer responsible for
-! the design analysis and performance testing of all pumps for Navy and nuclear applications. He also coordinated the seismic environmental testing of this equipment.
j In 1982 Mr. Salvo joined the Yankee Atomic
r Sim 1-9 333 1 as a member of the systems group assigned to the.Seabrook
(~ 2 Project. His areas of responsibility included coordination
%.)
3- of the HVAC portions of the project, construction inter-4 face activities and various special projects.
5 For the psat year Mr. Salvo has been respon-6 sible for the coordination and review of the equipment 7 qualification program for Seabrook Station.
8 The second member of the panel seated to my g far right is Newall K. Woodward. Mr. Woodward holds 10 his bachelor of science degree from Charter Oak College ij and has taken the course in U.S. Naval Nuclear Power and 12 Prototype training, as well as various military courses 13 encompassing the operation, maintenance and troubleshooting
/ :
, /
x' of specific nuclear plant and submarine systems.
34 He is a member of Phi Tau Signa, the National 15 Honorary Mechanical Engineering Fraternity, and a member 16 of the American Nuclear Society Standards Committee,
{ 97 e
- 18 ANS 56.3.
3 0
From 1968 to 1974 he served abord the USS j 19 a
$ ULYSES S. GRANT, nuclear submarine SSBN 631, where he was g 20 d the nuclear trained engineering watch supervisor.
21 h
- After leaving the Navy he joined Morse Nutes 22 and Company in the Energy Systems and Services Division where, among other things, he was the senior quality
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( ,) control inspector.
r a
334 1 .
Sim 1-10 In October 1976-he joined Combustion. Engineering 2
t.f~~)- -
-- where he was a neulear steam supply system design J v
3 .
engineer. >
4 In March of 1980 he joined his present employer, Impel' Corpora' tion, where'he has since then'been 6
the supervicing engineer in charge of supervision and 7
approval of all electrical and mechanical enviornmental 8
equipment qualification work for utility plants with 8
nuclear power plants.
10 He was the project engineer for the preparation 11 of the electrical and mechacal equipment EP files for 12
'end Sim Seabrook Station.
LSue fols g 13 14
'15 16
= 17 j 19 i
20 f
21 it 22 23 24 25
335 0?,1-SueW~ l The third member of the panel is George S. Thomas.
)
.v 2 I might note that Mr. Thomas has already qualified as an 3 expert witness and has testified in the August 1983 hearings.
4 Mr. Thomas is now the Vice President of Nuclear Production for 5 Public Service Company of New Hampshire.
6 He holds a B.S. and an M.S. degree in mechanical 7 engineering from the University of Massassachusetts and 8 Northeastern University, respectively, on graduation from 9 the University of Massachusetts, he became employed by the 10 General Dynamics Electric Boat and Quincy Divisions where he 11 supervised the initial startup of a number of submarine 12 reactors.
(#)
13 In 1967 he joined Babcock and Wilcox as a design 14 engineer where he performed thermo-fluid studies for the 15 design of light water and liquid metal reactor components.
16 In 1969 he joined Yankee Atomic Electric Company 17 participating in the Yankee Rowe training program, and in 18 1970 was appointed Preoperational Test Coordinator for 19 Vermont Yankee Nuclear Power Station.
20 While at Vermont Yankee, he qualified for a 21 senior reactor operators license at that station. And, in 22 1973 was appointed to the position of Assistant Station 23 Superintendent for Vermont Yankee.
, ( 24 In 1977 he was appointed Startup Engineer for Aco Federal Reporters, Inc.
25 the Seabrook project. And in 1978 he became the Startup
336
- 2 -SueW 1 Manager for Yankee Atomic Electric Company and established 2 the Yankee Atomic Electric Company Startup Test Group at 3 Seabrook Station.
4 He was an active participant in the TMI post-5 accident evaluation.
6 In September of 1980 Mr. Thomas was appointed to 7 the position of Nuclear Production Superintendent of 8 Public Service Company of Uew Hampshire and was appropriate 9 officer with overall responsibility for the operation of 10 Seabrook Station.
11 In June of 1982 he was elected to his present 12 position of Vice President of Nuclear Production with full-1 13 time responsibility for the operation and operational support 14 of Seabrook Station.
15 I should note with respect to Mr. Thomas that he 16 will appear as a member of all of the panels and has reviewed, 17 and is prepared to defend along with his fellow panel members, 18 all of the testimony that the Applicants will be introducing.
19 However, Mr. Thomas was not the author or principle author 20 of the testimony.
21 His function as a member of each of the panels 22 will be to provide a management position on any policy or 23 other type of questions that may come up either from cross-() 24
/,co-Federal Reporters, Inc.
examination by the parties or questions from the Board.
25 In its testimony, the environmental qualification
~
s 337 i
- 43-SueW. I panel will begin by describing the objectives of environmental (U 2 ' qualification and the: standard by.which it is conducted.
4 3 They will explain that for Seabrook the time duration objective 4 for all equipment that had to be environmentally qualified 5 was one year.
6 In.the case of any equipment that was not qualifiable 7 .for one year, an engineering justification was done which 8 would demonstrate the appropriateness of a shorter period of 4
9 time. For example, it might be found that although a certain 10 piece of equipment would only be qualified in a harsh environ-11 ment for two months, the fact is that the only safety function i
j 12 that it had to perform in the event of an accident would be 4
0 13 accomplished within hours of the happening of the accident 14 and that, therefore, there was no need to be concerned with the i
I 15 fact that this particular piece of equipment could not qualify 16 as operable in the harsh environment for a full year. ,
i 17 The panel next addresses each of 11 items that were 18 not qualified for one year at the time when Staff Safety F
19 -Evaluation Supplement Number 5 was issued.
20 Their testimony will be that two of the items have 4
21 since been found to be qualified for one year. And, with 22 respect to the other nine items, an engineering justification l
l
, 23 is made that they will remain qualified for the time l ( 24 necessary to perform their safety function.
A.e dere n.porms, inc.
25 In addition, the panel will address certain concerns I
_ ._ , _ , . . _ . , , _ . _ _ . , . , . , - - _ _ - - . , _ - . . ..m_~. . . _ . _y- __._._. - - . _ _ _ _ . _ _ , _ _ _ , , . . .
338
- 4-SueW I set forth by the New England Coalition on Nuclear Pollution in 2 a pleading filed in opposition to the request by this 3 Applicant for its five percent low power license.
4 On the basis of the testimony of the environmental 5 qualification panel, we will ask the Board to find and rule 6 in favor of the Applicant with respect to NECNP Contention 7 1.B.2.
8 Turning now to the second matter which will be 9 tried, SAPL Supplemental Contention Number 6. As I noted 10 earlier, the issues to be tried is whether or not there 11 still exists reasonable assurance that the health and safety 12 of the population residing near the plant will be protected O 13 even if certain items which have been suggested for inclusion 14 in the SPDS by the Staff are not added to the SPDS until the 15 first refueling outage of the Seabrook Station.
16 The panel, with respect to this issue for the 17 Applicant will consist of Mr. Thomas and Mr. Lawrence A.
18 Walsh, who is the Operations Manager for the Seabrook Station.
19 After some five years in the navy, which included 20 service aboard the nuclear submarine, U.S.S. Lafayette and duty 21 as a qualified reactor operator on the S5W plant, Mr. Walsh 22 became employed by Connecticut Light and Power Company where, 23 after two years with that Company, he was assigned to the
( 24 startup crew at the the Connecticut Yankee Atomic Power Ase-Federal Reporters, Inc.
25 Plant.
339
- 5-SueW i .He was a member of the staff during construction 2 and startup of that station and became a licensed reactor 3 operator for that station.
4 In 1970 he transferred to Main Yankee Atomic Power 5 Company to assist with with plant acceptance from the Nuclear 6 Steam Supplier and the Architect Engineer. He has assisted 7 with the instruction of prospective operating license holders 8 and formulated the initial procedures for the plant operations 9 at that station. He was promoted to Assistant Department Head 10 for Plant Operations.
11 While at Maine Yankee, he held an NRC senior 12 operation license. In 1978, he transferred to Public Service
(~
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13 Company of New Hampshire where he assumed his present duty 14 as Operations Manager for Seabrook Station.
15 As you can see from his qualifications, which I 16 have recited, as well as the more detailed statement thereof 17 in the qualification sheets which will be introduced, Mr.
18 Walsh has had extensive hands-on experience in reactor control 19 rooms and has a thorough knowledge of what it takes to assure 20 that an operator has the necessary information to react 21 appropriately in an emergency.
22 The testimony offered by the Applicant's panel 23 with respect to the SPDS will first demonstrate that the SPDS
() 24 Aeofadoral Reporters, Inc.
is not a safety system as such, and that indeed even without 25 the SPDS all of the information which is on the SPDS is
340
(6-SueW 1 otherwise available in the control room to the operators.
U 2 Next, the witnesses will take up each of the items 3 which the staff has suggested for conclusion in the SPDS, which 4 are at issue in this proceeding.
5 The testimony will reveal that a few of these 6 items have already been included in.the SPDS. And with 7 respect to each of the others, the witnesses will describe 8 'why, in their judgment, awaiting the first refueling outage 9 to make the addition, if it is to be made at all, will in no 10 way place in jeopardy the health and safety of the public.
II On the basis of this testimony, we will ask the 12 Board to find and rule in favor of the Applicant with respect O 13 to the remaining issue outstanding under Contention SAPL 14 Supplement Number 6.
15 Turning now to the EAL issue, the panel on tnis 16 will be Mr. Thomas and Mr. James A. MacDonald,the Radiological 4
17 Assessment Manager, Public Service Company of New Hampshire.
18 These are the two gentlemen who testified with respect to 19 this topic during the August 1983 hearings.
20 I have already described Mr. Thomas' qualifications.
21 Briefly, with respect to Mr. MacDonald,:he received his 22 Bachelor of Science in nuclear engineering from Lowell 23 Technological Institute in 1968, and a Master of Science in
() 24 Asefederal Reporters, Inc.
radiological health from Harvard University in 1970. He is 25 also a graduate of the Health Physics Training Program y , , , -y.
, , . - . . - . - - - - 3-..,. . . _ . -
, .,r 1-,..
i-i- j 341 i
' l sponsored by Brookhaven National Laboratory and the then f^']-7-SueW 2 existing U.S.-Atomic Energy Commission.
3 y Mr. MacDonald joined Yankee Atomic Electric 4 Company in May of 1970 as an engineer within the Radiation
!. 5 Protection Section. In 1972, he. transferred to the Safety 6 Analysis Section where he worked in the Source Term and Dose 7 Evaluation areas. These evaluations were performed for 8 '
i radioactive releases associated with normal plant operation 9 and for releases associated with accident conditions.
10 In October of 1973, Mr. MacDonald was appointed Il p to the position of Manager of the' Radiation Protection Group
! 12 at Yankee in which capacity he directed the activities of i h 13 that group which included both licensing assistance in the
. 14 radiation protection area for plants under design and i 15 construction and operational health physics for operating i
j 16 plants.
17 In August of 1983 he joined Public Service 1
18 Company of New Hampshire as the Radiological Assessment ,
19 Manager with responsibility for implementation of the 20 Seabrook Radiological Emergency Plan, a position which he 4
[ 21 now holds.
22 Mr. MacDonald is a member of the Health Physics 23 Society and is certified in the field of health physics by
()
. Ameedores Reporten. Inc.
24 the American Board of Health Physics.
25 The testimony of the Applicant's panel will once
342
- 8-SueW I again give a brief description of the emergency classification 2 scheme. They then go on to deal with items which were left 3 open as of the conclusion of the August 1983 hearings.
4 These items include the then lack of specific set-5 points for Seabrook Station, the then failure to have full 6 utilization of an in-station radiation monitor indications 7 within the classification system and the completion of the 8 comparison of the Seabrook Station classification system with 9 the guidance of NUREG 0654, Appendix I, Example Emergency 10 Events.
end #2 11 12
(' ~
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13 14 15 16 17 18 19 20 21 22 23
~s s _,) 24 Ace-Federal Reporters, !nc.
25
3-1-gjw 343 i In addition, the witnesses will testify that training s
2 has been completed with respect to the emergency classification 3 sys tem, and that state approval of the emergency action levels 4 have been obtained.
5 The witnesses will conclude by indicating that all 6
of the items that were open as of the conclusion of the 7 August 1983 hearing have now been resolved.
On the basis of all the testimony described, and 8
9 the testimony given in August of 1983, we will ask the' Board 10 ~for findings and rulings in favor of the Applicant on 11 Contentions NECNT-31 and NH-20.
12 On the basis of this and the balance of the record 13 that has been generated in this proceeding, the Applicants will 14 then ask the Board to issue a partial initial decision 15 authorizing operation of Seabrook Station Unit 1 up to a 16 level of five percent of rated power.
17 Thank you very much, and I am prepared to go forward 18 with my witnesses at this time.
19 MR. BACKUS: Mr. Chairman, as to the SPDS contention, 20 I just want to advise the Board and parties that we believe 21 that this issue involves not merely a question of reasonable 22 assurance, but also a question of whether under 10 CFR 50.57 23 Sub A, Sub 2, the facility will operate in conformity with the
() 24 Ase-Federal Reporters. Inc.
application as amended under the provisions of the rules and 25 regulations of the Commission.
34 4
i' 3-2-gjw
,2s 1 That is, we think the SPDS contention is not limited U 2 to whether it can be reasonable assumed the SPDS in its present 3 condition will provide protection for the public,but whether 4 it needs to meets the requirements of NUREG 0737, Supplement 1.
5 And that that is a separate and distinct question 6 on which this Board will have to rule, and I wanted the Board 7 to be aware of our legal condition on that.
8 It is our position that it does not.
9 JUDGE WOLFE: All right. Will the witnesses stand 10 please, and raise your right hand.
11 Whereupon, XX INDEX 12 NEWELL K. WOODWARD, O
b 13 AND 14 GEORGE S. THOMAS, 15 AND 16 JOSPEH M. SALVO, 17 Were called as witnesses on behalf of the Applicants, and 18 having first been duly sworn, testified as follows:
19 MR. DIGNAN: Is it all right for me to go 20 forward, Your Honor?
21 JUDGE WOLFE: Yes.
XX INDEX 22 DIRECT EXAMINATION 23 BY MR. DIGNAN:
() 24 Aso-Federal Reporters, Inc.
Q Mr. Thomas, I will begin with you. You have before 25 you a one page document entitled: George S. Thomas, Vice
~ _ . . . _ . . , _ _ _ . , -, _ _ ___ ___
3-3-gjw 345
,, i President - Nuclear Production.
/ \
(_) Is that a statement of your professional background 2
3 and qualifications?
4 A (.Mr. Thomas) Yes, it is.
5 MR. DIGNAN: Your Honor, at this time I ask that 6 a one page sheet, headed: George S. Thomas, Vice President -
7 Nuclear Production, be admitted into evidence and incorporated 8
at this point into the transcript of this proceeding as if 9 read.
10 JUDGE WOLFE: I ask for an objection.
11 MS, CURRAN: Before; the Applicants testimony is 12 submitted, I would like to examine the qualifications of the 7
k~l 13 witnesse s .
i 34 JUDGE WOLFE : All right. Shall we incorporate 15 the respective qualifications into the record, and you may 16 then proceed with voir dire, or which ever you prefer.
17 MS. SURRAN: That is fine.
18 JUDGE WOLFE: Will you present and incorporated 19 into the record the qualifications of all three witnessed.
20 MR. DIGNAN: Do I understand the ruling is that Mr. Thomas 's has been admitted, and may be incorporated, 21 i
22 Your Honcr.
23 JUDGE WOLFE: I thought I would incorporate them
) 24 all at the same time. You make the offer.
l Asofederal Reporters, Inc.
I 25 MR. DIGNAN: Yes, Your Honor. I will be glad to.
I
6 3-4-gjw. 346 t
1 BY MR. DIGNAN: (Continuing) 2 Q Mr. Woodward, before you is a two page document 3 entitled, Resume - Newell K. Woodward. Is that a statement 4 of your professional background and qualifications, sir?
5 A (Mr. Woodward) Yes, it is.
6 Q Mr. Salvo, before you is a one page document, and 7 headed Joseph M. Salvo, Senior Mechanical Engineer. Is that 8 a statement of your professional background and qualifications?
9 A (Mr. Salvo) Yes, it is.
10 MR. DIGNAN: At this time, Your Honor, I would ask 11 that they be admitted into evidence and incorporated into j 12 the transcript of the proceedings as if orally read at this h 13 point. A one page document entitled George S. Thomas, Vice 14 President Nuclear Production; a two page document entitled, 15 Resume, Newell K. Woodward, and a one page document entitled, 16 Joseph M. Salvo, Senior Mechanical Engineer.
17 JUDGE WOLFE: Said documents reflecting the quali-18 fications of the three witnesses are incorporated into the 19 record as if read.
20 MR. DIGNAN: And admitted into evidence, Your 1
21 Honor?
22 JUDGE WOLFE: And admitted into evidence.
23 (Above mentioned documents follow.
() 24 Aes Federst lioporters. Inc.
1 25
- - - - - -- - ,.,------,----.,----------,,-..--r- ------w --
4 ,-- . .c.. -% . - . - - --- --s. , m - - + - - - - re- . ----
JOSEPH M. SALVO V]
/
SENIOR MECHANICAL ENGINEER EDUCATION B.S. Mechanical Engineering, Northeastern University, June 1973 M.S. Mechanical Engineering, Northeastern University, June 1974 M.S. Applied Management, Lesley College, May 1986 PROFESSIONAL AFFILIATIONS / REGISTRATIONS Registered Professional Engineer (Mechanical), Commonwealth of Massachusetts Registered Professional Engineer (Mechanical, HVAC), State of New Hampshire American Society of Mechanical Engineers Mr. Salvo joined the Yankee Staff in February,1982 as a member of the Systems Group, assigned to the Seabrook Project. His areas of responsibility included coordination of the HVAC portions of the project, construction interface activities, FSAR preparation and review, as well as various special projects.
For the past year Mr. Salvo has been responsible for the coordination and
_ (. ) review of the Equipment Qualification Program for Seabrook.
Mr. Salvo came to Yankee from Gaulin Corporation, where he was employed from 1977 to 1982. He held the position of Senior Engineer responsible for the design, analyses and performance testing of all pumps for governmaat~
(U.S. Navy) and nuclear applications. He also coordinated the seismic and environmental testing of this equipment when required.
Between June 1973 and March 1977 Mr. Salvo was employed by Stone and Webster as an engineer in the Engineering Mechanics Division. There he was responsible for computer modeling and finite element analysis.
- l O
V
9 RESUME 1.-
NEWELL K. WOODWARD
'd
SUMMARY
OF QUALIFICATIONS:
Eighteen years experience in the commercial and naval nuclear power industry. Extensive experience in nuclear power plant design, con-struction, licensing, operation, and refueling. Supervision and direct participation in the design, procurement, installation, test, operation, and repair of nuclear power plant electrical and mechanical equipment.
PROFESSIONAL EXPERIENCE:
March, 1980 to present:
Icpell Corporation, Melville, New York Supervising Engineer Supervision and approval of electrical and mechanical environmental equipment qualification (E.Q.) work at Impell for utility clients with nuclear power plants. Proj ect Engineer for the preparation of electrical and mechanical equipment E.Q. Files for Seabrook Station.
October, 1976 to March, 1980:
Combustion Engineering, Inc. - Power Systems Division, Windsor, CT NSSS Design Engineer Responsible for the design, technical, and licensing support of a variety of special projects relating to the Reactor Coolant, Steam Supply, Main Feedwater, Condensate, and Auxiliary Feedwater Systems.
These projects included the analysis, design, and operation of system backfits to meet regulatory requirements, system design reviews with respect to regulatory requirements, and utility requested design evaluations.
1974 to 1976:
Morrison-Knudsen Co. , Inc. - Energy Systems and Services Division, West Milton, NY Senior Quality Control Inspector (1975 - 1976)
Shift Ref ueling Engineer (1974 - 1975) i
f l '
RESUME (CONT'D) NEWELL K. WOODWARD 1974 - 1976:
) (CONT'D)
Direct involvement and supervision of the refueling, overhaul, and modification of 3 Naval Prototype Pressurized Water Reactor Plants.
Responsible for monitoring and certifying reactor plant se rvicing procedures, nuclear and non-nuclear welding, brazing, system testing, pressure vessel and f uel lif ting and handling equipment, and nuclear plant materials. Certified to perform non-destructive testing in accordance with NAVSHIPS 250-1500-1, with civilian certification to ASNT/TC-1A, Level II. Extensive experience in the theory, main-tenance, and operation of automatic Omega seal welding and cutting equipment.
1968 - 1974:
United States Navy - U.S.S. Ulysess S. Grant (SSBN-631)
Nuclear Trained Engineering Watch Supervisor Responsible for the supervision of 10 technicians who operated the mechanical, electrical, and reactor controls equipment of a Naval Nuclear Submarine Propulsion Plant. In addition, as Machinery Division Leading Petty Of ficer was responsible for the supervision and training of 15 technicians who maintained the mechanical equip-ment associated with the reactor plant and the steam propulsion plant.
EDUCATION AND TRAINING:
Bachelor of Science, Charter Oak College, 1980 University of Hartford, Four Semesters Colgate University, Three Semesters Mitchell College, Three Semesters U. S. Naval Nuclear Power and Prototype Training Various Military schools encompassing the operation, maintenance, and troubleshooting of specific nuclear plant and submarine systems and eq ui pme nt .
Professional Affiliations:
Pi Tau Sigma, National Honorary Mechanical Engineering Fraternity American Nuclear Society Standards Committee ANS 56.3.
SB 1 & 2 Amendmant 53 FSAR August 1984
() GEORGE S. THOMAS
.VICE PRESIDENI - NUCLE.iR PRODUCTION 47 Mr. Thomas received his Bachelor of Science Degree in Mechanical Engineer-ing (cum laude) from the University of Massachusetts in 1965 and his Master of Science Degree in Mechanical Engineering from Northeastern University in 1982.
Upon graduation from the University of Massachusetts, he was employed 63
- by General Dynamics Electric Boat and Quincy Divisions where he qualified as an SSW Senior Nuclear Test Engineer and supervised the initial startup of a number of submarine reactors.
In 1967 he joined Babcock and Wilcox Company as a Design Engineer and performed thermo-fluid studies for the design of light water and liquid metal reactor components.
In 1969 he joined Yankee Atomic Electric Company and participated in the Yankee Rowe Operator Training Program.
In 1970 he was appointed Preoperational Test Coordinator for Vermont 4
Yankee Nuclear Power Station.
In 1972 Mr. Thomas qualified for a Senior Reactor Operators license at Vermont Yankee.
O In 1973 he was promoted to the position of Assistant Station Superin-tendent of Vermont Yankee. In this position he was directly responsible for
- operation, maintenance, and technical support of the Station. He personnally directed initial power escalation testing and several refueling outages.
During the cumulative period 1975 to 1977, Vermont Yankee attained the highest capacity factor of a domestic Boiling Water Reactor.
In 1977 Mr. Thomas was appointed Startup Engineer for the Seabrook Pro-ject. In 1978 he became Startup Manager for YAEC and established the YAEC Startup Test Group at Seabrook Station.
Following the Three Mile Island accident, he actively participated in the TMI recovery organization and the post-accident evaluation performed by EPRI-NSAC.
L In September 1980, Mr. Thomas was appointed to the position of Nuclear Production Superintendent for Public Service Company of New Hampshire. In that position, he had overall responsibility for the operation of Seabrook l Station from the corporate of fice. 43 In June 1982, Mr. Thomas was elected Vice President - Nuclear Production, with full time responsibility for the operation and operational support of Seabrook Station.
41 13A-3 l
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3-5-gjw 347 j JUDGE WOLFE: You may proceed Ms. Curran with your O 2 voir dire of the witnesses.
XX INDEX 3 VOIR DIRE EXAMINATION 4 BY MS. CURRAN:
5 Q Mr. Salvo, please tell me what your responsibilities 6 are with respect to Seabrook Environmental Qualification '
7 Program for electrical equipment in regard to safety?
8 A (Mr. Salvo) My responsibilities entail reviewing 9 the coordinating the overall program, and scheduling and 10 ensuring that all equipment for th ir safety were covered.
11 Q Did you personally review the equipment qualification 12 files for the Seabrook safety equipment?
r~)
k/ 13 A I did not do a detailed review of each specific 14 file, but just the overall review. ,
15 Q Did anyone in Connecticut Yankee perform a detailed 16 review of the equipment qualification files 7 17 A Not that I am aware of.
18 Q Mr. Salvo, do you have any training in electrical 19 engineering?
20 A No, I do not.
21 Q Do you have any experience in the field of electrical 22 engineering?
23 A No, I do not.
()
Medoral Reporters, Inc.
24 Q Mr. Thomas, will you please describe for me your 25 responsibility with respect to the environmental qualification
- 3-6-gjw 348 fs 1 program for Seabrook safety equipment?
k.)
2 A (Mr. Thomas) The equipment installed at Seabrook, 3 once it is qualified, comes under a maintenance program that 4 I am ultimately responsible for.
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5 Q And have you reviewed the maintanance program for
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6 each equipment qualification filed?
7 A I have personally not reviewed the program for 8 each file. There are people who are working for me that have 9 reviewed those programs.
10 Q Can you state who those people are, and what their 11 qualifications are?
12 A I am not prepared to do so right at this time. It U 13 is possible to get the information. It has been reviewed by 14 a number of people, and a number of different disciplines.
15 0 Are you aware whether those people are electrical 16 engineers?
17 A Some of those people are electrical engineers.
18 Q Do you have any training in electrical engineering?
19 A I have taken a number of courses in electrical 20 engineering. I am not, per se, an electrical engineer, but 21 I feel I have an adequate amount of training to recognize 1 22 certain aspects of electrical engineering, i
23 Q Certain aspects, but not all aspects?
() 24 Aeofeder:8 Reporters, Inc.
A Like I say, I am not an electrical engineer.
25 Q Mr. Woodward, who are you employed by, Mr. Woodward?
3-7-gjw 349 s 1 A (.M r. Woodward) I am employed by the Impell I \
\~J 2 Corporation.
3 Q Will you describe the Impell Corporation for me?
4 A The Impell Corporation is a wholly subsidiary of 5 Combustion Enginnering, which provides engineering services 6 to the nuclear utility industry.
7 Q And what has been your role with respect to the 8 environmental qualification program at Seabrook?
9 A I am responsible for reviewing and approving all 10 the work performed by the Impell Corporation, and the 11 preparation of EQ file packages.
12 I was also a member of the task team at Seabrook O 13 Station which helps coordinate all the information and 14 things that had to be done in order to put the program in 15 place at Seabrook.
End 3. 16 17 18 19 r
20 21 22 23 (2) 24 Ace Federal Reporters, Inc.
25
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3-350 Sim 4-1 1 Q Do you have any training or licensing.in 2
(s,s electrical engineering?
3 A (Witness Woodward)- I have.some formal 4
training in electrical engineering, but I am not a degreed 5h electrical engineer.
6 Have you personally reviewed any of the Q
7 equipment qualification files for Seabrook?
8 A 'As I have just so stated, yes, I have.
8 Have you reviewed all of those files?
Q 10 A
, Yes, because my signature' appears on the front 11 cover.
i 12 O Now would you say you have reviewed all those 13
- files in. detail, including the equipment qualification 14 test for the assertions that equipment was qualified?
15 A Yes.
16 (Pause in the hearing due to microphone j 17 difficulty and the inability of the audience to hear.)
18 MS. CURRAN:
h g
I guess I will just have to go
'j 19 on in as loud a voice as I can.
g 20 1 have looked at a number of.the ---
f J
.{ 21 FROM THE FLOOR: Can't hear.
22 (Pause.)
23 JUDGE WOLFE: Just a moment. We will tend 24 to that.
s 25 (Pause.)
, ._. -- . - , . . . 1- -- ___ - . . - , . - - , _ . . .
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351
-:cim 4-2 1 VOIR DIRE (Resumed)
I 2 MR..CURRAM:
V) All right, I think I am in 3 business here.
4 BY MS CURRAN:
5
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.Q Mr. Woodward, how long did it generally take 6 you to review a qualificatlon file?
7 A (Witness Woodward)' About anywhere from one-8 to three days.
9 0 I have a number of files here in which it '
10' appears from the cover that the file was prepared and 11 checked on one day and approved by.you on the next day, 12 Is that a typical process for preparing and approving
, ,S 13 one of these equipment qualification files?
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14 A It is a function of the size of the file.
15 0 In. what period of time did you review these 16 qualification files? Could you give me the dates?
i 3
g 17 A From approximately January of '85 up until
}c_ 18 approximately April or May of 1986.
j 19 Q When did you contract with New Hampshire a
20 Yankee begin?
A 21 A Approximately January 1985.
I 22 Q And are you still under contract to New 23 Hampshire Yankee?
24 A Yes.
( 25 Q What does that contract cover at this point?
352 Sim4-3' MR. DIGNAN: Your Honor, may I suggest we 2
.Q{'y are well beyond'the voir dire qualifications now and maybe
.it is time to-get the testimony in. If this cross-
' 4 examination is' designed to_ question credibility or something ,
5
- that properly comes after the testimony has been admitted.
6 , ggj CURRAN: I.would'just like to finish one 7
or two more questions on this.
8 JUDGE WOLFE: One or two more questions, all 8 right.
10
- BY MR. CURRAN
11 Mr.. Woodward, what is your fee for appearing Q
12 here today?
13 f ~g A (Witness Woodward) Approximately $95 an.
b 14 hour.
15 MS. CURRAN: Thank you.
.16 I have no further questions.
17 MR. DIGNAN: May I proceed with the witnesses, g
g 18 Your Honor?
, C d 19 JUDGE WOLFE: Go ahead.
a E
g 20 MR. DIGNAN: Gentlemen, I have caused to d
21 be placed before you a 24-page document entitled " Testimony i
I:
22 of J. M. Salvo, G. S. Thomas and N. K. Woodward, NECNP 23 Contention I.B.2," together with 10 exhibits attached 24 thereto, and I ask you fi you are the sponsors of that 1
O 25 document?
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353 Sim? 4-4 1 WITNESS SALVO:- We are.
f '-i 2 MR. DIGNAN: Are there any additions or
- t. )
~~ /
3 corrections that you wish to make to the testimony at 4 this time?.
5 WITNESS SALVO:- We have a one-page document 6 here which1 outlines four. changes that we would like to
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7 make. s t '
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3 8 MR. DIGNAN: Would you read those into the 9 record, please.
10 WITNESS SALVO: Okay. On page 2, line 10, ij add " normal and" at the end of the line.
12 On page 7, the line beginning "600-01-04" 13 add " Connection Kit" af ter Motor" .
j4 On page 7 also, the line beginning 15 "600-06-01" change Nanco" to "Namco."
16 On page 9, line 19, change " flooding. As" 37 to " flooding, as" and change "5, the" to "5. .The".
18 And there may be additional typographical I:
j 19 errors that we have not found.
J
-g MR. DIGNAN: I will ask'each of you gentlemen 20 a
d to answer this question separately.
-r i
Do you wish to adopt this document as corrected 22 as y ur testimony in this proceeding?
23 Mr. Woodward?
24
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J WITNESS WOODWARD: Yes.
25 a
354 Sim 4-5 1 MR. DIGNAN: Mr. Salvo?
4 /~'s 2 WITNESS SALVO:- Yes.
'y) 3 MR. DIGNAN: Mr. Thomas?
4 WITNESS THOMAS: Yes, I do.
5 MR. DIGNAN: Are.the statements, and again I 6 ask each of you to answer this question separately, are 7 the-statements set forth therein true and correct to the W
8 best of:your knowledge? ,
9 Mr. Woodward?
10 WITNESS WOODWARD: Yes.
11 MR. DIGNAN: Mr. Salvo?
12 WITNESS SALVO: Yes.
,,s 13 MR. DIGNAN: Mr. Thomas.-
] 14 WITNESS THOMAS: Yes, they are.
MR. DIGNAN: Your Honor, at this time I would 15 16 sk that a 24 page document entitled " Testimony of J. M.
s j 37 Salvo, G. S. Thomas and N. K. Woodward, NECNP Contention e
S. . 18 I.B.2," together with 10 exhibits referred to therein s
39 be admitted into evidence and incorporated at this point 3
into the record of this proceeding and bound in the 20 d transcript.
21 i I have furnished the necessary copies for this 22 23 Purpose to the reporter.
JUDGE WOLFE: Any objection?
24
(_/ MS. CURRAN: Judge Wolfe, I would object to 25 4
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355 Sim 4-61 admission of the testimony to the extent that either
' Er~m 2 Mr. Salvo or Mr. Woodward attest to the adequacy of the Q) 3 equipment qualification program for Seabrook and had*
4 the necessary technical' training and experience with the 5' files themselves to attest to that.
6 MR. DIGNAN: Your Honor,.I'would point out 7 .that Mr. Woodward testified distinctly.that he had reviewed 8 every file. _If the objection is on the basis that they 9 are not electrical. engineers, I know:of no basis on saying to that electrical engineering is a necessary background 11 for equipment qualification. It.might be to design the 12 equipment, but indeed as you will see, all three of these 13 -gentlemen are mechanical engineers, which is the usual O 14 discipline that performs this task.-
15 In addition, both Mr. Salvo and Mr. Woodward, 16 as to whom the objection has been made ---
a h 17 MS. CURRAN: I'm sorry. I meant to make it e
I 18 with respect to Mr. Thomas and Mr. Salvo and may have j 19 misspoken, a
20 MR. DIGNAN: Okay. Then there is no objection f
d 21 to it coming in via Mr. Woodward?
I 22 MS. CURRAN: Right.
23 MR. DIGNAN: All right. With respect to 24 Mr. Salvo and Mr. Thomas, under NRC practice and any g,,) 25 precedents it is custcmary to give panel testimony for
356 Sim 4-7 1 a reason, because there are technical aspects of this
w 2 testimony which are covered by move than one discipline.
(_)
3 The Board will recall that the issue before 4 the Board is the justification of the time duration 5 selected.
6 Mr. Salvo is perfectly qualified to defend this 7 and as the person who had responsibility for reviewing 8 it for New Hampshire Yankee.
9 I have already indicated with respect to 10 Mr. Thomas, who I think is fully qualified both by training jj and experience also to defend the testimony, that his 12 maj r purpose here is'in case a mangement position is needed
- 13 either as a result of cross-examination or questions 34 from the Board.
15 In any event, if the objection is only to 16 tw witnesses, the testimony should be admitted into evidence because Mr. Woodward admittedly is prepared to
} 37 e
5 18 defend it.
e j jg (Board conferring.)
a l: JUDGE WOLFE: Our rules permit testimonye 20
$ through a panel of witnesses, and the witnesses may consist 21 3
E g of individual with different backgrounds and who are f different disciplines.
23 We are guided by the Federal Rules of Evidence, (n) - 25 Rule 702, which related to testimony by experts, and I
4 dint 4-8 .
1 will read it. "If scientific, technical'or other specialized
~ (T 2 knowledge will assist the tryer of-fact to understand the N.v/
.3- evidence or to determine a fact in issue, a witness 4 qualified as an expert by knowledge, skill, experience, 5 training or education may testify thereto in the form of 6 an opinion or otherwise."
7 I believe that all witnesses under one category 8 or another, namely, knowledge, skill, experience, training 9 or education, I think are. competent and accordingly the 10 objection-is overruled and'the testimony of Messrs. Salvo, 11 Thomas and' Woodward',' plus the attached;or accompanying 12 10 exhibits are incorporated into the record as if read.
13 MR. DIGNAN:' And-admitted into evidence, Your r3 V 14 Honor?
15 JUDGE WOLFE: And admitted into evidence.
16 (The testimony of Messrs. Salvo, Thomas and a
k' 17 Woodward follows:
O j 19 i'
e 20
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24 25
O Dated: September 19, 1986 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION before the ATOMIC SAFETY AND LICENSING BOARD
)
In the Matter of )
)
PUBLIC SERVICE COMPANY OF .) Docket Nos. 50-443-OL-1 NEW HAMPSHIRE, et al. ) 50-444-OL-1
) On-site Emergency Planning (Seabrook Station, Units 1 and 2) ) and Safety Issues O !
TESTIMONY OF J.M. SALVO, G.S. THOMAS, AND N.K. WOODWARD NECNP CONTENTION I.B.2 As admitted by the Board, this contention reads as follows:
"The Applicant has not satisfied the requirements of GDC 4 that all equipment important to safety be environmentally qualified because it has not specified the time duration over which the equipment is qualified".
Environmental qualification is the process of generating, documenting, and maintaining evidence that equipment which is used to perform a necessary safety function will remain operable for the time needed to perform that timetion, under
(])
w 7'N U all normal and accident environmental service conditions postulated to occur during its installed life.
In nuclear power plants, many pieces of equipment can perform a number of safety and/or non-safety-related functions. These functions may be performed during normal operation and plant accidents, of which the latter could subject plant equipment to unusual environmental stresses.
The fundamental objective of environmental qualification is to assure that the specified electrical equipment purchased for the plant meets or exceeds the plant requirements under postulated accident environments.
A specific piece of equipment is said to be environmentally qualified when:
- 1. The equipment's safety and non-safety-related functions are known,
- 2. The postulated normal and accident environmental service conditions (e.g., temperature, pressure, humidity, radiation, chemical spray, and submergence) to which this equipment may be exposed during its installed life are known,
- 3. The duration of the necessary function and the conditions under which each function is accomplished are (I known, and O .
- 4. There is documented evidence of testing and/or engineering analysis to provide assurance that the equipment performs as it should, for the time required, in the plant environment to which it is exposed.
The constant state of readiness of environmentally qualified equipment to perform required safety functions is assured by proper design, manufacturing, installation, operation, surveillance testing, and maintenance.
The detailed requirements and guidance relating to the methods and procedures for demonstrating the capability of electrical equipment have.been set forth in 10 CFR 50.49,
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" Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants"; NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment", which supplements the Institute of Electrical and Electronics Engineers (IEEE)
Standard 323; and various NRC regulatory guides and industry standards, including Regulatory Guide 1.89.
Previous testimony given on behalf of the Applicants in 1983, regarding post-accident qualification duration, stated that the equipment was specified for a very conservative one year post-accident condition, which would encompass all required operating times. Further, it was stated that as a O
x
. ) result of the review of the equipment qualification data packages, now called E.Q. Files, some equipment may not be qualifiable for a one year duration. When this occurred, the shorter (less than one year) duration would be stated in the applicable E.Q. File. Engineering justifications, conservative margins, and reasons why equipment failure will not be detrimental to plant safety or mislead the operator, would also be incorporated in the E.Q. Files. Additional conservatism was incorporated into the program by the generic qualification of identical equipment irrespective of specific accident scenarios for each application. As a result of this methodology, Seabrook equipment was qualified to worst case environmental conditions (e.g., identical
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equipment may be located both inside and,outside of containment; however, qualification is based on the worst case harsh environmental conditions), to allow the J
flexibility of locating and interchanging like equipment j
among systems without jeopardizing equipment qualification.
i Seabrook plant equipment has been designed to function for a
- period of time consistent with the postulated accident scenarios and associated environments. It must again be emphasized that the one year post-accident duration was chosen as a very conservative upper bound to enable 4
environmental qualification on a generic basis.
() At the time of the NRC Environmental Qualification Program
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(v audit, the NRC and the applicant had a minor disagreement on the application of the Arrhenius equation. To resolve the issue, all Equipment Files were re-evaluated following the NRC's recommended methodology. This reanalysis resulted in the identification of several files not meeting the one year post-accident qualification duration. Subsequent discussions with the NRC staff resulted in a requirement to submit technical justification for any file which demonstrated a post-accident qualification duration of less than 100 days. The applicant agreed that this limit was reasonable and, based on engineering judgment, determined that this limit would envelop the required operating times
() of all files in question.
Although the NRC did not require submittal of written -
justification for files greater than 100 days, the Applicants indicated that they would make a written justification with respect to components which were not qualified for the one year post-accident duration. All relevant electrical equipment, located in harsh environments, have been reviewed and have met the one year qualification duration except for the eleven files shown in the fol' lowing Table and SSER-5. This Table is similar to the one that appears in SSER-5 with the exception that the radiation monitor, located in the containment enclosure, is j
longer required as a category 2 post-accident monitor,
() no
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see Exhibit 1. Furthermore, technical justifications are presented for each of the eleven files which did not satisfy the Seabrook post-accident qualification duration of one year. These justifications further document that the actual required post-accident operability duration is much less than the conservatively assumed 100 days' limit.
4 f
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\- Qualified post-Time required accident to perform EQ file operating safety Number of number Description time function items 248-36-01 Borg-Warner feedwater 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Approxi- 4 isolation valves mately 1 minute 113-03-01 Okonite 600-V power 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N/A cable
- 113-17-01 Anaconda 600-V control 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N/A cable
- 113-18-01 Anaconda 300-V instru- 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N/A mentation cable
- 113-20-01 ITT Suprenant 300-V 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N/A instrumentation cable
- 172-01-01 General Atomic Radi- 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Approxi- 2 1
O
\ ation Monitors and
, Detectors (inside mately 2 minutes containment) ,
174-00-01 Foxboro Transmitters 100 days 90 days 13 252-38-01 ASCO Temperature 160 days 30 days 4 Switches 600-01-04 Raychem 8 KV Motor 100 days 30 days 13 173-05-03 Maisoneilan E/P 204 days 100 days 4 Converter 600-06-01 h co EC 210 Series 318 days 30 days 16 Conduit Seals
- 0nly the cable that is subject to submergence is limited to 30 days qualification.
O
(~T x- Feedwater Isolation Values As set forth in Exhibits 2 and 3 to this testimony, the Feedwater Isolation Valves (E.Q. File 248-36-01) are required to close in a harsh environment created by a postulated pipe rupture in the main steam and feedwater pipe chase. ,
To establish the worst case accident scenario, a spectrum of break sizes were considered for feedwater and steam piping.
The valve closure time was based on the smallest break size, which causes the longest required operating duration, while the environmental parameters were based on the largest break size, which causes the most severe accident environment.
The conservative analysis concluded-that the valves would .
perform their safety function (close) in one minute.
Regulatory Guide 1.89, paragraph C.4 recommends that equipment, which performs its safety function within the first ten hours of the event, remain functional in the accident environment for a period of at least one hour in excess of the time determined by analysis. Adding this margin to the one minute, resulted in a required life of sixty-one minutes, which is less than the qualified Under this accident scenario,
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operating time of four hours.
the plant would be safely shut down using the Emergency Feedwater System, which does not require operation of the
() Feedwater Isolation Valves. Failure of the Feedwater
O Isolation Valve after it performs its safety function would not be detrimental to plant safety or mislead the operator, because its positioning is monitored by safety-related limit switches, which have been qualified for one year.
Furthermore, any equipment failure causing the Feedwater Isolation Valves to open would not jeopardize system operation since there are safety-related feedwater check valves located immediately upstream of the isolation valves in question. The four hour post-accident operability qualification has sufficient margin, per IEEE-323, to account for any uncertainties associated with the analysis.
The above justification attests that the Feedwater Isolation Valves are qualified in accordance with the guidance
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- provided in Regulatory Guide 1.89.
Cables The power, control, and instrument cables associated with Valves SI-V-17, SI-V-32, and CS-V-149 are located inside the reactor containment and ato subject to submergence due to l LOCA flooding /f As demonstra .ed in Exhibits 4 and 5 y the valves themselves will not be submerged and are qualified i
for LOCA environments for a one year duration.
I i CS-V-149 is the inboard letdown isolation valve and is required for letdown isolation and containment isolation.
SI-V-17 and SI-V-32 are accumulator tank isolation valves O
-9_
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O and are normally open, with motor power removed, during power operation (they also receive a safety injection signal to open).
To establish the worst case accident scenario, for determining the valve closure times, a spectrum of LOCA breaks was considered. .
A conservative analysis determined that valve CS-V-149 would perform its safety function (close) in less than one minute.
Adding the one hour margin recommendation from Regulatory Guide 1.89 to this value, resulted in a required operating time of sixty-one minutes which is much less than the The analysis also
{} qualified operating time of 30 days.
proved that valves SI-V-17 and SI-V-32 would perf6rm their safety function within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (remain open), which i's well within the 30 day qualified operating time. Failure of this equipment after it performs its safety function would not be detrimental to plant safety or mislead the operator, because:
i
- 1. Long term failure of the instrument cable would only j result in a ground alarm. Valve position would still be in.dicated.
- 2. Position indication would be known prior to cable failure.
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- 3. Long term failure of the power and control cables does not result in a change in valve position, thus system performance will not be impaired.
The 30-day post-accident operability qualification has sufficient margin, per IEEE-323, to account for any uncertainties associated with the analysis.
The.above justification attests that the power, control, and instrument cables are qualified in accordance with the guidance in Regulatory Guide 1.89.
Radiation Monitors O
The Radiation Monitors located inside the containment are required, only during refueling operation, to alarm on high radiation levels and to isolate the containment air-purge system. Exhibits 4 and 5.
In the event of a fuel handling accident inside the reactor containment, operating procedures require personnel to leave the area immediately and to isolate the containment air-purge system. These monitors are a backup to operator action, A review of the required operating time indicates l
that the radiation monitors will perform their safety t
function (alarm and isolate) within two minutes after a fuel handling accident. Adding the one hour margin 11 -
/'T V recommendation from Regulatory Guide 1.89 to this value, results in a required operating time of sixty-two minutes, which is less than the qualified post-accident operating time of seven hours.
Failure of this equipment after it performs its safety function wil1 not be detrimental to plant safety or mislead the operator because its failure will not impact other safety-related equipment. Also, long-term radiation levels are measured with the safety-related containment wide-range monitors, which have been qualified for one year. The seven hour post-accident operability qualification has sufficient margin, per IEEE-323, to account for any uncertainties
\- associated with the analysis. The foregoing justification attests that the radiation monitors are qualified in accordance with the guidance in Regulatory Guide 1.89.
Transmitters The Foxboro Transmitters are located in the Primary Auxiliary Building, Mechanical Penetration Area and Equipment Vaults. These transmitters are used to provide flow or pressure indication in several systems during various accident scenarios. As a result of a recent detailed review of the operability requirements (i.e.,
subsequent to the issuance of SSER-5), it was determined that the transmitters were not required to function during O
12 -
j
O the high energy line break, which caused the worst case harsh environmental parameters.
Since equipment is generically being qualified for the most severe conditions to which it is being exposed, the worst case environment was used to establish the 100 days qualified post-accident operating time which is specified in the previous table and SSER-5. Notwithstanding this, it should be noted that several of these transmitters were qualifiable for one year, when examined against their zone specific environmental parameters.
As a consequence of the recent review, the post-accident qualification time reanalysis based on the applicable (J~)
accident scenarios indicates that all of this equipment is qualified for one year in the harshest of the environments it will see.
Temperature Switches The ASCO Temperature Switches are located in the Primary Auxilliary Building and the Emergency Feedwater Pump House.
These switches are required to control the redundant ventilation system fans in both of these buildings.
It should be noted that the temperature switches in the Emergency Feedwater Pump House are qualified for one year,
(
13 -
O when examined against their zone specific environmental parameters.
Since equipment is being qualified for the most severe conditions to which it is being exposed, the worst case environment was used to establish the 160 days qualified post-accident operating time.
A conservative analysis determined that this equipment would be required to perform its safety function for 30 days, which is well within the 160 days qualified post-accident operating time. Failure of this equipment after it performs its safety function would not be detrimental to plant safety or mislead the operator because there is an independent high
{} temperature alarm located in the Primary Auxiliary Building which would indicate improper fan operation. Manual operation of these fans would then be implemented.
Furthermore, 30 days after an accident, access to this equipment is possible to perform repairs, recalibrations, adjustments, or preventive maintenance.
Motor Connection Kits The Raychem 8 KV Motor Connection Kits are located in the Primary Auxiliary Building, Equipment Vaults and Emergency Feedwater Pump House. These motor connection kits are used j for various electrical splicing applications between cables
() and motor leads.
l
. . - , , , - , - -... , ,, , - - - - - - - - - - - - - - . , -m , -- ------ g-,ne---~--------n- -----~,-- --. + --,- -
X U .
This file was first. qualified for one year, post-accident duration, based on Seabrook's original application of the Arrhenius equation. As a result of the NRC audit, this file was reanalyzed, following the NRC's methodology for Arrhenius equation application, and a revised post-accident duration of 100 days was determined.
Since equipment is generically being qualified for the most severe conditions to which it is being exposed, the worst case environment has been used to establish the 100 days qualified post-accident operating time which is specified in the previous table and SSER-5. Notwithstanding this, it should be noted that several of these motor connection kits were qualifiable for one year, when examined against their zone specific environmental parameters.
Although the 100 days' value was acceptable, Seabrook began investigating ways of increasing the post-accident duration.
As a result of a recent detailed review of the actual operating ampacity of the systems in question (i.e.,
subsequent to the issuance of SSER-5), it was determined that the temperature value used for qualifying the motor connection kits was overly conservative and did not reflect the normal operating or accident environmental parameters.
i As a consequence of the recent review, the documentation of
U m
which will be added to the appropriate EQ file, the post-accident qualification time reanalysis based on the actual operating ampacity of the system, for both normal and' accident conditions, indicates that this equipment is now qualified for one year.
E/P Converters The Maisoneilan E/P Converters are located in the Primary Auxiliary Building and are required to position valves that control the Primary Component Cooling Water (PCCW)
Temperature during the initial phase of any accident.
A conservative analysis determined that this equipment would 4 O . perform its safety function in less than ten hours. Adding the one hour margin recommendation from Regulatory Guide 1.89 to this value, resulted in a required operating time of no more than eleven hours. The 204 day qualified accident operating time is well in excess of the required operating time. Failure of this equipment after it performs its safety function would not be detrimental to plant safety because the temperature control valves could be placed in the full cooling mode of operation using safety-related contro.ls from the control room or manually controlled locally. This equipment does not supply any indications, therefore its failure would not mislead the operator.
Furthermore, 30 days after an accident, access to this 16 -
1 O equipment is possible to perform repairs, recalibrations, l adjustments, or preventive maintenance.
Conduit Seals The Namco EC 210 Series Conduit Seals in question are located in the Main Steam and Feedwater Pipe Chase. This device provides a means of quick disconnect of an electrical cable, while maintaining an environmental seal. The conduit seals are attached to the ASCO Solenoids which isolate air to the Main Steam Isclation Valve air operators. A conservative analysis determined that this equipment would perform its safety function within one minute after an Adding the one hour margin recommendation from
{} accident.
Regulatory Guide 1.89 to this value, resulted in a required operating time of 61 minutes. The 318 days qualified post-accident operating time is well in excess of the required operating time. Furthermore, 4 days after an accident, access to this equipment is possible to perform repairs, recalibrations, adjustments, or preventive maintenance. The accessibility of this equipment permits the implementation of manual isolation functions insuring that the Main Steam Isolation Valves remain in their safety i
position. Therefore, a failure of this equipment after it performs its safety function would not be detrimental to plant safety or mislead the operator.
17 -
1
, - - - - -r.----n.n , , , , , , - , - . , - - , , , _ ---.
. . , , , . - - - , , , ,--.--r-------------. , . , vv - , - - - .. - - -
r'T V
In an opposition to Applicants' request for a low power license, dated July 2, 1986, NECNP raised 'several concerns regarding the adequacy of the environmental qualification program at Seabrook. The following addresses each of the ,
concerns: .
NECNP Item A.1 at P. 18 NECNP alleges that the Applicants' documentation (i.'e., E.Q.
Worksheets) are contradictory and confusing with respect to qualification times for submergence.
The following is offered in clarification:
O In some situations, components are qualified only for those environments under which they are required to be operable.
For the example given in A.1, the N/A designation for submergence is correct because instrument racks included in the scope of this qualification file perform no safety function for the postulated accident which causes the submergence. These instrument racks are required for other postulated accident scenarios and were qualified for the associated environmental conditions. This can be traced on Exhibit 6, by Note 2 in the submergence qualification block, which references back to the E.Q. File Assessment Checklist
- 3, Note 5. It should also be noted that all electrical
() components on instrument racks which are required to be 18 -
operable with a submergence environment are located above the associated flood 12 vel.
NECNP Item A.2 at P.18 NECNP alleges that in spite of postulated environments that specify an operating time of at least one year, some pieces of equipment are qualified for only 30 days' submergence.
r SSER-5, Table 3.1 at p.3-34 identifies four E.Q. File Numbers for which the cable submergence is limited to 30 days qualification. NECNP's concern was specifically addressed in Exhibit 4, which identified the files as not meeting the one year post-accident operability duration.
Engineering justification for these exceptions has been included as part of this testimony as well as being formally submitted to the NRC via Exhibit 4. This justification is in accordance with the guidance provided in Regulatory Guide 1.89.
f
! NECNP Item A.3 at P. 18 NECNP cites two E.Q. Files as examples showing that l
Applicants' information is incomplete.
It appears that NECNP based its statements on Revision 1 worksheets provided in Exhibit 7. It should be noted that
' worksheets have since been revised and submitted to the NRC,
() and to the interested parties. In the case of the two files 19 -
i-- . - . , _ . - - - . _ _ _ _.___ _ _ ._ . _ , _ _ . , _ , _ . _ _ ___ _ _ __ _
O cited, the worksheets were revised and resubmitted in Exhibit 8 which clarified Note 3 on the worksheet. The note now states, "This is generic equipment which is not qualified for submergence, and is not submerged in the plant in any application where operability is required".
NECNP Item A (generally) at P. 18 and P. 19 An underlying concern apparently also raised by NECNP, has to do with the content of the Environmental Qualification Werksheets.
The Environmental Qualification Worksheet is a synopsis of the qualification status of all the lE equipment associated O with a particular purchase order and within the scope of the E.Q. File. It must be recognized that it is impossible to provide all the assumptions and engineering analysis which goes into the qualification of equipment. In this regard, it should be noted that a typical E.Q. File consists of 100-200 pages of documentation to verify component qualification. Therefore, a worksheet may correctly refer i
to other documents within a given E.Q. File.
NECNP Item B at P. 19 & P. 20 NECNP alleges that the NRC's audit of Applicants' equipment qualification on February 24-27, 1986 demonstrated that the O
i
t'3 NJ Applicants are not keeping reasonably accurate equipment qualification files.
The NRC audit involved the review of twelve E.Q. File packages including associated documents. Given that a typical E.Q. File consists of 100-200 pages of documentation to verify component qualifications, the reviewers inspected at least 1200-2400 pages of documentation. In this regard we believe that the four clarification related comments identified by the Staff, to further enhance qualification documentation, do not demonstrate that the Applicants are not keeping reasonably accurate files.
In regard to the Applicants' representations regarding (G~T qualification times, none of the comments made by the Staff, that are specific to individual E.Q. Files, indicate a concern with the qualification times.
The comment regarding submergence qualification (E.Q. File No. 113-06-01) does not raise a substantive concern regarding qualification times since it involves adding a statement to indicate when submergence qualification has been properly determined as not being required.
The Applicants' responses to the NRC audit observations, are set out in Exhibits 2 and 7.
O NECNP Item C at P. 20 NECNP seeks access to Applicants' analysis supporting conformance with Regulatory Guide 1.75 as referenced in SSER Supp. No. 5. The reference in SSER-5 Section 3.11.3.1 at ,
3-17 to submittal of analysis supporting conformance to Regulatory Guide 1.75 pertains to supplemental information for certain specific electrical separation configurations.
Applicants have submitted the supplemental information to the NRC and to the interested parties as set forth on Exhibits 9 and 10 to this testimony.
NECNP Item D at P. 20
' NECNP alleges there is a dispute between the Staff and the Applicants regarding qualification of post-accident monitoring equipment.
In discussions with the NRC Staff concerning Regulatory Guide 1.97 deviations, the Staff indicated that devictions regarding accumulator pressure or level, and containment sump water temperature were unacceptable. Applicants, therefore, have committed to install and have operational, prior to the restart after the first refueling, environmentally qualified accident monitoring equipment for and safety injection accumulator tank pressure or level, containment sump water temperature. The acceptability of
() this commitment is reflected in SSER-5, Section 3.11.3.1 at
r 3-19. The Staff evaluation in SSER-5 concluded that sufficient justification was provided for not having environmentally qualified parameters for primary coolant radiation level and narrow range containment sump water level.
In conclusion, the relevant electrical equipment has been ,
designed, procured, installed, tested, and maintained to meet the requirements embodied in 10 CFR $ 50.49, NUREG-0588, IEEE-323-1974, and various regulatory guides and industry standards including Regulatory Guide 1.89.
The Environmental Qualification Program at Seabrook has identified and documented the qualification duration of all relevant electrical equipment located in a harsh environment. This testimony substantiates compliance with all applicable environmental guidelines.
i l
\
\~ EXHIBITS ;
Exhibit 1 PSNH Letter (SBN-1161), dated July 18, 1986,
' " Accident Monitoring Instrumentation Review and Compliance with Regulatory Guide 1.97," from Applicants to V. S. Noonan.
Exhibit 2 PSNH Letter (SBN-988), dated April 3, 1986,
" Environmental Qualification; Post-Accident Operability Time," from Applicants to V.S.
Noonan.
Exhibit 3 PSNH Letter (SBN-1006), dated April 16, 1986, "NRC Request for Additional Information," from Applicants to V.S. Noonan.
Exhibit 4 PSNH Letter (SBN-1024), dated April 30, 1986,
" Environmental Qualification: Post-Accident Operability Time," from Applicants to V.S.
Noonan.
Exhibit 5 PSNH Letter (SBN-1030), dated May 6, 1986, "NRC Request for Additional Information," from Applicants to V.S. Noonan.
O Exhibit 6 Worksheet from E.Q. File No. 171-01-01, Mercury Company Instrumentation Racks.
Exhibit 7 PSNH Letter (SBN-998), dated April 10, 1986,
" Response to Environmental Qualification Audit Observation," from Applicants to V.S. Noonan.
Exhibit 8 PSNH Letter (SBN-1031), dated May 7, 1986,
" Environmental Qualification; Evaluation Worksheets," from Applicants to V. S. Noonan.
Exhibit 9 PSNH Letter (SBN-979), dated March 31, 1986,
'! Electric Separation Criteria," from Applicants to V. S. Noonan.
l f Exhibit 10 PSNH Letter (SBN-1107), dated June 13, 1986,
" Electrical Separation Criteria: Additional Information," from Applicants to V.S. Noonan.
O
l l
I SEABROOK STATION
/ ragineering Office p ; *a'l s
- 0 l July 18, 1986 l
1 Pubuc Service of New Hampshire SBN- 1161 NEW RAMPSHIRE YANKEE DIVISION United States Nuclear Regulatory Commission .
Washington, DC 20555 Attention: Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
References:
(a) Construction Permits CPPR-135 and CPFR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-1098), dated June 6,1986, " Accident Monitoring Instrumentation Review and Compliance with Regulatory Guide 1.97", J. Devincentis to V. S. Noonan
Subject:
Accident Monitoring Instrumentation Review and Complianet
.CJ
Dear Sir:
I, In discussions with the NRC Staff it was agreed that the Main Plant Vent Stack Noble Gas Radiation Monitor (FS AR Table 7.5-1, Item E7) provides the pri=ary indication for detection of significant releases or breach of the containment. The Containment Enclosure Noble Gas Radiation Monitor (FSAR Table 7.5-1, Item C-13) is backup indication that assists the operators in identifying the location of a release that has been identified by the Main Plant Vent Stack Monitor. Since backup Type C variables are considered Design Category 3 ve are revising the F.7AR to reflect this change.
Attached are marked-up copies of FSAR Table 7.5-1, sheet 12 and page 7 A-9 that reflects the change of the Containment Enclosure Noble Gas Radiation Monitor from Design Category 2 to 3. These changes will be included in a future amendment to Seabrook's FS AR.
We trust that the enclosed is acceptable and request that this be reflected in the next supplement to Seabrook's SER.
Very truly yours, I
fW /
John DeVincentis Director of Engineering k Enclosure cc: Atomic Saf ety and 1.icensing Board Service 1.ist
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Rm LL97 ft 1T l
l i
~
Peter J. Mathews, Mayor Diane Curran, Esquire City Hall l
Harmon & Weiss Newburyport, MA 01950 2001 S. Street, N.W. >
- Suite 430 Judith H. Mirner Washington, D.C. 20009 Silvergate , Gartner, Baker, ;
f '
Fine, Good & Mizner Sherwin E. Turk, Esq. 88 Broad Street Office of the Executive Legal Director Boston, MA 02110 U.S. Nuclear Regulatory Commission Tenth Floor Calvin A. Canney Washington, DC 20555 City Manager City Hall Robert A. Backus, Esquira 126 Daniel Street 116 Lowell Street Portsmouth, NH 03801 P.O. Box 516 Manchester, NH 03105 Stephen E. Merrill, Esquire Attorney General Philip Ahrens, Esquire George Dana Bisbee, Esquire Assistant Attorney General Assistant Attorney General Department of The Attorney General Office of the Attorney General Statehouse Station #6 25 Capitol Street Augusta, ME 04333 Concord, NH 03301-6397 Mrs. Sandra Cavutis Mr. J. P. Nadeau Chairman, Board of Selectmen Selectmen's Office KFD 1 - Box 1154 10 central Road Kannsington, NH 03827 Rye, NH 03870
() Carol S. Sneider, Esquire Assistant Attorney General Mr. Angie Machiros Chairman of the Board of Selectnen Department of the Attorney General Town of Newbury One Ashburton Place, 19th Floor Newbury, MA 01950 Boston, MA 02108 Senator Gordon J. Humphrey Mr. W1111sa S. Lord Board of Selectmen U.S. Senate Town Hall - Friend Street Washington, DC 20510 Asesbury, MA 01913
!. (ATIN: Tom Burack) i Senator Gordon J. Humphrey Richard A. Hampe Esq. 1 Pillsbury Street l Hampe and McNicholas Concord, NH 03301 35 Pleasant Street (AITN: Herb Boynton)
Concord, NH 03301 H. Joseph Flynn, Esquire Thomas F. Powers, III Office of General Counsel Town Manager Federal Emergency Management Agency Town of Exeter 500 C Street, SW 10 Front Street Washington, DC 20472 Exeter, NH 03833 Paul McEachern, Esquire Brentwood Board of Selectmen Matthew T. Brock , Caquire RFD Dalton Knad .
Shaines & McEachern Brentwood, NH 03833 25 Maplewood Avenue Cary W. Holmes, Esq. P.O. Box 360 Portsmouth, NH 03801 O Holmes & Ells 47 Winnacunnet Road Robert Carrigg
( Hampton, NH 03842 Town Office Mr. Ed Thomas Atlantic Avenue North Hampton, NH 03862 FEMA Region 1 442 John W. McCormack PO & Courthouse
_ Boston, MA 02109- .- . - - . . . _ _ _ _ - _
~~~*~*'""ww~w ",m.e -
-,m, , _ _
()
- Administrative Judge Helen Hoyt, Chairperson f- Atomic Safety and Licensing Board Penel 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 Vashington, D.C. 20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.~20555 Dr. Jerry Harbour Atoalc Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555
(
C)
S. ..
TABl.E 7.5-1 (Sheet 12 of 37) se DESIGN ENWitONMINTAL SEl$MIC I TIM TRkNDINC R EMARES/NOTtS CATECOBY QUALIFICATION QUAL. QA NtmafE VAm f A tlE Yes Yes Yes N/A Cil Costelament Pressure !
C12 Costelament Effluent See E7 Bed teactivity - Noble Ceees free Identtfled Bolesse Palate N/A e see Devletion uo. s la Appendia FA.
Cl3 tifluent Bedteactivity /T 3* 7p/ N/A N/A wee We' ele Cases (laalde buildtage or steer where penettettone or hatches are located)
TYPE D WAAlABLES. SYSTEM GPERATION
'"o t
O NiA Yes uiA L
2 vee
- ei .n. s,ete. riou N/A
- See Devlettoa No. 22 to Appendtn FA.
Yes N/A Yes e,a Stet Nest Eschenger 2 D2 Outlet Temperetute .
5AFETT INJfCTfDW e See Devletten No. 10 la Appendia FA.
D3 Accumulator Tank Level" e see paygetton No. Il la Appendia FA.
D4 Accumulator Tonk Pressure
- f4 2:
33 o cm.
4 i.I et a Q
- .-. e s
- O sus tn us (b
- O e
A1 No br 9 I
UNIT NO. 1 SEABROOK STATION f ,
REGULATORY CUIDE 1.97, REVISICW 3 EEVIEW ,
Deviation No. 9 Data Table Ites No.
variable C13 Effluent Radioactivity - Wohle Cases (Inside buildings or areas where penetrations j
or hatches are located.)
4 Deviation Fros Reeulatory Guide 1.97 Guidance I I
The installed range, 10 to 10 CPM (corresponding to 6 x 10 to 10 uci/cc), does not envelope the recosenended range (10' to 10 uci/ce). This variable is classified as Design Category 3 instead of Design Category 2 as recommended in Regulatory Guide 1.97.
Justification
\
The containment structure and all penetration / hatch areas are surrounded by the containment enclosure building. The exhaust from the containment enclosure building is monitored for scoss activity. The containment enclosure {
i building exhaust is routed to the main plant vent stack, where it is monitored '
! -7 5 (10 - 10 uCi/ce) prior to discharge.
The Main Plant Vent Stack Monitor (Table 7.5-1, Item E7) monitors all releases to the atmosphere that may result from design basis accident Stack events.
The Containment Enclosure Monitor is a backup to the Main Plant Vent ;
Monitor to assist the operators in identifying the source of the release.
Both the Main Plant Vent Stack Monitor and the Containment Enclosure Monitor provide indication of containment breach which is the purpose identified in Regulatory Guide 1.97. Backup Type C variables are considered to be Design ,
Category 3.
i O !
7A-9 i
F. Bean J. DeVincenti3 E. Brown T. Feigenbaun U A. Cerne G. Gram I ' I R. Cummings R. DeLoach W. Hall R. Harrison W. Derrickson D. Hunter Publ6c SerWce of New Hampshire April 3 19R6 gg n SBN-988 G. Mcdonald New Hampshire Yankee Division M. McKenna T.F. B7.1.2 D. Moody NRC Subject File Projects - WJD United States Nuclear Regulatory Commission Projects - Chrono Washington, DC 20555 Ropes & Gray (3)
A. S epar Attention: Mr. Vincent S. Noonan, Project Director ,
PWR Project Directorate No. 5 g, G. Thomas Ref e rences : (a) Construction Permits CPPR-135 and CPPR-136 Docket Nos. 50-443 and 50-444 UE&C & SB-20681)
P. Stroup (b) Environmental Qualification Site Audit, ASLB February 24-27, 1986 Subj e ct : Environmental Qualification; Post Accident Operability Time
Dear Sir:
As a result of the recent NRC EQ site audit, Reference (b), the Staf f indicated they were not in agreement with the Seabrook methodology in applying the Arrhenius equation to calculate the post-accident operability time. In subsequent discussions, we proposed a more conservative approach to the Staf f and provided examples of how this approach would be implemented.
In a telecon on March 31, 1986, we were informed by the Staf f that the exa=-
pies were acceptable.
We have now completed recalculating the post-accident operability times for all the EQ equipment files currently issued (109 of a total 115 files). We have followed the same approach used in the examples provided to the Staff and in all cases have taken no credit for any portion of the tect curve which enveloped the transient portion of the postulated accident pro-file. The results of this reanalysis indicate that, with the exception of the following, all files currently issued meet the 40-year normal operating life plus one-year post-accident life.
Post-Accident So-Ser of EQ File Iterc Number Description Operating Ti=e 174-00 Foxboro Transmitters 100 days 13 ite s 252-3A-01 ASCO Temperature Switches 30 days 4 ite-<
Raychem HKV Motor Connector Kits 190 days 13 item 6%-01-01 Maisoneilan E/P Converter 109 days 4 ite-<
173-05-03 a hours a f t .m 2 8-36-01 Borg-Warner Teedwater Isolation Valves EXW8Z r A . .
' ' ' ' - - w- - - - - ,____,.r ., . _ _ _ .
United States Nuclear Regulatory Consission April 3, 1986 Attention: Mr. Vincent S. Noonan, Project Director Page 2 O In all the above cases, the post-accident operating time has addi-tional margin to meet the performance mergin requirements of IEEE 323, 1974 From our discussions with the Staf f during the site audit, engineer-ing justifications for post-accident operating times of 100 days or longer is not required. Therefore, the following is our engineering justification con-cerning the acceptability of the post-accident operating time for EQ File No.
252-38-01 (ASCO Temperature Switches) and EQ File No. 248-36-01 (Borg-Warner Feedwater Isolation Valves).
The Feedwater Isolation Valves (File 248-36-4 1) are required to close in a harsh environment created by a postulated nonsechanistic pipe rupture in the main steam and feedwater pipe chase. The feedwater and steam piping in this area is designed under the concepts of "Superpipe". Our en-gineering analysis conservatively has determined valve closure would occur in less than one minute. The plant would be safely shut down using the Auxiliary Feedwater Systes, which does not require operation of the Feedwater Isolation Valves. Control Room indication of these valves :an be relied upon for a longer duration than four hours be cause the Namco 180 Limit Switches are qualified for one year post-accident operation. We have concluded that the four-hour post-accident operability qualification has sufficient margin to ensure the required safety function has been performed.
l The ASCO Temperature Switches (File 252-38-01) are located in the Primary Auxiliary Building in the vicinity of the Primary Component Cooling O
Water Pumps. In the event of HELB in this area, the switches automatically start safety grade fans (PAH-FN-42 A and -B) to provide HVAC services for the PCCW pumps.
The fans have a continuous run feature that can be used to operate the fans if the tempe ra ture switches fail. Also, separate high temperature alare and nonsafety grade HVAC fans normally provide cooling ventilation for the PCCW pumps. In conclusion, the 30-day post-accident
, operability qualification has sufficient ma rgin for the required immediate j
safe ty f unction of providing safety grade HVAC cooling.
The remaining six EQ file packages are in final review. We will use the same methodology for determining post-accident operability times for j these packages as previously discusssed. We will notify you when our review is complete and will identify those items, if any, that do not meet the one-year post-accident operability.
The information provided in this letter is intended to satisfy the Staff on the Seabrook methodology used calculating post-accident ope r abili ty time. Accordingly, we request that the acceptability of Seabrook's methodol-ogy for calculating post-accident operability time be reflected in the next supplement to Seabrook's SER.
I i Very truly yours, f . *-
, Y .' d ohn DeVincentis, Director Engineering and Licensine Enclosures ec: Atomic Safety and Licensing Board Service List
Peter J. Mathews, Mayor j Diane Curran City Hall Maemon & Weiss 20001 S. Street, W.W. Newburyport, MA 01950 Suite 430 20009 Calvin A. Canney Washington, D.C.
City Manager Sherwin E. Turk, Esq. City Hall Office of the Executive Legal Director 126 Daniel Street U.S. Nuclear Regulatory Commission Portsmouth, NH 03801 Washington, DC 20555 Stephen E. Merrill Robert A. Backus, Esquire Attorney General 116 Lowell Street Dana Bisbee, Esquire P.O. Box 516 Assistant Attorney General Manchester, WM 03105 office of the Attorney General 25 Capitol Street Philip Ahrens Esquire Concord, NH 03301-6397 Assistant Attorney General Department of The Attorney General Mr. J. P. Nadeau Statehouse Station #6 Selectmen's Office Augusta, NE 04333 10 Centest Road Rye, WM 03870 Mrs. Sandra Gavutis Designated Representative of Mr. Angie Machicos the Town of Kensington Chairman of the Board of Selectmen Town of Newbury RFD 1 East Kingston, NH 03827 Newbury, MA 01950 Mr. William S. Lord O Jo Ann Shotwell, Esquire Assistant Attorney General Board of Selectmen Town Mall - Friend Street Environmental Protection Bureau Department of the Attorney General Amesbury, MA 01913 One Ashburton Place,19th Floor Boston, MA 02108 Senator Gordon J. Humphrey 1 Pillsbury Street Senator Gordon J. Humphrey Concord, NH 03301 U.S. Senate (ATTN: Herb Boynton)
Washington, DC 20510 H. Joseph Flynn (ATTN: Tom Durack)
Office of General Counsel Diana P. Randall Federal toergency Management Agency 500 C Street, SW 70 Collins Street Seabrook, NM 03874 Washington, DC 20472 Richard A. Maspe, Esq. Matthew T. Brock, Esq.
Hampe and McNicholas Shaines, Madrigan & McEachern 35 Pleasant Street 25 Maplewood Avenue Concord, NH 03301 P.O. Box 360 Portsmouth, NH 03801 Donald E. Chick Town Manager Gary W. Holmes, Esq.
Town of Exeter Holmes & Ells 10 Front Street 47 Winnacunnet Road Exeter, NH 03833 Hampton, NH 03841 O Brentwood Board of Selectmen Ed Thomas FEMA Region I RFD Dalton Road Brentwood. NH 03833 John W. McCormack PO & Courthouse Boston, MA 02109
- . - . . . . - - . . - - . _ - - - . - - . - _ ~ . - - . - . - . . - - _ -
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- i s I WA I l i WA I WA I I i ll i WA I I l il Cte>mical Note i l l i l sprey (peil l I I i I I _i I
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ll 4U Tear normal i I i Test 1 None Demon: WA 3 I p. 4 7 3 i 1
ll Radletion Oose il 1a 10 i i 1.8 m 10 1 I i I p. 6 I I I ll (Rossi i l I l
B I I I ll I fear Accident I 4 l p. 4 l I l 4 lai t ing invironment : I I I 1 loc at ion: t iec tric al ll Radiat ion Oose 1I 3.4 m 10 l 8 3
3 i Ene i il IRads) I I 4 I Test I l Penetrellon Area ll I
l I i 108.5/40 1 l Appendix 'C" l l l
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- f / Vear si I i I ~l, l Penets at ion Area la 1 l l 8 .i I
i sti-3hl l I I ll I I a l
e 1 I WA l None is i
1 WA 1 WA I I l- l 3 i I I I t owest it watton: WA ll i WA I I I sub=urgence I I I I I flomstevel: WA 11 l l * ***
l 1.towe i tood Lews t : WA ll l l
- ll l 8. The only postulated harsh environmental IkFuisiiinTaiion i<e eonnces: tamperature es.:
Ser vice Envirosament Charf , Rev. 37, 1/21/BS.
parameters for zone 11-30 are 742. 02-6259-320, tAs. lear Component radiatlon.
- s. Ol &L Dr IP-1/006-ul, aelng No. 9763-f -300219,*out hwest Hesearch Inst Coolantitute Datumunt hasp f use 1.
t/uaillication lost Plan for the quelllication of a Hoat tor L ob l oo t , dated 8/84/dl . te 01-6249-320, Nuc lear
- 1. I P- 5 tht14-O i , Sout hwest Researc h Inst itute 0
or vl( e I nv f r s enmant Char t , how.f or U?.D I u ,o Gloc ks the only harsh environnuant I.ar amet.n .
18950-64N,
- 3. Ul &L Ds awing -01, No.At ton Quali f lo alIsan Ie st Rg.or i No.
- 2. Ii*- 3 4 tu I,. ut at Seabr o1/9-I-01, A St at ion. datews $2/7/84 f6 sio 2 of Awowna nl ( Iwm kil J .
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1, *. einbe IQ illo No. "l le = ali n9 *> t u.ly H.el e l a, .n l 88 .688'.l. f '
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4
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Checked By: gj , - V, -
%sataroca St at ion LOUllM NI QuAliFICAIlON filf NO. 129-08-01 D(akst: S0-443 -wi f, 'b I
.f,nc, l l g I
I I Hererence i 8
l Equipausnt De xription il Parameter I 8 I
'g I I g i I y,,, g %
1I Operating i l I year i p. 5 -3 l I i Purchase Or der No. : Ties I i Year l P. 1 O#* I I I 1 9763-006-129-01 il gg g g g I __II l l l ,
i I qui pensnt ID No( s) . : ll I g i l l l i 114 -M+ *>84 18 i l WA None ll Peak i N/A N/A N/A I i WA I ll T reture g g I ) -g l l ,
ll I g ,
I i I i l i il l l l WA l None I i il Peak i W A- 1 WA l WA g ,
i l WA I l l i ll Pressure l l 1 Equipmunt Iype: IPstgl 1 1
I I I ll I i Iceminal tilocks il i a i
l l l i I l I
II i l N/A I N/A l None i i Relative i N/A l N/A l i i 1 M:nuf ac turw :
il l N/A l I ll Humidity I i 1 I l t b stinghouse il til l t 1 1
I i l ll l i I i
i Hosei Number: 5 s
i i WA l Hone :
I luAt-90 ll i i WA l WA 1 Chemical I WA I I I l il Spray lpHI I WA l i ll 1 l l 1 ~~
I l l I I ll l I 1 l I I l l l Accur acy : Spec; WA ll I l 2 i None l Demon: N/A ll 40 Year Normal i l.0 m 10 3 l p. 4 l 8 I p. 5-3 3 Test ll Radiation Dose I I i 1.87 x 10 I l l l I ll (Rads) i i l l l l Tear accident i l l l 15 3.4 m fo i j p. 4 I l I
ll Radiation Dose 1i l l 8 I
I t imi t ing i nvironment : IRads) I 3
l Test and i None 11 I I l il i
j i l 3 l Analysis l l tccatloa: Electrl(al 11 Aging i l p. 4 1 114/41 1 I I I l f%nott at ton Area if 1381 ll l*F/ Year si l 8$/40 i I I i "
l H d lone: Electrical ll l l l 1 I 3 3
l Penetr at lon Area l[138) l} l I I I I I WA l None l I I WA l
' il l l WA 1 I l 4 I I O i t owust i levat ion: N/A I ll WA 3 SubsmorgerKe I I I WA ll I I l floud level: ll l l l l Above fItm>d Lowel: WA ll l
l
- 8. The equipment is located in stuitsects1.as is Ikat umsenia e ton lielos esent os_: 11, datud 7/22/8*>.
- Penetration Ar ea where (a.flatlans Qu ail t lcallon the only harsh environmental pas anuit..a .
I. Ut 1C Os aving No. 9763-F -300289, *,er v ite i nvironm. int Chat I, liev.16758 -fi/N, & nwironaumtal and Selsele
- 1. 8 8'- 1/ Jt.6-06, Ac ton Iest fiepos t No./, 2/6/83.
of (lass it lueminal Hi<4ks, Row. 1 of Awessa..nl ti n kil .t . ... .. i s 8. .. ,
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ll ll 1 8
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WA l leone i 1
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- i i Note 2 - Note 2 l g il l l iI Equipment Tynet ll Pressure : --
l I l I i i
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! Meruf actur r: aoston b Reletswe - I Note 2 1 1
I i 1 il m aldity 1 l 1 1 l g l lazulated wire I l l l i Il (H l l s
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ll e i
I l I I WA l leone 1 lModeiNumber Bostred R #3 i
i I l WA i WA i l cheelc et I WA I i ll Spray IpHI I WA I l {
11 l 1 I l l ll l I I I g {
I I I I
- 4 i Aa:uracy:spect WA 11 ll 40 year Normel i I I I
2 1 I, ,,,, I, l D.m.on : WA 4., x 106 I p. 3 I 2.0 x lo a I, ,, a g y,,,
I I il Redletion Oose 1i I I l l l il (Red al I I i ( I I
i l I 15 : Tear Accsoent i 3 I p. 3 I i i ll Redletion Oose { l . 9 m 10 l I {
I L laiting f avirotusent s IRMsl I I 3 l Test and {
l ll I
I l l i Amelysis l None l II l i 3 I I tocction: Mothenical Aging i l p. 2 l 194/ 38 1 I l l Penetr ation Arme (MPA-4) !! l 104/40 I (90*CI I I i l Red lane: PEW Pump Aree ll (*F/ Years) l i l 1 ll l
i i 8 I
l IPS-II) ll 1 i s
I I i
a I I WA I Mone l a l I WA I
- I I WA 1 1
I to-est tievation (~l 4* jil ,
l WA I 4 l
I rfood Lo w l: Note i Il Sutnurgerte l l l l Notes:
l Abow flood teml: Yes]
l.
The f lood te.wl4 for Moch. Penet, e.4e and FCus Document at ion Ref erences:_ 17, dated 7/22/85, Pisup Aree eso (-9 25'-18 and (-121'-6" Service Envirorument Criar t, hv. B986, April, 1980. respect i wly 2ili y
' 3. Of4C Drewlsql No.80stred9763-F-300289 1 Flame and Radletion Resist ant Cables. 3. B/W Report No. 2.The equipment are in Opera
- 2. IP-7 4934-01, file No. 170-06-01, Note 1 of Assessment Clieckli st No. Code C for those events which c.im
- 3. Se at> t ocA (Q 10/23/83.
4.
Slu-9e,265, ut sc t et t.r. F looding stuor Matrim, these parameters to be harsh le.i t liese equ i pme n t. .
i 9 u..n
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il I i I n I WA I Mone i i
il I -- I Note 2 g ,
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l l i g il l i I I Eq;wipment rypes IPsign i i l j 1 Tetuinal Blocks ll I ;
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il 1 l I I
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I i I Is : a l WA B WA I None I i I 1 Model Anter: ll Oienical l WA I WA I WA 1 i i I I l $ prey (PHI i i I I ~1 ll I i ll t I f I I i l
i i a i 2 I I I
i Auur ac y :5pecs WA il s I i None j Il eu 3.or normai s 6 l p. 3 I s i p. 32 l Test I I Damon: WA 1 2.20 x lo I I il Radletion Dose 14.2 i = 10 i I I i I (Red st I I i ll i i l I is user accioem s S l p. 3 I I I i il Redletion Dose i! 1.9 m IO I I I l l _t i ilt ing Envi roesnent_ IRest I l Test and i l
il I
I l l l Amelysis ! None 4 if i l 8 1 132.8/40 1 3 I I I Lacetlon: Machenical Agitg l p. 2 I I I l Penetration Arne OPA-4) II ( *F/ Veers) 1 804/40 I i l 1 fled Zone: Pent Pump Ares ll I I '~l I I 3 3
i i les-ll) 11 i I 4 i i il i
I ,
B i l WA l None I i gg l WA l WA 1 3
i l 4 i ! !
I to.est taevetion:(-) 4*-sil Sutamorgerce i WA l !
l F lood towl s 8 tote I il I i __
jy "- -l: n= ll 1 Notes:
- l. The flood lowls for Mech. Penet. esse and IU w Dccument at ion Ref erences s 17, dated 7/22/85. Pump koa are (-) 2S*-Il and (-321*-6" re spect l wely
- 1. ui &C Dr avi rug No. 9163-F -3002 8 9, Service Envirotomont Criert, Rev.1S809-87, States forstnel 2.TheBlocks equipmentand Test are5.Itc.tes, i n Ogier.ibi l i t y I P- f itA& Oi , A l t on Te st Repor t N.
2.
Nv. 2 S/6/ts). 0 7&O6-01, N .to I of Assessment (Mchilst
- m. 2. Code C for those eventr. which f**s c.in
- 5. S eatte ua A IQ l lie W.
( ut dC lof fer, f f raxil.=j Liudy Hatrim, 10//$/8S. t heSe [hlrameters t o be l1.i r Sll
- 4. S pu-w,1 t 18050 s *sjtli['p en t ,
i . i . ... " ,
_ _ _ _ _ ___-m __m__m- _ _ _ m.-__m
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- I 2 1 il I i i 1 Test esone l cm e -462a 18 ensk i p. 2 470 1 P, 9 i E-& -44 3A reture 179 ,
T I l g I I , j l E-CP-44 38 I I g 3 l g g I
18 I I i j I eso,e :
I ll 8 I Note 1 Test ll Peak l 1 Isote 2 1 l g g Pressure I --
l l l g Equipment Type Il l l I l il IPalg) I I 1 Tc:rminal Blocks I g f i 18 l 3 i No , I l I note 2 ITest l Relative I Not e, 2 1 I l Manut ecturer
- MP namidity 4
- I I ( l il i I 1 1
't f 18 til l 1 i e
a i ll l s i
s l I I i
16eosal n=taer: PIDG is i I i I WA l Test I kne I
I choolcol i WA 1 WA l i i
il Spray (pH3 l WA I I i I I i
11 i I l l 1 4
1 il l l I 3 8
I ll I I I 2 l l l Accuracy:5pect WA II 40 year Normal I i l I leone i WA 6 l p. 3 8 I p. 8 i Test i l Demon ll Radletion Dose i I4.T m 10 l l 2.59 x 10 I i l i I l l l I Rad s) l il i i l l i I 1
! I I
ll : iear acciosa I 5 l p. 3 I l I I il medletion Oose ii 1.9 m 10 I I I i i t lett ing Enviroment: IRws) I l Test and l I l
11 l
4 l i 2 l Analysis l Mone i l
Mechanic al ll i i l p. 6 l l Loc at ion Agi ng i l p. 2 l 194/40 1 i
I Penetration Aree 19PA-48 ll ll l* F / Tear si i 104/40 I ( A'cl i l i I Red Zones POCW Pump Aree il 1
I l 8 i
I I IPS-lit l i i I l
ll a
s i
I l I WA B None J: I WA l WA 8 I 8 l 4 i I Lowest Elevation: (-) 4-911 Sutmergence i WA l l g _
i f lood towl leate I yes l ll l l Notes:
l Atwaw Flo d Lowl:
- l. The f 1004 levels for Mach. Penet. eres and it 8v Daument at ion Ref erences s Chart, Rev. 87, dated 7/22/85. . Pamp Area are 1-1 25'-18 and (-128 8-6*
Service invirorsmerrt swappcti wly 110-18004, Rev. O, 2/2/82.
3.
Ol dC Orawing No. 9765-I -300289, IP-34313-Oi, #f Quellitcetion Iest Report No.
2.The equipment are in OperabiIiiy c.ii.
- 2. Nov. 2, $/6/83.3.
OS70-on-osa, Rev. O. Code C for those events which I..:
- 3. lap.Il calculat ion m). 10/25/85. these parameters to be harsh 4.
ste96/63, uf ac letter, F looding study Natria, tbese equ i pmerit .
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QUALIFICAllON EVAL Prepared By: $
Public Service any of New Hampshire Check *: sy 'f, ,,f f.', , / /, ,, ,
ost.: c' ,i Seatsook Station EQUIPMENI QUALIFICATION FILE NO. 170-06-01 .
D>cket : 50-443 vuun enain F 1 vuai s s ion envir 1 vuosivicaison i Items rosTusavec tnvironmenT Reference l Nothod l si Reference l Value l i g
Par ameter l Valuo l a i
i l i l Equipment Descrnu.. Iption lI i I i i l i None s
a ruisn=2= u-ss i I 1 Year i 3 i Test and I I 9763-006-170-06 II OPw atlas flee i 1 Year i l l l Analysis l g
il p.1 l ) i , g I Equipa*nt 10 No(s).: l , g 4 I I I I SS-CP-482 g, i l P 74 and l None j g
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i e i l l Cable n i I I 4 st lNone s
i stelatin i i 100 p.28 l 1 Manuf acturer:
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l Model Numbw :FirewallIl l
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l Flood Level:(-) 21*-6* l l Above Flood Level: yes g Notes:
Rev.17, Oocument at ion Ref erences:
97 6 3-F - 300 219, Service Environment Chart,
- 1. UE&C Drawing No.
dated 7/22/85. Flooding Study Hatrix, 10/25/85.
-96263, UE&C Letter, Ha* 8 58 "a
- 2. S /14/86. ea.je . 4 l- li
.11 C.ticul.ition No. 0570-01.5-0911, Hev.0 ~
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Am; 4.
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QUA418 l( AllON t ee4 BC: WOm Stifi ., I N Prepared Hy: % G .3 _Date *:'* * '"
Put,I ls Service Comany of New llgshi rus Seabru2k St allon 10ull Mi HI QUAT tilCAll(N I It E NO. 170-13-03 Cinicked Hy: .,
- y I(iste:3, % -N Ou te t : 30-443 wai s t ied e nvi ronment i waisiacesion IFsra m i 1 Postu r ate d E nvi rnesuent s i Re f erence l Method l I tems i 1
II Value i Ref ererte l Value l Pa ramete r i I 1 Equipment Desc r ip t ion il I 3 I I I
I Ittt hese Uribr No. . II 3
1 I Year 1 3 i Test and i None Operat ing i I Year I i l Analysls 1 a l 9763-006-170-13 11 I p. I l l l ii TIsmo l l l l l I I I i Equipment 10 HotSl.: ll I l I l l l I I 'l l f [1 -+et-9 7 ll I I I I I I Iest i None a l ([1-89+- 116 Il l 44S I 2 Peak I 37S I I I i i I il i 3 I I P. 22 l I l ll leaperat u re I P.
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Notes :
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Der ument at lon 14n t erenc es ;
Ciert, Nov. I1 //??/85 Ut AC Orau B rq No. 9 T63-1 -300219 Ser wi(e f n,I forilegenesuentt r ic Penetrat ion Assemlelless for
- 8. IP-73457-Oi, Design Qualif ic at ion Hmort
- 2. IPS- 410f.. esa tmi 88/23/83.
Class ifCalc Serulat vireion f or Seabrtx>h St atRe No. OS10-032-Olo, ion. No.
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11 i i i Test I s&2ne I I 63 1 2 l i 18 i I I I I p. 6) I l Il Peak p. / l l g i l 4.d a l l l I (quipment Irpe: la t'ressuro l l i i l iPb43) l i 1 l Soltamald Walve 11 i i I I a l il I I 2 ) Test l 'Nne i i 100 1 l l I il l 400 l 1 1 l p. All i 11 %lat i va l p. 1 l p. 22. 23 I i 1 i Manot as.turor : ASCJ thelJlly I l I l l l ll I I I l i Il til l I I l I i i l I I i fest i N/A 1 4toI Natsor: ll I N/A I 3000 ppe boron l 2 l l 18 N/A l p. A20 1 l 108-4 4 tt- 6 ll Chemical i l i as uoric Acid II p. 22, 23 l l l I l Spray (pHs i I pH = 10.S l il i l 3 l 1 ll l l I i l l I I l l l Ac ur ac y : Spec . N/A ll I I l l i ll 40 Tear Nrmal I l l Test I maa l lbaso: N/A 3 l p. 2 i 2
- 10 0 1 2 l 1 l
ll ReJlation tbso iI84 10 l i I P. 59-62 l I ll IHadst - 1 4 l I l t I ! I llTTe~ar MccioenT I l P. 2 I I I l ll Radiation Lbs.s 1i 6.1
- 10 I I I 3 i Limiting invironerent: Imd s) I 3 I Test eno i pain. J l
Il i I li3.9/2.l*> I 1 Analysis ! l l Loe4 tion: M5 & (W Pipe Il A l laj l i to 1 I 1 (I14.3*Cl I ) I I chose (PcW-5: 1I i p. / I I l l t* /fearsi i i Nf* I I I l ama tone: M & tW Pape il 1 1 1 i i 1 8 Chase (PCW-Js il l I I I l l a I ll a I I WA i mne i 1 is a I I WA l g- I i WA l 1 to sse Elevation: 28*0" 4 11 Sutmaar genco l N/A I l l f S ' >= ll 1 l I Flead imvel: Yes il 1 i I l Notes: lg Ano e flood Level: mte 111 Ih.ormal 14 f e account s for tie.st re w is. normail y 1. ikxumen t at I.in Nf orunces :_ I f, 7/11/d*3. energlaed valve. Vaive do onorgi ses to perfoa m
%s vic.s Lnvir.u nour th.se 3. mv. P-1 blonold safety function durinj acclJont conditions.
- 3. ut &C t ar .se i ng m . 9 f b 5-t' - 100119,AQ4-bl566/Hovi sion O. Hopor t ori 04.si e f s cat2.ionAlthough t F- # l's4 7-ul, of AW N Installed, this equipment is anst presently 8ths lowest elevatlost for PQf-) and 2.
Ustvos. M.$ rote 1, 1961. 0*> 10-011- 1 14, Hav . O. 1 PCE- 5 I s 2ts' -u". Hovision u
- 1. Impoll L. sit.ul sf lon %. Page i of s h &C lot f or aIJ3-01-0/,ldr essed la Y At C una f f ema.fi n ; S to fy 4alr = .Assowment s' sum k I 4 sI taal.s 4.
4.
'3 'giu - M* /t, t*2:4:4, s utsu i s ,k i O 6 I le W.
e
l QUM if lCAT ION [VMt,ns lON tsolE StHI Pubi lC Servl(e Company of New Hampshise e~a-da: v u+ Oat.: Sea . Sta,l_ 113-04-01 Cte(bed by: [u, jf pate: g (WIP14 NT QUAL IflCAll0N IILE NO. Dus.be t : 50 443 I GaallfleG En wl,Lnast
,o lon I, LAaf ,a., S,TanSI* ,
5 it)stulated E nvironment I yeal,i ,e, f i c,,eT Il , ,a,ue , ,,e, e,_ e , I v.iue I ,le , .,.,,c . im-gr e ti- e i; Pa-te r ; ; 3
; , e,, a,,, ;% _i I , I , ,es, l I i 9 e+.-i n-04 ii 0,.ra t i.,g i i v.a,
- p. 3 1 1 i Analysis g g Tl** I I g g Il l g I l l g g g
IEu ment 10 statsl.. ll l l g g 1 -2171-1, ll I I I peune i I CC-IV-2878-2, is i I I I 40S I 2 i Iest l l i CC-1Y -22 71- 1, il Pee i 13S l l p.63 l I T emperature i 1 .p. 3 I I ll l l l a (E-IV-2278-2 ( *F ) i i I I I t II I I I I I 18 I I I I i I I 2 I Iest i None Il 1 63 1 l l 3 Peak I 0.4 l 8
- p. 62 l l l I i ll l I p. 3 l I i I qui lment lype: ll Pressure I i l 1 (Psig) i i i i i i l Selenoid valve ll i I I I I I i i il i I 1 2 i Test I seme il 1 100 l l i Helat t wo I 100 1 1 l p. A28 l l
l Manuf ac turer : A5(D ll I p. 5 l
- p. 22, 23 I i 11 Huelof ty i I I i l i I I I I Il 438 I 1 1
I I I I i 1 Model nameer: 18 I 2 l Test I h/A 1 I i N/A l 3000 ppe borun 1 I i 1 206-sol-2Hvu if l N/A i I p. A20 t ll Clienic al I i as Boric Acid p. 22, 23 I i 1 I 5 prey (pto l l pH
- 80.5 l l I I
il 1 l I I ll l l I l I I 3 l 8 I I l l l Anur ac y : Spec : WA ll I l i l Desam : WA !! 40 Tear Normal l 6 g p, 3 l 2 l Test I kme l ll Radiation Duse 1i 4.7 m 10 l 12m 107 1 I I I ll ( Rad s) I I I P. 59W 8 I l I I ll l Tear Accident i 5 p. 3 1 8 l I i 1I Radiat ton Dose 1I 3.9 m 10 l l 1 I I I t Imlt Ing invirt2rument : (Rads) l I I i fame I 11 I $ l Test and i- l 3 I i 248 /9.56 1 l Analysis I i I t ot at ion : Primar ll i 104/40 l l I I Aumillary blog. (fts-Ill ll Agi ng I p. 3 l 1120*Cl I I i I il I *f / Tears I I I It)f
- I i I I a li Had lone: Prlear Aamillary blog, if"8-ill 18 I 1
i i I 3 3 I I I ll I I I I I I #A I II I I #A I I "' i I WA I I
- 38'-4* 18 '
I 4 I Lowest E lemt ion Sutmergerice i WA I g I f lood Lawl: (-121'6" Il I I I Il I I I Atm> w I lood L ow l :64)toYr5 2 ll l Notes : I 1. liermal li f e accourri s f or teet s ise la nos mal ly Doc ument al lon Ref orwnces : hsv. 17, 7/22/8S. ener gi sed val to. Valvo de-enesgtses to peafe.es Lur vice (nwirotusent Chart, W -l Solenoid solely f ust tion <&st I ng accident sfeondif f ons. el shown
- 1. Ut at Os a f rvj No. 9163-f -300219,I P-71S41-02, NH-67360Miewis ton 0, Hepor t on Quaillicat 2. Ilie lowest ionelewet of A5(4 lon and iload 2.
Vai te s, March 2 196 2. OSiO-0 32-020, New, l. # egresent ttas sursi tase for tle locatim of lopull Calculet lam fa). Itu egalpment ID Nus. Iistud.
- 3. YAIC on a l<mmli tsj 5f udy Hnt s in.
- DIF96 Ut SC L eiter addressed to I 73-04-Oi, Assessmeril 4 ten biist Note 4.
4. S. I" Jet, ook iQ I lie N. e.e,. l .. .
01At tilCAlltDe EVAa unilGI tdoi* SHft i Prepared By: _kg /Er.w Date: _f[ fg l'ula l lt Servica, Company of Nes Hampshire Date:J I /,f/ s.. r- S t a , , - l@HM N1 QLA& lilCAll0H f IL L NO. 173-04-04 Ctec6ed By: b. ,b ff < a Duc6et. % -443 g - g
= = = 'as i ye.,m ,,,nc e 7.C " ** "" *"* a',,,,, j m' ",;cy,'aa ; ,, ,
ment y,sc ry son , e.r. t.r
'{"' *E" i year i l y y,,ar ! 3 l 1.st .no g No.,
l I 9763 406-173-04 0 ating I i Analysis 8 P. 4 1 I I I iquipment 40 Noisi.. ll l g g g g l O 1 , I let-f T-616-1, ll g y , lName { l RH-4Y-blV-1 1I l 405 1 2 I lest I I 11 Peak i 196 I L l p. 63 I l Iamperaturu l l p. 4 l I g g l ll (T) l l l 1 l g g 11 l l I i i i i : : i il i i.Noc.r, I is i i 63 1 2 I test . i i Peak i 1.0 l I l p. 62 i el ll I l 1 l I Pressure l p. 4 l l l t quipment type: Il l l l i I ll IPsig) l i i i l i Solenold Valve i I I I I i l Il I 2 i Test l Nova i I i 100 1 l / I Il Relattwo I 800 l l p. A21 l lI Manuf ac turer: A5(X) ll l p . 4_ l I l ll Hueldity l 1 I p. 22, 23 I l l I 158 l 1 l I i I 11 l l a i ll l s a i None 1 1 Model Nuoter: i 2 i Tesst il N/A l 3000 ppe l>oron i I I i 206-Jol-49u Chemical i N/A ) I as Boric Acid I p. A20 l I I i il i i l p. 27, 23 I ll 5 prey (pH1 l l pH - 10.5 I I I I l i I ll i l I I I i _ I I g g ! l Accurac y:5pec: WA 11 I I g g i Dennon : N/A ll 40 Tear Normal I 6 ; p, 4 g 1 Test i None I ll Radiat ion Oose iI 4.7 m 10 i 12m 108 1 2
- p. 59-62 I i l i il IRads) : I l i l i s I I l i 11 i Tear accident I 7 I p. 4 I l i 3 I
l t imit ing invironment : ll Radiation Oose 1I 6.0 m 10 i i 3 I (Hadst I 3 l None l ll i I 5 1 Test and i 1 I t oc at son : Equipment Vault il 3 l l 248/5.79 l Analysis i Agirg i 104/40 1
) ll20*C) I i I l li v -eA l 11 I p. 4 i l f *f / Year %) l i It2te i I I i Had Ime: Equipment Vault il i i I I I I 3 i Itv-6A & 6el :i l 1 s
i I I I I ll a I I i sa s l I WA 1 WA i None i WA i ' 8 g I L owest E lega t ion : 1-)37'0*l1 WA I -4 i I ' Sutsiergarte l I I I - .I I f lood to wl: 1-1$5'88* ll I I I 18 l l i Atm2ie i lood L e te l : Nate Yes 2 11 3 __ Notes : i Iteraal life accounts for test rise la normelly cucument at ton Heterentes : 17, 7/224$. l. energised vatwo. Valie de-energises to per fuse Solenold saf ety f ustflon charing accident cosullflons. 1. 2. Ut &C Drawi ng No. 9763-f -300219, 5er wito Envi ronment Chart, fetiv.IP-7/S4
- 2. The lowest elewallon 7-02, and fACH-67368Aewisi lood lowel shown .,8 Val was, hrc h 2, 1987, r eprese nt tie mor st case f or tim locat ion 1.
l ape l l C o l( u la t l on No. 0*> J(H) 32 -020, Rev.to YAtC oseifemmaissJ S tudy 64at r i m . ttu ecpipaavif ID Nos. listed, 3.
- 4. S itt mat, ' 3. Ul &C let ter addressesd I13-04-01, Assesseesis (i.est blist Note 4. l S. l' *Je t , e in.h I Q l lie 94>. g ,es. . visI. . , . . ... / .
QL90 If iCAI 80N ' VAL ...I10e WDfW $Hffi Prepared By: / p g j4,, p.g . : Jf/j, l Pub t l( 5ervite Company of New Hampshire CincluHf By: gjj jj p 9,3 /g jg 173-04-01 Seabrun Statim EQUllMH1 Qu& lfICAllOf FILE NO. v r a 14 6e1 : S0-443 Q rostulated t nwi runment : I *** I 33 I a fieference l tmd 3 I Value I Reference l 19:1pment Descr iption il Paramet er l g i I last and I home I thrchase order No.: 3g g I i l 1 Year 3 i i ll Operat ing i I Year l l l Analysis g I 9703-006-873-04 II"* I I P. 2 l g g g II l g I l 1 l i y i E9sipment 10 Notst.: 18 I i g i i H5+1 - 300 8 - 3. 4. S 6, Il y g I lest I kne a i l 405 1 2 l l i %+1- 3002-3, 4, S , 6, Ig f%aA I 3n i l p. 63 I i MS-P T - 3003 - 3, 4 S 6, il I p. 2 l I I Temperature i I I l l i E+ 1- 3004 -3, 4, S . 6 ll ti l i I i l l l 3 Il I i I I I i Nono 1 il I I I lost I 63 2 l If I I i l 1
- p. 63 I l I Peak I l l l i ll l p. 2 I i i 1 Pr essu re i 4.8 l l l i i Equipment type: il iPstgl I I L I I
!! I I l Solanoid Valve il l I I l Test i kne l I I I 100 l 2 II I i l l l 3 l ihslat l wo I 800 I p. A28 i i l Maxut at tueer: ASOD 18 l p. 2 8 I p. 22, 23 i i il Humidity I I I l l I Is) 1 1 I l il l I I I l I I i Test i N/ A I ! Model Nuoter:
ll I I I 3000 ppe t=>ron i 2 i II I WA p. A20 l t I L 206-3BI-454 Ctemical I WA I as Boric Atid I l 1 11 I I p. 22, 23 l I 1 (206-388-4 % 5 pray (pH) l l pas = 10.S I I. l ll 1 3 l l I I I 13 I I 1 i l I I I I - l Anurat y:Spe(: WA ll I I I l Iest l Ene 1 f I Dumm : WA II 40 Tear Normal i I I P. 2 l 2 m 108 I 2 I i I il Radiation DoseI II a lO l i l P. $9-62 I I l I Had s) I I I I ll I I __I ll i Tear Accident I 4 p. 2 I I 1 I I I I Il Radiat ion Otise 1i 8.2 m 10 I I I 1 Llatting Environment: I I mn. 1 Il IHads I I I I test and l 1 I I i 273.9/3.2 I Analysls I l t ot el lan : M5 & FW Pipe II i ISO I l (134.3*Cl l S I I I Agi ng l P. 2 I l Chase IPCw-38 11 i *t* I I I _i 4*f/Yearsi 8 I I I Had 2me: M5 & F w Pipe ll l 1 I I I these iPow-31 ll 1 1 i I I I I 3 ll i I WA l None i l : I I g is I I i WA I WA 3 8' 4 I I tonest f low s t on : 28'0* 11 I WA 3 I l I S'S* Sutmu rge tte I I _ i f loud te gel: ll I Yes !! l I I i At,o w Iluod Le wl: I Notes : Note 2 11 i 4. Tiermal li f a account s f or laat r i se in nee ma f f y Documentat ion Heterwaxes: lesw. II, 7/12/85. ones'gised walw. Val go de-ene,91 ,,, go p., gy,e Ser vit e En vi rurune.nt Char t, SCO NP-8 Solenoid safefy furctim earlag accident torullflons.
- 1. Ul &C Dr au l taj No. 9 763-f - 3002 8 9,IP-lh47-02, /QH-67368Aewiston 0, Haport 2. Alt tuugh t his acpslpment is not presently on Q.saillicat ion of A 2.
Installed, fle looest elevalitse for ftw-) s.=s Val ses, Nrch 2, IMl2. 1. Study Matrim. ITI-3 15 28 ' -O * .
- 3. lapell taiculat im No. 0S70-032-020 Rev.0140 let ter addressed to YAll' on i leuwel esjAssessment ( fun,l'agee b a1 +4lst Note 4.
.I , l . .
4. S. ShM6 P 9et, ook IQ file Hu. 173-04-01, 9 9 l
*~ ' > lc al la > - la==Sw Prepared By: ,k g A, .,,g ggf, euoiic Set ,l os m . ,as,, o, ... ,,,,,,. % sat,ruA Statins, l'"*at: $0-443 tQun w nl Qts litcAlim yItg no, 173.o4.ol c,'oched fir: , bh. sd//,d- pate:M,kpf, ' l ,;'"'-'"'";;,ome ; - ';;>c;> * , - ; Nt,;p l j, g -mt g le, l', r.--t., """ Ta7s"' ]*' I No, e,,_ o ;,,ea, j 3 j ,,,, ,,,4 j ,,,,, j u s e o-i>>-04 n 0 ,.mtin, I I re, 1 ; i~, sis ; j l "- la4 i i . ..m t I m t,... !! l g a g g l
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- p. 62 I t i ll i p. 4 1 1
l l Pressuru I l.0 l l I I I ( quipment typo: ll IPhlg) l l I I I a l l Solenold Walve il i I s il s i i None i I i i 300 1 2 1 Test l I II I I I
- p. A28 l l ll blat l w I 300 I l I i l Manuf ac tu rer : ASCO l l p. 4 i p. 22, 23 I l 11 Hueldity i i I I i ( 5) { i I i I
il i i I I i II I I i N/A 1 i ModeI Nat=r: i N/A l 3000 Ilpa tmron i 2 l Iest I I i 206-3el-4Nvu il N/ A I p. A20 l il Chemical l l l as Boric Acid Il p. 22, 23 1 1 I l Spray (pH) l l pH = 10.5 I l l I ll l I I i il l i I 8 I I i I l I l I Aauracy:5pec: WA ii I l l i None i . l Demon: N/A is7 Tsar reormas I 6 1 6 2 i Test I ll Rediat ion Dose il S.3 = 10 l l2m 107 8 I I l 18 I Hads) l 3 P S942 I I I l I I I I 11 : Tsar Accident i 6 l I I ---- 1 I I I L imit ing invironment: li hdlation Dose Il I I i B 8 l None l ll tRads ) e i i i lost and I I~ I Locallm: Equipment vault il s 1 1 I 248 M.56 i S I Analysis 1 i Aging i 104/40 i i f l20*cl l I I It v-eA s ll f *f /vear si i p. 4 I Nute i l I I l t bd 2me: Equipment vault il 1 1 I I I I I I Lv-tA l ll I I I I i I I I g Il I I I I None 1 11 I I N/A I N/A l 1 i N/A I S'0* 11 I 4 I l tomest tievati m1-3 : SS'il" Il Sutmergence i WA I I I 8 I I t i f good towl: il i I 1 l Ano w f f ood to wl : Ves ll 1 testos: _ l
- 8. Ilie rmal life account s for hasal r ise in teormall y luxumentation Heterences:_ acergised valve. Val w de-energises to perfose Sesv l us i nwi r onmeel Diatt, Hew. II, 7/22/85. saf e ty f unction est i ng accident u2ndif fons.
A5(D 14*-1 Solenoid s
- l. LA LL Os aming No. 9763-f-30028 9,NJH-6 71Nf /fts vlsion 0, Repor t usi Qual i f ic at i m of 2. Its lowest elevation and iloues lesel ' tamn
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lase l l u k u l a t i m No. 05 70-O 12 4)20. les w.VAIC m i luoding Study Matr i m. SistF 9t,/6 3. ul &C L et ter addressed to 3.
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S. 6. P tses Sib- /O PLf41 L et ter (s om H.l . Bleut ras t /J .W. Obwlsle.s. Pape4 . .f 4 u
QUALIf4CAflON 1AIION WGtK 9ffI p kdl:g1 Prepared By: M 8 ** y JW ,ste:
.e Company of No. Haapshire F eut.ile s Seabrt=A S t at lon Checked By: @* om (f. u Datellf14,[8C fQulPMNI QUAL IFICAllON FILE NO. 113-05-01 '
s Om het: S0-443 yn,asssses Environment i quas ir ic at ion i oursvancing i l'ostulated t nwisc.r.t a Met hod i stems l I II i Falue I feeverente I g t'arameter i value I Neference , , i l__ g i tquipe nl Dewalption g 3 i Test and i None i l Purthese order #so. . s: i I I l e year i 2 i i I 9765-006-873-oS lt oper at ing i i rear I I l p. 4-7 & 4-14 i Analysis g g II II"* I g 4 g I l l 3 g g g l lquipment ID Skatsl.: ll l l l , g l y y i CC-15-24 74-8 ll i y g y g g ,,, g ,,,, g i CC-15-2 4 7 8 -2 11 l l gg4 l 13S l p. 4-5 I l g i CC-15-2271-1 11 Peak l P. 3 1 i l l Temperature I I I l CC 22 7 4 -2 Il l i I g , i il ( *i l 3 l 1 l l I 1 il I i 1 i I l 2 l Test i None 1 I il I O.4 1 1 1
- p. 4-5 l i l il Penh 0.4 1 l
I l p. 3 1 I l 11 9uspammt type: Il Pressure 1 I l 6 I (Pstga l i l l 1 I t Ini t Sultth 11 l I I 18 i i i l None i I i 2 i fest I Il e i 100 l i i 100 1 l p. 5-10 & 4-5 l l l ll Relettwo I i I i Manufacturer: Maeldity l l p. 3 I l l Namco Controls ll l i I I I It ist I I I l l I I I I s I nideI Amber : 18 i l WA l None i 3 l N/A I WA l I tA7$0-80100 ll I WA l N/A I l l ll Chemical l l l I I i il 5 prey (pH3 l I I I I i i I I I il l I 3 I t l 3 3 l l Accurac y: Spec : N/A il l I 3 l Il gu Tear reormal I 6 I l i None l l Dommm: WA 11 Radiation pose 1 4. 7 = 10 l p, 3 8 2 l Test i l 2.04 x 10 1 t I l ll (Rals) i I I I P. 4-6 & 10-14 lI l i l usar accsaent I I l ll D I p. 3 I I I 1i Radiation Dose iI 1.9 m IO I I I l t tot t is.1 ( avironment : I 3 I 11 (Rads! I i 8 l Test and i None i I 1 2 i ta stion: Pr imary Au.. Il 5 l l l 104/18.18 p. 4-14 i Analysis i I Aging i 104/40 1 I l I slog. (Pu-Ill il ( *f / year si i i p. 3 8 I 3 I l I had lone: Pr imary Aum. 11 I I l I . I I I I i eldg. (Pe-all 11 i I i I WA 8 l None l g Il e i I WA l si a l 5 i N/A I I I N/A i I l g l I to est tievation:1-121'-6= 4 78-6" Illl Sutmergence 1 i , , , i ffoodwei,ewel:6-4 L.,el , u s ;; ; Ates: o.. _ ,.t.tless mt.re .s. Neviston i 7, 7//J/8S, Ser v ice Lnwironment Chart.
- 4. Ut 40 Os avIng No. 9763-F-300289,M . QIH 480, Hewision 0, dated 10/1/81.
J. # P-7 3S97-04, Namco lest Repor t173-0S-04, Assessment Cicc Nte k list,4.
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QUALII1(ATION [VA6 .ON NORK SIEE1 prepared By: b ] /X+=v Sate: I!/M,A, f Public Service Company of New Hampshire Seabrook Station Checked By: M I , k M 0ste: J 2/ #4 Doc k:;t: 50-443 EQUIPNENT QuALIllCAll001 FILE NO. 177-05-03 -
> que11 Tied Environment > quaisticatten > cuts 4Jadtag >>
' D Festulated Envircement value > zererence > Nethod > liens n Farameter > value > zerereace >
> Equtwat Descriptica > > > > > > Furchase Order No.: D > 1 > > > Test and > > 97 h3-006- 173-05 n Operattag >
p.1 > 204 days > 6 > Analysis > None , > n itse > I year D > > > l > Equipment ID No(s).: > > > I > CC-IV-2171-4 n > M > > 3 > >
> CC-IT-2171-5 > l > > lione > > CC-11-2271-4 n Peak >
135 > p. 3 > 335 > p. > Test
> CC-11-2271-5 n T r > > >> T( r)eture >
n > > > > >
> > > > None >
n Peak > B.5 > 3 > Test j > > 0.4 > I > > >
' > Equipment type: n Pressure > P. 3 > > P. >
n (Pstg) >
> E/F 1ransducer n > >
y > > > None > D Relative > 1 100 > 3 > Test
> ftenxfecturer: > 100 > p. 3 > > p. > > >
D thmidity > >
- > hasonellen n (s) > > } > pendel leimber: n > } } }
D } > > >
> a005A > 1 > N/A > None n Chemical > > N/A > N/A > p. 3 > N/A > > >
n Spray (pel) > n > > >
> Accuracy:5pec: Yes n > > > > Demon: Tes D 40 Year normal ) "
6 7 3 Test > None
# p. 3 1 a 10 > } $ $$"*d'M} $
P* >
> > )
n 1 Year Accident > l.9 s 10 9 > 1 >
> t t7t tlee Environment: n Radiation Dese >> > P. 3 >
n (Rads)
$ $ $Testand j > Locattom: Primer Aus. M >
{ , { > pp. 4-6 > Analysts > None >
> p. 3 > 104/13.95 (0 rs) 104/40 > >
ear > i RM Zone: B149 . P8-III f 3 f > >
> > None M > > > N/A > N/A > Lowest Elevation: ??' n > > N/A > 2 > N/A 3 3 3 D Sutmergence > > Flood Level: (-)21'-6* n > > Above Flood level: Tes Notes:
1 Doctmentation
References:
No. 9763-F-300219 Service Environment Chart. Rev.17. dated 7/22/85. 1
- 1. Of&CDrautnheabrookStationFloodingStudyHatria.
58lJ-9626 3. 23 '. Cygne Repor t No. 81041-RN002. Rev. L. 2/8J. Checklist Note 3. 173-05-03 4 5sabroot station E.Q. File gio,
'f o [ f 'No. 17 3-05-0 3 Checklist. Note 8. S i ., i
QUALIFICA). (VALUATION WORK SHEET Prbilt Service Company of New Hanpshire Prepared By: M/ /X,,v Date: VI, Stabrook Statton ,f Docket: 50-443 EQUIPMENT QUALIFICATION FILE NO. 173-07-01 Checked By: h Date: f //j I V Postulated Environment Quallfled Environment qualtftcation Uutstanding Equipment Description Pa rame ter value Reference Valee wererence Method Items . . Purchase Order No.: Operating 1 year 1 1 year 2 Test and 9763-006-173-07 T1se P. 1 Analysis None l Equipment 10 No(s).: 6 RC-Fv-2881. SI-FV-2475.
-2476. -2477.-2482. -2483 Peak 1 4. p. 4-10 of Test and -2486. -2495.-2496 Temperature 37 5 p. 1 390 App. IV of Analysts None CAH-FV-6572. -6573. -6574 (OF) App. III
- 8. p. 51 55-FV-2857. NG-FV-4609 4
-4610. VG-FV-1661. -1712 I p. 4-10 of WLD-FV-8330. -8331. Note 3 Peak i
Equipment Type: Pressure 60 p. I 113 App. IV of Test None 521 nold Valves (Pstg) App. III Manufacturer: 4 Valcor Relative 1 App. III Test None Histdtty 100 p. I 100
- p. 57 (1) -
Mod 21 Number: V526-6040-6. V526-6040-1 4 Test and V526-6040-8. V526-5631-20 Chemical Boric Acid 1 App. III Analysts None 1.2% by wt. p. I 1.25 by wt. V526-5940-16 Spray (pH) p. 58 pH 7.5-10.5 pH 9.5-10.5 V526-5871-4 5 Accuracy: Spec: N/A 1 Demon: N/A 40 Year Normal 4 Radiation Dose 2 x 10 7 p. I
- p. 23 & p. 4-22 (Rads) 2 x 10 8 Test None I
of App. IV of I fear Accident gpp, ggg i Radiation Dose 1.04 x 10 8 p, 3 Linittna Environment: (Rads) Location: Containment I 4. p. 18 & 19 Test and (CS-12) Aging 120/5 3. p. 3 Analysts None 120/40 p. I Rad Zone: Containment (OF/ Years) Note I (General area /Not submerged) Lowest Elevation:(-)l5'-U' N/A N/A Mone N/A 7 N/A Flood Level: (-)20'-8* Submergence Above Flood Level: Yes ! Note 2 liotes: Documentation Rererences: 1. For evaluation of qualtfled If fe. the heat rise due Service Environment Chart, Revision 17. dated 7/22/85. to the flutd temperature and the energized condtt1on
- 1. Ut &C Drawing No. 9/63-F-300219 has been taken into account (Ref. 3. p. 3).
l 2. Impe11 Calculat1on 0570-032-070. 526-5631-20-2 Rev. C. 2/10/86.
- 3. FP-73759-04 Qualtfled Life Evaluation. Document No. MR 2. The lowest elev. and flood level shown represents the 4 IP-73216-01 Qualfication Test Report QR 52600-5940-2. Rev. C. 4/24/81. worse case for the location of the equip.10 Nos. liste
- 5. Seabrook Station. Equipment File No. 173-7-01 Assessment Check 1tst Note 5. 3. Equignent I.D. Nos. RC-ZS-2881. 51-Z5-2475. -2476
- 6. Seabrook Station. Equipment File No. 173-7-01 Assessment Checklist Note 2. -247/. -2482. -2483. -2486. -2495. -2496. CAH-25-6572 7 500-96263 UEAC tetter. " Flooding Study Matrix". -6573. -6574. SS-ZS-2857. NG-ZS-4609-1 -4609-2
- 8. FP-73135-03 MR-526-5631-20-3 Rev. 8.10/8/85. i -4610-1. -4610-2. VG-ZS-1661. -1712. WLD-Z5-8330 and l -8331 are for the integral position indication within these Solenoid Valves.
I Revision Paqr I o'
QUALIFirA. EVALUATION idORK SHEET 'j Pubitc Service Company of New Hampshire Prepared By: ~3.-, j /Pf<rw Date: 9/'/' Srbrook Station Checked By: Olm/ Dock 2t: 50-443 EQUIPMENT QUALIFICATION FILE NO. 173-07-02 ,
- Date: a V W Postulated Environment Quallffed Environment Qualtftcation UutstanJIng Parameter Value Reference Value Reference Method Items Equipment Description Purchase Order No.: 2 9763-006-173-07 Operating 1 Time 1 Year p. I 1 Year p. 38. App. VII. Test and None
- p. D-2 Analysis Equipment ID No(s).: 4 RC-FV-2831 RC-FV-2832 2 Peak 1 RC-FY-2833 p. 38 Test None RC-FV-2836 Temperature 375 p. 1 417 Nste 2 (OF) 1 2 Peak Pressure 60 p. I 103 p. 39 Test None Equi pent Type:
Solenold Valves (Psig) 1 2 Maxufacturer: Valcor Relative 1 100 p. 39 Test None Humidity 100 p. I (1) Model Ntsiber: V526-5295-Il0 Boric Acid 1 Borfc Acid 2 V526-5683-48 Chemical 2.31 by wt. App. VII Test None 5 pray (pH) 1.2% by wt. p. I pH = 7.5 - 10.5 pH = 7.5 - 9.0 p. 7 Accuracy: Spec: N/A I Demon: N/A 40 Tear Normal 2 Radiation Dose 2.0 x 107 p. I
- p. 24 (Rads) 1 5.9 x 107 Test None 1 Tear Accident 7 p. 1 Ltziting Environment: Radiation Dose 1.4 x 10 (Rads)
Lccation: Containment 120/ 5 3 Test and 1 (C5-10) Aging Note 1 p. 7 Analysts None 120/40 p. I R:d Zone: Containment (8F/ Years) Note 1 (General Area / Not Submerged) N/A N/A None LowestElevation:(-il5'-2* Submergence N/A 5 N/A Flood Level: (-h20'-8" Above Flood Level: Tes . Documentation
References:
- 1. Thermal If fe is based on room ambient intern Service Environment Chart. Revision 17. 7/22/85. Rev. D. dated 4/19/84 heating and process fluid conditions (Ref. .
l. UE&C Drawing No. 9763-F-300219 Qual. Test Report for Class IE Solenoid valves. QR-526-5683-6 FP-13400-02. 2. Equipment ID Nos.. RC-Z5-2831. -2832. -2831
- 2. and -2836 are for integral position Indicat
- 3. FP-73759-04 Qualt fled Life Evaluation. MR-526-563I-20-2 Rev. C. dated 2/10/86. within these solenoid valves.
4 Impell Calculation No. 0570-032-076. Rev. O. Test Profile Extrapolation.
- 5. 5BU-96263. UE AC Flooding Study Matrix. Reviston 2 034,8 g ,Pa s e i .. , ,
QUALIFICA. EVALUATION ndORK SHEET Putilic Service Company of New Hampshire Prepared By: M //M Date:f .r # Su brook Station Di,c b e t : 50-443 EQUIPMENT QUALIFICATION FILE NO. 173-07-02 Checked By: b,fd44[ - Date:j v a Postulated Environment Quallffed Environment quellf f cation Uutstandins [quipment Description Parameter Value Reference Value Reference f*7 thod Items Purchase Order No.: 9763-006-173-07 Operating 1 2 Time 1 Year p. I 1 Year p. 38. App. VII Test and None Iquipoent ID No(s).: p. D-2 Analysis 4 RC-FV-2837 RC-IV-2840 Peak 1 2 RC-IV-2874 RC-FV-2876 Temperature 160 p. 2 417 p. 38 Test None RC-FV-2894 (OF) RC-FV-2896 Note 2 1 2 Peak Pressure 1 p. 2 103 p. 39 Test None Equipment Type: Solenold Valves (Psig) 2 Maxufacturer: Valcor Relative 1
- p. 39 Test None Humfdity 100 p. 2 100 (1) _
Model Number: V526-5683-48 . v526-5683-56 Cheefcal N/A N/A None Spray (pH) N/A N/A N/A V526-5295-110 Accuracy: Spec: N/A Demon: N/A 40 Year Normal I Radiation Oose 2.0 x 10 7 p. 2 2 (Rads) 5.9 x 107 p. 24 Test None 1 1 Year Accident 7 p. 2 t ialting Environment: Radiation Oose 2.8 x 10 (Rads) Location: Mech. Penetra- 1 104/ 5 3 Test and tion Area (MPA-2) Aging Note I p. 7 Analysis None 104/40 p. I Rad Zone: Mechanical (OF/ Years) Paetration Area (MPA-2) N/A None towest Llevation:(-)l5'-0" Submergence N/A 5 N/A N/A Flood Level: (-)25'-11" Above flood Level: Yes lotes: Documentation References;
- 1. Thermal Itfe is based on room ambient intern.
UE1C Drawing No. 9763-F-300219. Service Environment Chart. Revision 17. 7/22/85. Rev. D. dated 4/19/84. heating, and process fluid cor.dttfons (Ref.
- 1. Equipment ID hos. RC-25-2837. -2840. -2814
- 2. FP-73400-02 Qual. Test Report for Class 1E Solenoid valves. Rev. QR-526-55843-6 C. dated 2.810/86. 2.
-2876. -2894 and -2896 are for the integral
- 3. FP-73759-04 Qualified Life Evaluation. MR-526-5631-20-2 0570-032-076. Rev. 0. Test Profile Entrapolation. posttfon indicated within these solenoid 4 Impe11 Calculation Mc.
5BU-96263. UE1C Flooding Study Matrim. valves. 5. Revision ? Page 2 of 1 03478
Public Service Company of New Hampshire Prepared By: M/#% Date: I h 4f EQUIPMENT QUALIFICATION FILE NO. 173-07-02 Checked By: b b4 Date: [J V Postulated Environment QualIfled Enviro..ir.ent quellIlcation Uutstand % Parameter Value Re ference Value Reference Method Items Equipnent Description Purchase Order No.: 2 9763-006-173-07 Operating 1 Time 1 Year p. I 1 Year p. 38. App. VII Test and None
- p. D-2 Analysis Equipment ID No(s).: 4 RC-IV- 2830 Note 2 1 2 Peak T ature 375 p. 1 417 p. 38 Test None 1 2 Peak Pressure 60 p. I 103 p. 39 Test None Equipment Type:
521enold Valve (Psig) 2 Mn.ufacturer: Valcor Relative 1 100 p. 39 Test None Htanidity 100 p. I (1) Model Number: V526-5683-48 Boric Acid 2 Chemical 8crfc Acid 1 2.31 by wt. App. VII Test None 5 pray (pH) 1.21 by wt. p. I pH = 7.5 - 10.5 pH = 7.5 - 9.0 p. 7 Accuracy: Spec: N/A I Demon: N/A 40 Year Normal Radiation Dose 2.0 x 107 p. 1 2 (Rads) p. 24 Test none I 5.9 x 10 7 1 Year Accident i Liniting Environment: Radiation Dose 1.4 x .107 p. 1 (Rads) 120/1.1 3 Test and i' Lecation: Containment Aging 1
- p. 7 Analysis None (C5-10) p. I Note 1 (OF/ fears) 120/40 Rad Zone: Containment (General Ares /
Not Submerged) N/A N/A Mone Lowest Elevation:L 516'-0* Submergence N/A 5 N/A Flood Level: d-020'-8" Above Flood Level: Yes Notes: Documentat1on Reference 5: 1, Thermal life is based on ambient internal Service Environment Chart. Revision 17, 7/22/85. heating, and process fluid conditions (Ref.
- 1. Ut &C Drawing No. 9763-F-300219 Qual. Test Report for Class IE Solenoid Rev. D. dated 4/19/84 Equipment ID No. RC-25-2830 is for the
- 2. IP-73400-02 valves.
Rev. C. dated 2/10/86. QR-526-5683-6 2. Integral position Indication within this
- 3. FP-73759 04 Qualfffed Life Evaluation. MR-526-5631-20-2 solenoid 'Ive.
- 4. Impell Calculation No. 0570-032-076 Rev. O. Test Profile Extrapolation.
- 5. 58u-96263. UE1C Flooding Study Matrix, Reviston 2 0>.7e e g.ee3-i
.,~ 15,a u 8.,s.t m .A. - s,. t i n .,s,.I o,: a,. L //o 7
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f&j4 f 0.ste: /d
. sat ><.esu %sJet..a 174-15-02 Ctwo.kol up: r 1.)ille*46 e41 v At is Is_ Allo;4 I Ill NO. y-th.kot: 40-445 w, ail iod tavirons=>nt i waai s t icat ion i uousranaing i FosTuT'sTisif T nWscisse a I Ma t tsod l Items l il Yalue i Hefurenc.s I i i ValM~ ~ l IT.sf. s osm .s a I I i tg. u n pmm t -Ikss. r lo t ton ll l'.sreastor I I l I I 4 l Test anJ l None l Furr h45.s ur Esr '*)- . II i I Y.sar i i l I Ye.sr 1 l Analysis l I 11 Oper. sting l l l 9105-000-814-85 Ilms I i p. 8 i l l l ll I l I l
1I I I I i i i t quipasnt til nel s t . : 1 I i 18 1 I I i l CL-LI-Itll-1,1,5 '
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! CC-LI-2191-0 2, 5 ll l *f i l l l 3 7
l f c-PI-e n t, i d-e*I-4 h i, il I i 8 8 I 8 I tb-rl-4114-1,4 fw-II- Il I 8 8 1 1, p. 47 I Iest I hoa* I I 4214-1.4. IW-t3-4154-1,4 li s l I i 73 I I f%.* I 0.') I l 5. A>P - 1. P il I i re-rl-4144-2,4 Il Pr. s sur s ! I p. 5 I I I 3 I s Osa B -s St >, cs-f I - 7 51t> ll I I I I il Wul8 I I I I e quip.m t typo: 3 I I 3 6 8 l Noths l i Pr assus o is ansali ter il i i I t, p. 41 I last li i e i 1001 I I I NIative I 8001 I I 5. A'P - la P 12 i I I i genor x tur.or : Il thaal si t y I i P- 5 I I il I I t i 1 l Hosa=2ent til l I i j il I ! I 3I N/A l nasmJ l l MJai Numtser : l N/A l N/A l N/A N/A l l' I il Chesnic al i 1 I I i g 11 8 , i g I I g g i we ac ,:sp.s. is, esti li I I , g 11 40 Tear n>real I , "2'** I t h.m m : ts.esti
' "*# 2. 21 a 1o' l 2. P. 4) I*s'
{ l I ll , l' 8 I I I I' P* '8 g g l II voar acciaans i j 3 i p. 5 I , g '. l Il dadiation DossI I l.a . to , , g i t i .i t i n.I t r.v iron =sa s : l , l I d.s.ls t l None I il I i , ,g4fyn g j, p, ao i lest anj A,,4,,,8, I I tor e 4.m: I's- l a . Au . Il i i9q,q9
, ,,,,,,s,.,, 1 1
i i
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1I l ** / 8ad' S ' I g i I l I g 1 I N1 2 la<ms: f ** l a. Aasa - g 3 i t51 J.j . lono l'u-2 Il I I s a i i 18 ' s i l ! i s g l N/A l 4)fhs as I N/A i N/A I j I- fs0*4* 11 3 N/A I ' I g i ! l lawust Llovation: (-IJI'6" 1I Sutumsr.jonc o I g l I 1 I Fl.sd tovel: I l l 1,%ve F itm>J t ovesi ; Yes II 1 m2t.ss: 4 g reste i 11 __ semsen
- 8. Isme lowest elevetion and titm2J luvol tharument at t.sn H f.srences: thu t , 1/ tt/u's. f e,ardsen t tims wor st c ase f or f ths location ut 11, Sor vito t uvir.m..wst Ilms o<lulpeesnt 1.11. 4 35. II toJ.
Ot &t. De ani n.3 te s. 91u5-f-500/19, H.s v. IOtlO/4,ttsv. C, .s .s t .s.1 / /18 8 . a. Hos.smasnt Os.nll e scat ion H. spor t Ms. I, .f.sf.s.1 // 5/UI .
/. M s. I Oakites, V. i t .
5 H.as.m. msn t Os.sillic at s.sss ILee se t l*s ..f ile ( e ss .ip.sf si s.us f.a# 4, f ees st a s. ale.ul ti lan 0S 70-051-015, si.svi I.us / s... I S S *,ar less it Is ens.all t.n , I'.s g.s t .es i Ks S. *dtil - es.fi al U. D 1.m ell n 3
- t uit y Mses64, 10//4/W8 e
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. . . .i. e
QUAlIFICAll0N I % dAl WOft( 5t(ET s
*E Y M Nv 8' 8' * - M Me'a-
< Public Service C%eny of Nee Hampshi ru SeabrotA Statlasi i Out ste HI QUAL If ICAI 144 F IL E M). 22S-03-01 nj hj p.g.,
' Occbet: 50-445 Cheched eg ,,,,,,c _,# ,
3 F won,,e,gn,3s --_ ,,,,, uur svew s og i 11 t'ostulated a nwironment a yeve,*nce I Methad i Items i I value wetesence verse ,
, g i f qul;-t Desc r Ipt Ion iI rarameter i I g 3 g y i% i Nase Drder No. : II I I Year i 3 l Test and Operating i I Year i I g g,,,,,,, g g i C763-006-22S-03 ll Tien i I p, I g g g g g l ll l I l 3 g g g i fquipment ID Notst.: il l l l g IA8+-t Y -3 7A, 31El l , , ,
i ll i I y y 3 y ,3, g go,, g i Pht4 T-3SA, 3S8, 36A, il l l l 40g i i Peak l ISO I p. 63 I l i M ll Teeperature I i p. 5 l l l I i F Mt4 T-5 44 2-1, 2 ll i i i l l I AH4 V-S443-1, 2 11 ("F l I l l l l I l I I ~lj 18 I I I I I 2 l Test i None 8 II l 3.0 I I i 63 1
- p. 62 l l l Peak l l
, I il Pressure 1 I p. 3 1 t i l i Equipment Type: ll l l I I Psig) l I I l 528enold Valve ll I I I il i I 3 i I I I I i 100 1 2 i Test I time l i 11 Helat l we I i i I p. A28 I I l Manuf ac turer : A5G) 18 p. 3 I l l l il Ibeldity l 800 l I I p. 22, 23 I I i 151 I I I I il I I 8 I I a 8 i I l Model mober: 18 e 2 i Test i None la a i l N/A I 3000 ppe Boron i l i i u w a52nA384v N/A p. A20 I il Cimalcal l I I as floric Acid I p . 22, 2 3 l l , I il Spray lpH) i I pH = 10.S I 1 I I i ll l 1 I I 3 8 I g l I l Accuracy:5pec: WA Il 3 3 3 I 3 I l 18 ou Tear 14ormel 1 6 3 g i i None i I Demon: N/A I p, 3 2 i Test il Radiat ica Dose 1i 4.2 m 10 I I2m 10) 1 I I I l g gg gp g gy 3 I I I P
- M* I i 18 : Tear accident i 6 g p, 5 I 1 l L les t Ing I nvi ronment : ll Redistlon Dose i i3.6 m 10 I I 18 (Had st 4 Test and Neo I 248/9.56 I i i i 104/40 l i l l Analysis l re dg. -la i Agirg i p. 5 i fl20*Cl I 8
18 l'F / Tear si l Note 1 g ! I Cad 2(me: Cont a inment l I sc losure Bldg. ICL - il ll 3 1 Non* Il I I N/A I N/A I i N/A l I tomest tlevarlon: gu -o- II l 5 l
!! Sdmergence i N/A I ,
i i F lood tow 1: (-121 *-6* l I l l 1 l Anow. Ffood Letel: Note Yes 2 II il I I Notes: 1
- 3. Thermal life account s for host r ise la n<weall, Documentation
References:
energised walve. Valve doenerge ses to per to,e Chart , New. i i. , 2/22/8S. saf ety f urct ion during accident condis sons. Service f ewisonment O. Hwort on Quellfication of
- 1. uf&C 03. No. 97634-300219, A0H-67568. ibv. 2. Since no ilanding occur s in 0 -l (Ref 31, fr.
- 2. IP-618m-05, A50) Test fASCO)
Haport No. Catalog se-I Solenold valves for Saf ety-Helated Applications in elevation for tim P AH has been listed. f lood The solenoid valwes Iccated in tria pas (pan s s Automat ic Seitc h Co.Nuc lear Poser 0$10-032-038, Nov.Generatirny O. St ations. Man's 2,1982. Impell Calculat ion No. 125-05-05, Cinck I l st ible 4 SSA & PAHf Y-36Al are last alled at elevation
- 3. The remainder of tiils equipment is Seabrcme Station Equipment Qualitication F ile No.
Natrim. 40'-0".
- 4. Stat ion f looding Study located i n Q - 1.
S. Stil-96265, Seabro(A O O k.-
' M Prop ared By : Lj4 p.g. : .f[g Pte lic Service Company of New Hampshire 5eatircan 5tatIm i QuilM NI Qu& IIICAI1(N F11E NO. 225-03 08 Chec6ed By f, [ bMg g).g.: gg~
Doc het : So-443 i f" (
"WEWL 2 i M mc en on i M p aw ng 4 --e i -t-d i items i y rue u.,,,,-- - - -
l f oulp--t Descript im li rareenter
, ne,ma,e m., .o. .
i 5 l T.sg g g% II Op ating i i rea' l I l I Year ! A#alysIs i I M 3 6 -225-03 O' ! I I I g g I I i Equipment 10 Notsl.: ll I g g l I 3 I I F AH4 Y-S4448, A II I 3 i ang y g g ,,, I il Peak I Iso l I l g 1 il l I l p. 63 1 g
- I Temperature i p. 5 i i i g l ll 1 *F ) i I i l I il , g I I i 1 I ,
il i : I i 2 1 Test l None 1 11 i I l 63 1 i Pee I Sil9 htly I p. 62 I I i, i ll i I g Pressu re i Positius p. 3 i l I i i tquipment Iype: ll EPstgl I i i I i
- Solenold Walve ll l I s i I a i I
! I il : s 2 I Iest i None i II I I l 800 1
- p. A2s i 1 1 11 Relat t wo I 3s I i l l I Nanuf acturer: A50) Hueldsty i 100 t p.
I I p. 22, 23 I i i 11 i I i i 1
'l ll til i i I I I I I l Model Nuoa.or: il I I 2 i Iest i None 4 1I I l 3000 ppe floren 1 l l I Wts320A 1841 N/A i N/A p. A20 l ll Cheetcal I l l as Boric Acid I p. 22, 23 I i t I Spr ay spHI l j l pH = 10.S I l l i
ll i I Il I I I I I 'l l l I I I l i Accur acy :'s,ec : WA Il 3 3 I Demon : N/A il au Tear normal I 3 I p. 3 1 1 y I y.sg g sc,, g l il Radlet lon Dose il 8m 80 I I2m 108 1 l l 1 I IRad s) I P. 59-62 l i i 18 I i 1 I Il Tear Accident i 8 I p. 3 1 1 I l ~l i il Radiation Dose 12m 80 l 3 I l l t iet t ing i nvi ronment : ikad s) i Note 2 l ~ ' I I l Ncme 1 I ll i I I l 4 I Iest and l l I l 248/S.29 I Analysis l I t or at ion : F uel Storage il Agi ng i 804/40 l Il20*Cl l l l I nullding (F58-SI II I i P. 3 i l i Red lone: Fuel Storage il ( *f / Year si l l Note i I I I _l I I I Cullding (F58-SI 18 I I I { l ll 1 I O ! I 4 I None Il I l i WA N/A g l I WA ll N/A l S l Looest [ Ie vat ion : N/A 11 Sutmergen:o I I $ I I I ._ I
! I F lood towel: WA N/A ll I
i i l Abow f lood Lowl: Il I Notes: g l. Thereal lif e account s f or heat e Ise la normally ,,e D(r ument at ion Ref erences: 1 7. , 7/22/ tis. energised valve. Valve dueneryl res to pe, s c ond r e t ons, No. 97634 -300219, Seer vice I nwirooment Char t , Re v. Qualific at ion of saf ety f um: tion ansring ac(Ident
- 1. Ut &C Dw) .
I P-61820-Oi, ASCO Iest Report No. AQH-675ta, Rev. O, Hepor t unsaf et y-Helated Applications 2.in For conservatise its value spen s tled in Nov se tA50DI Cef alog W-1 Solenoid val ves for
- 2. of Heterecce 8 has been used.
Automatic 5 I tc h Co. Nuc teer Power Generating Stat tuns, Nort h 2, i982. c u l af l on No. OS 70-0 32 -036, No v. O. 2/*)-O bol, (hest b i lst Note 4.
- 3. lapel I at ion f quipment Qualif icat ion f lie No. /
- 4. Seder o< Seateria.h S t at s am J 3.m.di a) S t udy Mat t l= .
S. Suu-9t Os l.m / set / _,4
Qual 1818 AlIC3 i Vaii d if06E Sitii Prep ared ity : A jf f4 t, . ,: J/, ,,fg utalIc Serwlae % any of Ne= Ilampstil re Sesater(2 6 58atIevi tQuis H HI QuM ll I( Al lON i iti NO. 72S-03-02 Checked tsy: g b[f ga L, [ /duhff ,/ Dase:r ////s*(. ' 3.s. bet : SO-44s i vuali sic asi on i uut su andIas~ l 76sTuTaf.;l TEvTrWnaFnr~ i vues :i snd a nws rorment Al tod i Items I i Met erence l I a I Llue I Ref erenc e i value I I I i Iquipe.mt leew rlpelun il I"ar amete r I I I I I I $ l Iest and 1 i i II 4 I I year i Analy s is i None ll Operating l 8 yeas 1 I I I l 6%rt hase Or der No. : Time i I p. I i 1 1 I 9fb3-006-22S-03 il i I l l I l il I I i ~l I l 1 I I ll I I I l E qulgment ID Not sl . : I
~ ^ ~T I I !
18 I I N/A None .I Pat MA Pee 1 I 142 i S l 1 l i pat +-15-3tA ll i 14/ I p. 5 1 l i ll Temperature i i I .Il i I i I l ll 14) l 1 i I l i I ll i I i I I l I I I I I Nonen I I il
! I 4 I WA ll Ne p. 1 1 0.4 1 I I l Pr essu re i O.4 1 I I l E quipment Type: Il I I i I IPsist i i l l l timit 5.I ti h Il t i i i 8
ll s i I N/A l Hone g ll i 800 6 i
l p. 3 I Il i I 800 I I I ' l l l s i I I Isl I i
il l 3 g l l Modei Numter : 1I I I I l l Hone l l WA I ILA 170-38302 li WA I WA WA N/A ' l I^ ' Sp peo I l l -l, 8 I I , l y g g 18 I i Auut acy :5pec : WA Iest i None i Demon: N/A II 4U voar Normal i l P- 3 8 I p. 80-6 I I l ll Radiat ion Dose 1I 4.7 m 10 l 2.02 x 10 I p, 10-49 1 1 g IN*8 *I I g i il i 1 g pg g l l il I Tear Accident I g g I I l p. 3 I p. 10-$6 1 g il Radiat ion Dose iI 1.9 m IO I , I L lai t ing i nvi rtaneent : I I i 18 IRaa d 3 l lest and i II I I 8 l 1
$ l Analy sis ! None 1 i Iccction: Prim. Auu. A 9 1ra; 1 l p. l 104/18.17 1 g
g g i ltul l d i ng, IP8-123 ll l*f/Yearsi l 104/40 l i l 1 l Red lone: Prim. Aum . Il I g i l I II i I l Building, IPB-Ill I g g i l l II I I g i i WA l Nme 1 II I yg l WA i l i 40'0" 18 I y g i l I l L owest f levat ion: I WA g l *I ll Sutmergem e l l i F ic:>d le vel: 1- 4 2 8 'e= Ves lI I g g i Abown Iloud towsl: Notas: I sc.ument at ton Ref erences - Itiar* , N w. I7, dated 4/22/85. 9763-f -500219, %r vl(e i nwle orne nt807, lie wi sion 0, I ewi ronment and Selsmical I. Ut AC De a.ltm; No. No. QIN
- 2. I P-tal87H-04, Hammo Cont rols Repor t cated 1/ /S /tsS. (lau b list , Note I,
- 1. Ul ac Calc ulat ion Set No. 6.01.oti, Quelli fration f ile #124-01-0/, A sses sment kiisi, Nte 2.
$*derose I quipment ( tun k l ist , Note 7.
4 S.
- at.rame I gulpment QualiIlt at lesi#11S-01-07, i ile #/?S-OS-07, A ssets venwitAwas.m. ne 8 tes Iruvi s t.c /
ipment Qual tl ic al f are i lle I . .e O I
- b. Se diten & t AC 3 et for i lamut Sf u ly Mal a l a .
- 7. SitH-H,/r.
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QUAL if ICAllON L ON NORK SHEET Prepared Sys
@(p , 6 ,ea . fyM a Ilk N Public Ser v. gang of Nee Hampshiro v Seabruuk St at ion 225-03-03 Checked Sys a L' ,L Dates al/gf A r-Dochst: 50-443 (QulH(NT QuALIF ICAllON FILE 80.
Ulaallvies Lawironnesef I guellv icev uon i UWTsimmsing i 1 I II rostulated Environennt i i Method l
- liens i i Meyerence 3 Talus I Neverence l iquipment DescrIpt ton li rarameter I relue
, , g g 3 i i 1%rchase order no. i l Test and I idone I 1
Operating i i Veer i i I I year i 4 i I 9 h h 223-03 il l i l l Analysla 1 i 11 Iles l p. I g g g l l l l l i Equipment ID hist.: ll l l l l i Emt-25-2SA, 2S8 11 i l , , i g l E#i-25-37A, 3 168 Ii a 3 i Test i None ! I I I 372 1 i PAH-15-3 Sis il Peak i ISO l p. 10 14 l l l i 11 Teaperature I l p. 3 1 l 1 I PMi-25-368 i I 2 1 3 1 l 1 # Alt-25-8 3A. 13tt il (*F ) I l 1 i il l I i I I I I 3 i il I i 100 3 i Test i None Peak 8 4.0 i i 1
- p. 10-14 l l l I il Pressure l p. 3 I I l l I E quipment types ll 1 l l l (Palg) l l I I I I Llelt $= Itch ll I I I i 18 I a i i I I s i Test i None i i is 1 400 1 3 l l Relative i 100 1 1
- p. 10-14 I 1 Manstacturer: ll i I p. 3 1 1 i i i I C:anco Controls if Humidity I I i l l
- 83) I l l I I ll l l I 7 i temsei Nunt,or : Il I I 8 I I i Iest i None 1 1 LA-180-38302 ll WA I WA l Boric Acid i 3 l l
[ A-180- 32302 ll Chemical I 8 Sod. Ihlosulfatal p. 10-9 l 1 Spray (PHI l l I l i I l I LA-180-33302 ll I I & Em3 i l l l 31 I l i pH = 10-81 l i i Accur acy :5pec: WA 18 i i i 8 i ll 4u year suormal I I I I I i l Demon: WA 6 l p, 3 1 1 i Test i None I
- I ll Radiation Dose i 4. 7 m 10 l l 2.04 m 108 1 3 I I i l 18 IRads) l I I I I P. lH & I I l l ll i veer accisont i 3 app. A l i 6 g p, 3 4 l l I I Lletting Environment
- il Radiation Dose 1 3.6 m 10 l I I I il IRads) i I I l
1 I I : 3 i Test and i None l Location: Cont. Encio, il i 104/40 l i l 104/20.6 1 8 Analysis I l Area ICE-il 18 Aging I l Fig. 8, i I l (*F/ Tear si l I l p. 4-12 i l 1 Red Zone: Cont . E nc io. II l I I l Area BCL-il ll l 3 l I i 1 I I i i i 18 ) l ,1 I . i I Ene 1 j l I I WA I WA 18 I - l g l l Lo.est E levation: WA Submergence I WA I S g g g g 3 f loud Level: WA Il l I g g l l g i Above f lood Level s WA Isotes: i l lu x_--t at ion Re f erences : Service Environment Chart, Rev. 47, dated 7/22/85
- 1. Ut &C Drawing No. 9763-f-300289ut &C Letter MtLL8/a(L8 f amperature vs. Ilas Analysis", dated 8/19/85.
2 20-95078, L A-ll10 3 Nemo lest Raport too. QTRIOS, Rev. 4 (PAPCO Job iS44SI, Namco Model dated 1/9/84. (Migd. from 2/808 Llatt Switch f avironmental Quelllication Rgort, , 4 lapell Calculat ion No. OS 70-032-024, hv. O. Page i of I S. MdJ-96163, LA &C L et ter, "F looding Study Matt im*. l uoriat
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QUAa IFICAllON EVALUAllON tf0fE SHLEI /) ' Detes 1//t/fy Prepared sy, f,' M ,f Put>Ilc Ser.ite Company of New Hampsinfre Seaaw ouk St ellun EQuitteLMI QUALifICAll0N FILE NO. 225-05-01 chedied sy y [ d .,, oste Yo.d s Dr.gh:t : $0-443 a gemi s vicar iasi a um . . . *'s i rusTUTnY4a anvironmenT s vess i v ies enw n - . Bless i si value l Nefer w a l hthod l value Iteter w a I l E quipment Descr iption ll raremeter l e 1 a e a a s t ne s._ us --. sum. . operettag I l g i I l l None l i 11 I i I Year I 3 An.slysis l 11 Igen i I Year I I l I l 1 I I P- 1 i l i I (quipment to Nots).: 11 1 1 I I I I I ll I I I I I EPA- FY- 313 I I ! 4 8 l Il I I 'l rest Hone ; EPA-FY-,j4 Il Peak 25o ,, , ; ; I l g ll ll w~. l l io' l 1 i P. 4 l 1 s l I s I I i s 1 i ll g l Slightly l 1 l Slightly l 6 Test None kt,alpeentType: Pro sure i P. 4 l l l s (Psigt l Positive 1 -l Posit ive l l Solenoid Valve Il i i I I l n i l uone i ' i 6 rest 5 a-'- '-- : " "t';",;* ino j e, l ioo l l l l ASco Il m I l l 1 l l i ma. - jl l l l l 8 l l l I HPtil21ASV gg cm ,,gc g g O O b 5 pray (pH 1 N/A I, p, 4 g l l 1 I l A.4 w .cy: Spec: N/A ll l 3 I l l l ) 13 go Year w aal 1 3 , l ommun. N/A i X la l l I ll hdlation Dose il i 18 4 I g x l04 5 N/A l None ll (Radsl l g i, , ..., m i i I l l l i i ... a.(Radsliu mse ii N/A ; I I ,,si,,,,,t.., _ ,2 I P- 4 ll l l 3 Analysis None l l 8 l l ltocasion: EFWBuildingll q , ,9 I p. 4 l 1o4/8.57 l l EFW-1 ll *t /vear sl l I l l a u fone: U I l l i i _l g e 8 Il I , N/A N/A Hone l I l i to est tie.ation: 41'-O"l1 2 N/A i, 5"I'mer 9ence I N/A i Flood t o.el: il/A II l 1 l l
; m.. . .- ..ei y , ll mt. .
r_ t . , , o., . . _., Service Esivlsonment 4:h.st t , Hev. 17, 7/22/85
- 1. IlE6C D . swing 9163-F-3DO219,t o YAEC on Flood ing St udy H.st s f x.
- 2. Sitti 'At:263,llE6C 1.etter Clic< k I i s t I, Notc 3.
E .1} . F1!c No. 225-05-01, Asser.sment
- l. S e.it. .. O, H.s e r ie 7, 3 9H .' . 2.0 t, l na >le I ynl/aS. S-i .
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f I Properw sy '8 ffg p jf, p n.,e, e j c/,,,,g Public 5.r vice %eny of Moe Hempshire g A, m j z 5***r e 58a'lua LQUlFNLNI QUALIFICAll0N Flti peo. 225-05-iJi wwy tkx.he f : S0-44)
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II ' l ll 8 I I l l l N/A 1 NPB121ASV ll Cheelcel i g I N/A N/A N/A I i 3 I I l ll sprey spas N/A I P- 3 I l i ' i il I I l II i i l l l Acuracy: Spec: N/A i I I l l N/A n gg .o voa,r g.al. son -,pose i I x 10 3 I 3 I 4 5 l N/A l None l g i I P. I x 10 l 11 (Radst i a i I l l II : voar accionar i I l l t iet ting tavaronment: Radiat se g 3 l l l l l I l l Hone l I tocation: FS Building 11 Il A91 a9 I l I 104/8.54 j 3 l Analysis l l l t f /vearsi i 104/40 l p, 3 l Had lune: FSB-5 ! I 3 -
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- I tamu ne.tsun u.sw ances
- Service Environment Clia s t , N ev . 17, 7/22/85.
3 1.7WM7 raw'IT,g 97ET F-300219,YAEC on Flun. ling Study H.st s lx .
- 1. SBil-96/61 IIE&C l. cater to I, Note 3.
ok E.Q. File No. 225-05-01, Assesa. ment Cliec kl i st
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Quat IF ICAllON EVALUA14000 tK51K SHEEI Prepared Sy:[/M ',Yd6Defes //. *//j, Publ8c Ser.lce CMany of New Hampstilre 7 Mt,_ /jg Seabrouk Stallon Checked av A .r" A .,, ceter tuoimEnt guatlFICAll0N FILE NO. 225-05-03 p
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l Modsi Number. 8I II ' g g l NP832tASE ,, l I N/A Hone I I N/A N/A I sprar SpH3 i N/A I I O l i il i i P. 3 i i I I g 18 i i l hur acy: Spec a N/A gg I l l l l I o.aon: N/A il 40 Year Normai I I g l 4 l ll Radiation Dose 1 4.7 x 106 i 3 1 2.0 x 10 8 l l Test l Hone l 11 ERadst i P-3 p. 4-4 i I 1 IITToar acciaenT i j l l l 1
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- 1. IlF6C Osawing 91f,3-F-300219, 2.
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- l. ImpsIl 8' a l cial .s t ton No. O's/O-032-I31.A,HCV- 1919-No. Alls-f t l.1H/TH , Hev. Ho.isi..
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i Af r r het: So-441
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I H ;,4 fone: il I ___ 8 g l,63n, l I wo-l l s i 8 g uf4 l n/a g si I gj3 I 4F'-O" Il l N/A l 3 l g g i i l Lowest Elevation:1-828'-6" Sut==.rgence i i i -- 1 F lood towel: 11 I I g Ves il I I g l Anove flood Level: 18 Notes: i nas the llelging l. fuel Sturage Hullding if $ti *)) uocumentation Heterances: t , llow. I I, // Jl/d*) . toeperature ast.1 the Pr leary Ausilar y uulldinj los L lef t Sel lstates, ItU-II) has the llaiting pressure envirusemens. Q &C Or awing No. 910H-)OOll9, Ser vite k nviramweent Chas 1. 2. Nam.o Hopor t fas. QIN SOS, Qualllicat to.i of L A-idu *.ur Hev. 4, 1/9/d4. N.mo W.I.sl L A-idd L imi t Swl tches 3. 08 &C Calculation No. 9 761-5-f Q-00-lOl-f , Huv. O, Ot o 's. Hod e g l.n / Anety5is,'I/19/d4. Bon iV File //4-4-01, As se , .ansnt Chus a 4 4 ,1, f* nJ s I .et i 4 S. Seatar umk Satu *Melb
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I I l ll spray spHI 1 P't to S I 4 l 18 l l I I I $ i l l 8 3 8 3 l Au uracy:'4 ac; N/A ll i s I I i l g I D=un . h/A il 40 Tear brual I 6 g p, 3 I # I 2 i Test i None a I 18 Hadiation Dose 1 4.7 = 80 I I2m 10 1 I I 8 I ll an.d s) l 8 3 I I P 39 8 I I I i 11 i rear accident i 6 I p. 3 8 I I I I I t i.ll en., l awlson nt il Hadiation Dose i 3.6 m 80 l i mads) i i 8 3 8 il I 8 l Mone ! I I I I I Test and I Ltaetson; k ntalament iI l 1 248/9.56 l Analysis I l Ag e sig i 104/40 i 1 (120*Cl I $ I I I tislosuse, (C1 -l a ll ( *l / Te ar si l i p. 3 I I I Had lone: (.ont ainment il I I NO'e i I I I
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- l. l l I Ar,o= aluimstewel: WA l l l 69..
5- ._ t.tlun f.eler _ e,: Si Ihermal li f e account s f or Imat r iso i n Ses vite i avironment Cliar t, Hewislun 8 7, dated F/22/83. normally energised valve. Valve on-onergises 9 7t,3 300119, to periore saf ety f unction char ing accident 8 ut&L D=9. No. ASt.O ltegior t N. AQH-t,75tAl, Nov. O, l<egnos t un Quallf l(ation of ASCO J. I l*-t.i tslecu ), (onditions.
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