Text

Transcript of 810609 Meeting in Washington,Dc for Discussion & Possible Vote on Full Power OL for Facility.Pages 1-19. Draft Ltr to Util,License,Fr Notice & Viewgraphs Encl
	ML20005A214
Person / Time
Site:	Sequoyah
Issue date:	06/09/1981
From:	; NRC COMMISSION (OCM)
To:	;
References
	REF-10CFR9.7 NUDOCS 8106300050
	Download: ML20005A214 (45)
	v • d • e

.

]

t_

I I((

(l ((IkII(((f(f

(

II (k

(

( lk ( l (ihi II

((

w. b TRANSMITTAL TO:

Q Document Control Desk, 6

~~N 016 Phillips CB

_b M

' ADVANCED COPY TO:

C The Public Document Room p

c]=

DATE:

.Tm n in ign p

oN Attached are the PDR copies of a Commission meeting d

transcript /s/ and related meeting dccument/s/.

They 9

are being forwarded for entry on the Daily Accession p

M List and placement in the Public Docunent Room.

No g-other distribution is requested or required.

.xisting c

DCS identification numbers are listed on the individual b

h documents wherever possible.

=M e

c5 ciG g

1.

Transcript of:

Discussion and Possible Vote on Full-Power e

License for Sequoyah-2, June 9, 1991.

(1 copy) 6 6,_

Y a.

Letter to Mr.

H.G.

Parris, Manager of Power, TVA frca M

M Darrell Eisenhut, Division of Licensing, NRR, undated, g

Docket No. 50-323.

(1 copy) p

~4 2

~M b.

Handout entitled:

Sequoyah Unit No.

2, License

=-

2 Revisions.

(1 copy) r n

C, ~.

~

/

, A ' p -~~~i

e g

Jake, crown F..

cs" Oft h of the Secretary fff',y.Q.y, cc

-r..,-

.-C cs

. N r.4 A 0..

- ".,',',,, ? :.%.;}

i

=@

f,,

.cck:*.;v,,~"e: s -

g a

n

$u u

c==

M=

' O: ' s..

x..

'm M

6

~0 F

=

i m

p 5

S S

W:

2 G=

c;=

2>-

=c cC

^

S c:c S=

=c TH'.S DOCUMENT CONTAINS

'g-N POOR Q4AUTY PAGES g

2 p

h.... m f?f?) $ dQ$ $ Y N @ffy?ff?ldI?ll?yyyy)'y)));yyyffyyyyyy)a.

21)))*)'yfff..

'y

(

IB10 6 30 0 0%

e i

i I

'll'G'.

3 'g%'2.g' ?f i..i-NCCLEAR P.IGC* ATOPZ COM!CSSICN

"' Of[ ',..'.

$5.f,/

(-

n t.

~~g o/.

S'4 COMMISSION MEETING l

Is *d:a Mat::ar cf:

DISCUSSICN AND POSSI3II VOTE ON FULL-PCWER LICEN9E FOR SEQUOYAH-2 PUBLIC MEETING

.=

D k..

OA*'r:

June 9, 1981 PAGIS:

1 - 19 AT:

Washincton, D.

C.

f s

ALJERSON PJOtWING f.

e 4C 0 7f _T -4.1 Ava.,

5.*4, Washi p==,

O.

C.

200:4 L

Tal.a=h==a : (202) 554-2245 l

, ~ _. -...,,. _ -,,,.,,., _,,,,,,.. -,..., -,,,...., -,,,,

i

'N 1

1 UNITED STATES OF A3 ERICA 2

NUCLEAR REGULATCRY COMMISSION 3-4 DISCUSSION AND POSSIBLE VOTE ON FULL-POWE3 5

LICENSE FOR SEQUOYAH-2 6

7 PUBLIC HEETING 8

3. -

9 3aclear Eegulate:7 Commissics to Room 1130 11 1717 H Street, N. *i.

12 Washington, D.C.

13 Tuesday, June 9, 1981 14 The Commission met, pursuant to notice, at 2:15 15 p.m.

16 BEFORE.

17 JOSEPH 3.

HENDRIE, Chairman of the Commission 18 VICTOR GILINSXT, Commissioner 19 JOHN F. AHEARNE, Commissioner 20 PETER A. 3RADFCED, Commissi.,ner 21 22

=

24 25 ACERSCN REPCRTING COMPANY..NC.

4C0 VIRGINIA A L $/N. WASHINGTCN. D.C. 20024 (2C2) $54-2345

_a

i

)

8 '

2 1 ALSO PRESENT:

2 SAMUEL J.

C.iILK, Secre ta ry L

3 LEO ELAGGE, General Counsel's Office 4

CABL STARLE 5

SOB PURPLE 6

HAROLD DENTON 7

DON ' QUICK 8

30GER 3.\\TTSON 9

20BERT DEFATETTE 10 11 12 13 14 15 16 17 -

18 19 20 21 22 23 4

.4 25 AL EPSCN AEPCRTING CCMPANY. INC.

4C0 VIRGINIA A7 $1N. WASHINGTCN. O.C. 20C24 (202) 554 2345 l-

i s

i l

- - :-. ~ s,

a--

t

'.s Ls as t=:cdfd " = ' =a=s--dy: ci a. =ne" ? ! -la C=d.:ad 5:x:as 3" '==- 24g=.5.a:::f C-

' si = ha.Li := - June'9"lT9al

. -dA C- ' *si=n's o " as a: 17' 7 T. !=ae, 3. ~J., "J4s%- _=,

d U. C.

tha- =ne:i=;g :3.s 7== = pe t ' - 4::=-d--- a=d ci:sa_..:1:=.

D '""""***"**. *:s.S =27. DeEl=r 237f 25 Fed, CM-2d,.== 4di*3d, L:: :ny m *- =

a-,

"a =xr*~ = L1 L:~a=iad, sal.a!.7 ! : grus:1.' " = i..: = n " ~ = '

purgesas.

.n.s,..-. ind. by 10 CZZ. 9.102, f.: L

_== pa=

ei a

l

!===x~ ::- *

A :sc::-L L '"~~ <t~ ci -la :1::1:= <c:ssed.

zz;r:ssa" --- :t :pa-a - L, as,

.<~: f

_:: sanss2_-..T

niLac: i'-=

La

.~, s :: y. f a ',.

3a ps. as g :: :-.-

8 page: =a7 be. =4 21:2= -le C-

' si:=.i= %f pr:csad1=; as

' =

ss~.~.L: ci : add:xssed =

w, s 1:s=an: :: 1.,-

-,' - u_

hared-_, t=:2== 1s

i".e P-

' e ed - :, =g 7 g -" --"* *2.

i F

l O

O

\\

e G

e i

1 i

e 8

s D

.----..,.--a,,

l

< s 3

l 1

2 PR0CEEDINGSs 3

CH AIRMAN HENDRIE:

If we can come to order.

The Commission meets this af ternoon for discussion and, I hope, 4

5 a vote on the operating license for Sequoyah Unit 2.

We met 6 last week and got this subject started.

7 Why don't I start out by asking the staff if ther 8 have anything to tell us in addition to wha t they have 9 already said last week and if so, to please tell us and then 10 let us turn to questions about license language or whr.tever 11 other subjects may interest Commissioners.

12 MR. DENTON:

Mr. Chairman, in connection with the 13 budget I had an opportunity to look back at the Sequoyah 14 exercise and have some numbers that might be of interest.

15 We spent 17 aan years of reviewer time on l

16 Sequoyah-1 and 2 and had over a hundred individuals involved 17 in th e review; three national labs; ten other consultants, 18 and we had a total of 13 seetings vita the ACES or its 19 subcommittees.

20 COMMISSIONER GILINSK!:

This is the operating 21 license?

l l

22 ER. DF'.'!ON:

For Sequoyah-1 and 2.

l t

l 23 COMfISSIONER G 1INSKI And is tha t just the 24 safety review?

25 ER. DINTON:

Ies.

What we have done Today is ACEASCN AFPCRT:NG 00MP Ah !..NC.

400 VIRGINIA AVE. 3/N, W ASHINGToN. D.C. 200:4 (202) 554-2345

i 6

l l' circulate a few pages that spell out changes we would propose to maXe in the license for Sequoyah-2.

These 2

3 changes reflect the guidance from the last meeting we had 4 with you, calls from some of your staff.

They are attempts 5 to clarify those areas which were no t clear last time.

6 There are a few areas v2 have extended - three or four areas 7 - the dates to the first refueling.

8 I do not think there has been any change of 9 substance from the license that we proposed the last time, 10 but these revisions do attempt to clarify those issues which 11 were troublesome previously, and we are prepared to discuss 12 any of these that are of special interest.

13 CHAIRMAN HEND3IE:

Consents, questions?

14 COMMISSIONE3 AHEARNE:

Well, I guess I would like 15 rou to briefly review these changes you mad e.

16

33. DENTON:

Why don't I have the project sanager 17 d o that.

18

53. STAHLE:

If you turn to the copy that I passed 19 out to you.

What I have done is iden tif y those revisions to 20 the license that you were reviewing last week, the items 21 identified as (16)E.

??

This is in addition to the words that are in your 23 license.

We also identified here the fact that the need for 24 having an individual assigned from Unit 1, with prior 25 ex;erience in the icy power test progras, shocid be ALOERSCN REPCRUNG COMPANY. iNC.

400 vtRGIN!A AVE., S!N., WASHING 7CN. D.C. 20C24 (202) 554-2345

s 5

1 completed at some convenient tise.

2 So, we have added this requirement that in essense 3 says, we will expect a report from TVA and our findings sust 4 agree that there is an acceptable level of ex;erience and 5 training, so that this ites does not go on indefinitely as a 6 hardship to th e TV A.

t 7

.The second item identified as (16)I here is a 8 clarification.

9' The next three items, (16)N, O and P, simply add 10 the dates that were omitted in the last license, consistent 11 with the NU3EG 0737.

12 The next items, (16)E and 5, provide more 13 clarification than ve had before, as well as hopefully clear 14 up the confusion.

15 COMMISSIONER AHEARNE:

On (16)R, then, you are 16 firm that unlike what the SC3 says, it can meet the 82 days.

17

33. STAH1Es Yes, sir.

18 COMMISSIONIH AHEARNE:

The SCH is not quite right 19 in tha t statement.

2C MR. STAHlE:

That's right.

The SCR had some

~

21 confusion.

The paragra.ch that you refer to was really TVA's 22 position - certainly not ours - and we tried to indicate 22 that, but not quite clearly.

24 MR. DENTON:

I think it is f air to say, T7A would 25 like relaxation in a number of areas that they think are too r.

ALCERSCN REPcRTING COMP ANY. INC.

400 VIRGINIA AVE., S.W WASHINGTCN. 3.C. 20024 dC2) 554-2345

s 6

1 strenuous.

We,- in our rethinking of the problem, remembered 2 that 0737 was a relsxation of 0660 as a result of our 3 zeeting with AIF.

If we do not keep some of these dates 4 f airly firm, we vill not ever get them in.

5 It may be that, as the dates come due, we may have 6 to provide a temporary relaxation or some compensating 7 seans.

I would propose to deal with those few examples if 8 they happen to occur.

9 COMMISSIGNER AHEARNE:

Fine.

10 CHAIRMAN HENDHII:

When you say under " Upgrade 11 emergency support f acilitie s" tha t we vill comply with the 12 quidance of 696, I thought we agreed to consider the TVA 13 emergency support facilities.

They were outlined in their 14 plan, and whenever they came up here ve had a briefing about 15 it.

I thought we agreed to accept that with the provision 16 tha t they give us a plug-in trailer some placs c1cse te the 17 site.

18

53. DENTON:

I think that is what the Commission 19 did decide.

let me ask Mr. Van Niel what the specific 20 intent of this requirement was.

21 NH. DEFAYETTE:

I am not 31 chard. Van Niel, I am 22 Robert Defayette from the Emergency Preparedness Civision.

23 On March 19th this year we sent a letter to TVA 24 with that position.

We said, "We agree with the ;csition 25 that you sent in before, hcVeve r, he re are some ALOERSCN REPCRT.NG 00MPANY,.NC, 400 VIRGINIA AVE., S/# WASHINGTCN. 3.C. 20024 (2001554-2345

7 1 conditions."

We listed the conditions, some of which are 2 trailers.

3 To bring you up to date on that, we received a 4 response from IVA yesterday, proposing their eventual 5 concept, and we really have not had a chance to look st it 6 yet.

7 COREISSIONER AHEARNEs I think Chairman Hendrie's 8 point is that what you can read this (16)R(3) as indicating',

9 that what ycu told TVA - which wo uld track with what the to Commission decided - is no longer the case.

Instead, T7A 11 sust comply with 0696.

12 BR. DEFAYETTEs I think th e wording on the pa per 13 you are reading th e re is a little bit misleading, I agree on 14 that.

We actually have granted some relief to the strict 15 criteria of 696; ve have granted their concept.

16 MR. DENTONs Well, perhaps we oucht to sharpen 17 that by going back to this letter, to be sure it reflects 18 the decision.

19 CHAIRHAN HENDRIEs Yes.

20 COREISSIONER AHEARNEs It probably ought to.

21 CHAIRHAN HENDRIE If this is the language which 22 would go into the license, then I just ask that ycu think 23 whether it il fact is wha t you sean.

24 COMMISSIONER AHEARNE:

We could say, "As medified 25 by the letter of" - whatever the date was "that you sent 1

ALOERSCN REPCATING COMP ANY :NC.

400 VIRGINIA AVE., S/N WASMNGICN. 0.C. 20C24 (202) 55 A-2345 l

i i

8 i

1 the letter."

2 CHAIRMAN HENDRIE:

If that is the appropriate 3 thing to say.

4 ER. STAHLE:

On Item (a) we simply added the word 5 " interim" emergency support facilities.

The "S"

is 6 clarification.

7 Turning to page 3 of your handout, this is simply 8 a clarification of the understanding of what would be 9 included, but not necessarily limited to what vould be in 10 the RCD program.

11 C053ISETONE3 AHEARNE:

Just asking a question.

12 under Number (1) when you say and " Improved calculational 13 sethed," what do you have in sind?

14 MH. DENTON:

There was that classic code which the 15 first time around did not include heat sinks.

Ihat is one 16 of the areas that we have been pushing to improve.

17 COMMISSIONER AHEARNE:

I see Hoger getting ready 18 to stand.

19

53. MATTSON:

Hell, the revised caJculational take 20 account for heat sinks and local temperature distributions 21 inside the containment rather than a conservative bulk 22 temperature for which one : hen calculates local temperatures.

23 CCHMISSIONE3 AHEA3NE:

But you hacie An :ind using 24 an improved version of classics.

25

33. MAITSCN:

Yes.

I believe that is due to be l

Al. ERSCN REPCRT;NG COMPANY,:NC.

4CO VIRGINIA AVE.,3.W., WASHINGTCN. C.C. 7C024 (202) 554 2345

9 1 submitted within a relatively short time.

We are fairly up 2 to date on what they are doing and how it changes the 3 temperature, staying abreast of that, as we have told you on 4 a couple occasions, with regard to the interim rule.

5 CO!!ISSICNE3 AHEARNE:

Thank you.

8 MR. STAH1E.

The next item, vents, previously the 7 July date of

'82.

TVA propose prior to startup after first 8 refueling.

This is within the same time f rame.

I think 9 this is quite acceptable and we vill make that. change.

10 With regards to the non-THI items identified, the 11 first one on masonry valls is new to the license.

This is 12 to reflect the fact that the acceptability of masonry walls 13 was done on the basis of interim staff criteria, and 14 modifications may be necessary based on our final staff

~5 c ri te ria.

1 16 The next item on instrumentation and controls.

17 Simply, we had a date of 18 months.

We have converted over, 18 based on TV A 's request here, prior to startup af ter first 19 refueling; again within the same tine frame as we had before.

20 Fire protection.

On the ceiling panels we had i

l 21 prior to acceding five percent of power.

TVA's request 22 indicated because of procurement in s talla ti r n, September 1 23 is probably within a month or so of what would be the j

24 anticipated date that they would reach the five-percent i

25 power level.

Cn that basis, that date of September is quite I

l ALOERSCN AEPoRTING OCMP ANY,,NC.

400 VIRGINIA AVE, S/N., WASHINGTCN. D.C. 20024 (202) 554 2345

1 i

10 1 acceptable to us.

2 M3. PURPLE:

While ve are on fire protection, not 3 highlighted on this handout, but it is included in the 4 revised license that was handed out on page 6.

There are 5 some word changes there to accomodate, I believe, comments 6 since the last meeting.

7 The first ites where it says, "TVA shall maintain 8 in effect and fully implement all provisions," the " maintain 9 in effect" is new from what was there last week.

10 COMMISSIONIH 3RADFORD:

But it is the same as 11 McGuire?

12 MR. PURPLE:

I can't answer that.

13 MB. STABLE "

Yes, it is.

14 MR. DENTON:

But we would propese to add (3)L.

15

32. PURPLE:

On Item "D" we would add Item (3)L 16 from the discussions this morning.

It is not on the copy of 17 the license you have.

18 ER. STAHLE:

That comple tes the list cf the 19 revisions that we have made at this point.

20 COMMISSIONER AREARNE:

Again just a clarification 21 question.

What is added by saying " maintain in effect" over 22 " fully isplemen ted ?"

23 MR. DENTON:

I have to turn to the autact of that, 24 if he is here.

25 COMMISSIONER AHEARNE:

Auther, auther?

AL.OERSCN AEPCRTING COMPANY..NC.

400 VIRGINIA AVE. $.W. WASHINGICN. 3.C. 20024 (2023 554 2345

11 1

It was not' a significant quest?.on.

2 COMMISSIONER READFORD:

If I were advising IVA on 3 what the change meant, I think I would say that probably 4 while " fully implement" might cover it, " maintain in effect" 5 says not only will you do it at one point in time, but you 6 vill also keep it that wa y.

7 COHHISSIONER AHEARNE:

I would think " implement" 8 means that.

It is a trivial question.

9 CHAIRHAN HINDRIE:

Dear Mr. Parris:

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNIT 2 - ISSUANCE OF FACILITY CPERATING LICENSE The Nuclear Regulatory Commission has issued the enclosed Facility Operating License No. CPR-79 to the Ter.nessee Valley Authority for tne Sequoyah Nuclear Plant, Jnit 2, lccated in Hamilton County, Tennessee. License No. OPR-79 authori:es operation of the Sequoyah Nuclear Plant, Unit 2, at 100 percent power (3411 megawatts thermal) upon completion of certain related construction items.

Also enclosed is a copy of Supolement No. 5 to the Safety Evaluation Recort, together with a related Federal Register notice which has been forwarded to the Office of the Federal Register for publication.

Two signed originals of Amendment No. 7 to Indemnity Agreement No. B-82 which covers the activities authorized under License No. CPR-79 are also enclosed.

Please sign and return one copy to this office.

Sincerely, Darrell G. Eisenhut, Director Division of Licensing l

Office of Nuclear Reactor Regulation

Enclosures:

1.

Facility Operating License No. OPR-79 2.

Federal Register Notice 3.

SER iupplemen: 5 l

4

'rendment 7 to Indemnity Agreement 3-82 cc w/ enclosures:

See next page 1

t r

,_.,~

Tennessee Valley Authority ccs:

He reer: 5. Sanger, Jr. Esc.

Mr. Bruce Blanchard General Counsel Enytronmental Projects Review Ten,1essee Valley Authority Department of the Intertor 400 Commerce Avenue Room 4256 E 113 33 18th and C Street, N. W.

Knoxville, Tennessee 37902 Washington, 3. C. 20240 Mr. E. G. Seasley Defense Maccing Agency Tennessee Valley a thori:f Aerospace Center a

W10C'11 C St. Louis Air Force Station 400 uommerce Avenue Missouri 53118 Kr.oxville, Tennessee 379C2 Federal Inergy Regulatory Ccmmission Mr. wicnael Harcing 325 North "acital Street, N, E.

Westingncuse Electric Corpora:i:n Wasningt:n, ?. C. 2C425 P. O. Sox 355 Dittsburgh, Dennsyl vania 15230 Chairman Tennessee Pu:lic Ser/ ice Ocamission Mr. David Lamber:

Ci-102 Ccecell Hull Suilding Tennessee Valley Au:nce::/

Nasnville, Tennessee 37219 400 Chestnut stree: Tower II Cha::ancega, Tennessee 3740!

Mr. J. F. Ccx Tennessee Valle'enue,nority v Aut Direct:r 4C0 Ccemerce Av W10C131C Cf fice of Ur:an 1. ders' af # airs Knoxville, Tennessee 37902 e

108 Partway Towers 404 Jarnes.iobertson Way Residen: Inspect:r/Secuoyah NPS Nasnville, Tennessee 37219 c/o U. S. Nuclear Regulatory C0mmission P. O. Sox 699 The Hencratie Ocn Mccre, Jr.

Hixson, Tennessee 3T343 County Judge Hamil:en County Courthouse Chattancoga, Tennessee 37201 U.S. Environmental Protection agency ATTN : EIS Coordinatur Region IV Office 345 Ccur:1and St., N. E.

Atlants, Georgia 30308 At:ceney General Sucreme Cour Building Nasnviiie. Tenressee 37219 U.S. Environmental Protection Agency A :n: Ms. F. Munter Office of Federal Activities Rcce W-535. Waterside Mall 201

5:ree, S. W.

Wasningt:n, 3. C. 2C460

dr

&i O

o $ A)

//p A%

S'

%y'v+ $'

ll&s%

~

.. E E-,-

TEST T ARGET (MT-3) e

_l.0

% a LM

!! g EE 11 ' E m Om u

= =E I.25 1.4 1.6

=-

v 9

b 4{f,f?,f

(.qh

't

%.#c) 9#

/

A RQ<>

%,;$q, TEST TARGET (MT-3) l.0 lllm E4

- y ll IE i.i l'c Ea

! '~

_g I.25 1.4 1.6 m-a 4

gn

/

)

S+4%

M $' 9 '

4,,, f Q,f 4 4

~

L.

m

/,O

+$* 'q?t#

/

TEST TARGET (MT-3)

I l.0 l9 EM EM

$ l55 f! EIE l

NS l-l

.q m

i 1.8 1.25 1.4 l 1.6 i

6" "O

h

4 4$ 4%

4f,,///f 43,Q,(4

'N g>

e

.. W

p n aee,,'o o

u UNITED STATES

+

8 %

3.

j NUCLEAR REGULATORY COMMISSION j

.pp /' j c

WASWNGTON. D. C. 20555 tg v*j TENNESSEE VALLEY AUTHORITY 00CKET NO. 50-328 SECUOYAH NUCLEAR PLANT, UNIT 2 FACILITY CPERATING LICENSE License No. OPR-79 1.

Th'e Nuclear Regulatory Commission (the Commission) having fcund that:

A.

The application for licenses filed by the Tennessee Valley Authority complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly madei' B.

Construction of the Sequoyah Nuclear Plant, Unit 2 (the facility),

has been substantially comoleted in conformity with Provisional Construction Permit No. CPPR-73 and the app;ication, as amended, the provisions of the Act, and tne regulations of the Commission; C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; D.

There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without eedangering the health tnd safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission set forth in 10 CFR Chapter I; E.

The Tennessee Valley Authority is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.

The Tennessee Valley Authority has satisfied the acclicaole provisiens of 10 CFR 33r: 140, " Financial Protection Requirements and Indemnity Agreements", of the Connission's regulations; G.

The issuance of this license will not be inimical to the common defense and security cr to the health an d safety of the puolic; a

.h_

. H.

After weighing the environmental, econcmic, technical, and otner benefits of the facility against environmental and other costs and considering available aiternatives, the issuance of Faulity Operating License No. DPR-79, subject to the conditions fr.-

protection of the environment set forth herein, is in accordance with 10 CFR Part 50, Appendix D*, of the Comission's regulations and all applicable requirements have been satisfied; and i.

I.

The receipt, possession, and use of source, byproduct, and special nuclear material as authorized-by this license will be in accordance with the Ccmit,fon's regulations in 10 CFR Parts 30, 40,and 70.

2.

Pursuant to approval by the Nuclear Regulatory Commission at a meeting on June 9,1981, Facility Operating License No. OPR-79 is hereby issued to the Tennessee Valley Authority to read as follows:

A.

This license applies to tne Sequoyah Nuclear Plant, Unit 2, a pressurized water nuclear reactor and associated equipment (tne facility), owned by the Tennessee Valley Authority. The facility is located in Hamilton County, Tennessee, about 9.5 miles northeast of Chattancoga, and is described in TVA's Final Safety Analysis Report as supplemented and amencec, and the Final Environmental Statement prepared by the Tennessee Valley Authority.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses tne Tennessee Valley Autnerity:

(1) Pursuant to Section 10a(b) of tne Act and 10 CFR Part 50,

" Licensing of Procuction and Utilization Facf'ities", to possess, use, and operate the facility at the designated location in Hamilton County, Tennessee, in accordance with the precedures and limitations set forth in tnis license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with tne limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, scurce and special nuclear material as sealed neutron sources for reactor startuo, sealed scurces for reactor instrumentation and radiation monitoring ecuipment calibration, ind as fission ce:ectors in amounts as required; "See 10 CFR S 51.56

a 4_

d.

Failure to complete any tests included in the described procram (planned or scheduled for power levels up to the authorized

. power.l evel ).

(4) Monitoring Settlement Markers (Section 2.6.3)

TVA shall continue the monitoring of settlement markers along the ERCW conduit for the new ERCW intake structure for a period not less than three years from the date of this license. Any settlement greater than 0.5 inches that occurs during this period will be evaluated by TVA and a report on this matter will be rabmitted to the NRC.

(5) Design of Seismic Category Structures (Section 3.8)

Prior to startuo following the first refueling, or as directed by the Ccenissicn, TVA shall evaluate all seismic Category I masenry walls to final staff criteria and implement required modifications that are indicated by that evaluation.

(6) Tornado Missiles (Section 3.5)

Prior to startup after the first refueling, TVA shall reconfirm to the satisfaction of the NRC that adequate tornado protection is provided for tne 450 V transformer ventilation systems.

(7) Low Temperature Cveraressure brotection (Section 5.2.2)

Prior to startup after the first refueling, TVA shall install an overpressure mitigation system which meets NRC requirements.

(3) Steam Generator Inspection (Section 5.3.1)

Prior to start-up after the first refueling, TVA must install inspection ports in each steam generator or have an acceptable alternative for inspection.

(9) Negative Pressure in the Auxiliary Building Secondary Containment inclosure (AB5CE) (section 6.2.3)

After the final ABSCE configuration is determined, TVA must demonstrate to the satisfaction of the NRC that a negative pressure of 0.25 inches of water gauge can be maintained in the scent fuel storage area and in tne ESF pump rocm.

(10) Containment Isolation Systems (Section 6.2.A)

Pricr to startuo after the first refueling, TVA shall modify to the satisfaction of tne NRC the one-inch chemical feed lines to the main and auxiliary feedwater lines for canoliance with GDC 57.

i l

r i

3 (4) Pursuant to 'the Act and 10 'CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physica1' form, for s'mple analysis or instrument calibration i

or associated with radioactive apparatus or components; and (S). Pursuant to the Act and 10 CFR parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I-and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Connission low or hereaf ter in effect; and is subject to the additional conditions specified or incorporated below:

)

(1) Maximum power Level The Tennessee Valley Authority is authori:ed to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal. Fuel loaaing and operation of the facility is subject to compliance with construction items listed in.

(2) Tecnnical ' Soeci fications The Technical Specifications contained in Appendices A and 3 attached hereto are hereby incorporated in this license. The Tennessee Valley Authority snali operate -the facility in accordance with the Technical Specifications.

(3)

Initial Test Program The Tennessee Valley Autnority snall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this progr,3m unless modifications have been identified and have received prior NRC approval. Major modificat'ons are defined as:

a.

Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amenced as being essential; i

s.

Modification of test objecti' es, methods, or' acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as ceing essential; c.

Performance of any test at a ;cwer level different from j

nat cescricec in tne program; and D

5-(11) Environmental Qualificat'nn (Section 7.2.2)

(a) No later than June 30, 1982, TVA shall be in compliance with the requirements of NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," for safety-related equipment exposed to a harsh environment.

(b) Complete and auditable records must be available and maintained at a central location which describe the environmental qualifica-tion method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the 1

00R Guidelines or NUREG-0588. Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance by June 30, 1982.

(c) Within 90 days of receipt of the equipment qualification safety evaluation, the licensee shall either (i) provide missing documentation identified in Sections 3 and 4 of the ecuipment qualification safety evaluation which will demonstrata conpliance of the acclicable ecuicment with !!URF"-CSFS, or (ii) ccamit to corrective actions which will resul; in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30, 1982.

i l

(12) Recuirements For Modification To Or Addition Of Instrumentation Ana Controis (7.3.2)

(a) Prior to stgrtup after first refueling, TVA shall have installed instrument downscale failure alarms for the effluent monitoring instrumentation channels for radioactive gaseous and radioactive licuid effluents. Also, appropriate modifications to crocedures and Technical Specifications 3.3.3.9 and 3.3.3.10 shall have been completed.

(b) Prior to startup after the first refueling, T/A shall have installed, demonstrated operable, proposed appropriate Technical Specifications, and received NRC approval for an additional level of over/undervoltage protection acceptable to the NRC staff. The level of protection from the effects of power transients on safety-related equipment provided by Part I of the staff's " Degraded Grid Voltage Position",

or equivalent, is required.

(13) Diesel Generator Reliability (Section 8.3.1)

Prior to cperation following the first refueling, TVA shall implement the following design and procedure modifications as cutlined in Section 8.3.1 of SER Sucplement No. 2.

These include: I t) Moisture in Air Starting System; (b) Turb:cnarger Gear Orive Prcelem; and (c) Personnel Training.

._3

e 1 (14) Fire Protection System (Section 9.5) a.

TVA shall maintain in effect and fully implement all provisions of the approved fire protection plan and the NRC staff's Fire Protection Review in Supolements 1, 2 and 5 to the Sequoyah Safety Evaluation Report. By July 1981, TVA shall implement the following three items which deal with the ERCW supply: (a) enclose the necessary exposed conduit with a 1-1/2-hcur fire barrier; (b) reroute train B ERCW pump and transformer power cables to.obtain a minimum 20-foot separation from train A; and (c) enclose the ERCW junction box with a 1-1/2-hour. fire barrier.

b.

After initial criticality of Unit 2 and prior to the completion of item (a) above, TVA shall provide:

1) a continuous fire watch in the area of the EROW junction box on elevation 590.0 of the auxiliary building. '

2) a roving fire watch in the area of conduits which exit the top of the junction box, pass through floor elevation 714.0, and terminate on floor elevation 734.0.

c.

TVA shall replace the control rocm ceiling panels with acceptable panels by September 1,1981.

d.

By October 1,1981, TVA shall submit a report that identifies and justifies differences between existing or proposed fire protection features and these features specified in Se<.tions III.G, III.J, and III.0 of Appendix R to 10 CFR Part '

TVA shall implement any fire protection features found aoprocriate by the NRC on a schedule consistent with that recuired for other operating reactors.

(15) Mechanical and Hydraulic Snubbers Prior to exceeding 5 percent pcwer, TVA shall provide a listing of mechanical snubbers on safety-related systems. Functional

!esting of snubbers shall be carried out in accordance with the Technical Specifications.

(16) Comoliance with Regulatory Guide 1.97 Sy June 30, 1981, TVA shall submit a proposal including a schecule for ccmpliance with 3.G.1.97.

(17) NUREG-0737 Conditions (Section 22.2)

Each of tne following conditiens snali ce completed to the satisfaction of the NRC by the times indicated:

_s

' La.

Shift Technical Advisor (Section 22.2, I.A.l.1)

TVA shall continue to provide a fully-trained on-shift technical advisor.to the shift supervisor.

-b.-

Independent Safety Engineering Group (Section 22.2, I.B.l.2)

TVA shall continue to have an onsite Independent Safety Engineering Group.

c.

Procedures for Verifying Correct Performance of Operating Activities

( Section 22.2, I.C.6 )

' Procedures 'shall be available to verify the adequacy of the operating activities.

d.

Control Rocm Gesign (Section 22.2, I.D.1)

Prior to start-up after first refueling of Unit 1, TVA shall complete the detailed Control Room Design Review. As part of this review, TVA shall consider benefits of installing data recording and logging equipment in the control rocm to correct the deficiencies associatec with the trending of important paramet s s on strip chart recorders used in tne control.rocm. All correctr/e actions specified for Unit 1, shall be made on Unit 2.

e.

Training During Lcw-Power Testing (Saction 22.2, I.G.1)

Licensed operators shall complete simulator training for natural circulation conditions prior to exeeding 5 percent power level.

-One experienced operator trained on Unit 1 low power testing for natural circulaticn cperation snall be assigned to eacn shift prior to exceeding 5 percent power level. Requirement remains in effect until TVA submits a report and NRC agrees with findings that an acceptable level of trainir; and experience on Unit 2 has been attained.

f.

Reactor Coolant System Vents (Section 22.2, II.B.1)

By July 1,1982, TVA shall install reactor coolant system and reactor vessel head highpoint vents that are remotely operable from the control room.

g.

Post Accident Samoling (Section 22.2, II.B.3)

By January 1,1982, TVA shall ecmplete corrective actichs neecec to pr0 vide the capabili y to promptly cotain anc perform radioisotopic and chemical analyses of reactor coolant and containment atmosphere samples under degradec core conditions without excessive excosure.

l-

[

_e

[-

. h.

Hydrocen Control Measures (Section 22.2. II.B.7)

(1) For coeration of the facility beyond January 31,1982, the Commir,sion must confinn that an adecuate hydrogen control syste: for the plant is installed and will perform its intended

~

function in a manner that provides adequate safety margins.

(2) During the interim period of operation, T'.'A shall continue a research program on hydrogen control measures and the effects of hydrogen burns on safety functions and shall submit to the NRC quarterly reports on that research program.

(a') TVA shall amend its research program on hydrogen control measures to include, but not limiter to, the following items:

1) Improved calculat'Ional methods for containment temperature and ice condenser response to hydrogen combustion.

2) Research to address the potential for local detonation.

3) Confirmatory tests on selected equipment exposed to hydrogen burns.

4) New calculations to-predict differences between expected equipment temoerature environments and containment temperatures.

5) Evaluate and resolve any ancmalcus results occurring curing the course of its ongoing test program.

(b) The results of these investigations will be provided to the staff for review in June 1981. A schedule for confirmatory tests beyond this date will be provided consistent with the requirement to meet the Jaruary 31, 1982 deadline, Section (16)h.(1) of the license.

i. Relief and Safety Valve Test Recuirements (Section 22.2, II.D.1)

TVA is committed to conform to the results of the EPRI test program.

Occumentation for qualifying the reactor coolant system relief and safety valves under expected coerating conditions for design basis transient accidents is to be completed by Octob-- 1981. Documentaticn en piping and supports is required by Janua y 1982. Sicek valves are to be qualified by July 1982.

9

.g

j. Auxiliary Feedwater (Section 22.2, II.E.1.1)

Prior to exceeding rive percent power, auxiliary feedwater pump endurance tests will be completed and a report will be submitted to NRC within'30 days after all tests are completed.

k.

Con E j. ation Dependability (Section 22.2, II.E.4.2) 1.

Additional Accident Monitoring Instrumentation (Section 22.2 II.F.1)

By January 1,1982, T/A shall instali continuous indication in the control room of the following parameters:

(1) Containment radiation monitors.

(2) Neole gas effluent from each potential celease point.

m.

Instruments for Inadecuate Core Cocling (Section 22.2, II.F.2)

(1) T/A shall provide a reactor vessel water level instrumentation system by January 1,1982.

(2).T/A shall submit a proposal for uegrading the incere themoccuple systen in June 1981. T/A shall uegrade the incore thermocouple system by January 1,198c.

n.

Voiding in Reactor Coolant System (Section 22.2, II.K.2.17)

T/A is participating in the Weetinghouse owners group effort on tnis item and is committed to conform to the results of this effort. The analysis will be submitted by January 1,1982.

o.

Secuential Auriliary Feedwater Flow Analysis (Section 22.2, II.K.2.19)

T/A is participating in the Westinghouse owners group effort on tnis item anc is committed to conform to the results of this effort. The analysis will be submitted by July 1,1982.

p.

Calculations for Small-Greak LCCAs (Section 22.2, II.K.3.30 ano II.K.3.31 )

TVA is participating in the Westinghouse owners group effort for this item and is connitted to confor n to the results of this effort.

The analysis for redel justification will be submitted by January 1,1982.

T/A shall limit the purge valve openings to 50 degrees.

1

1 q.

Uograde Emergency Preparedness (Section 22.2, III.A.l.1)

TVA is required to have a prompt notification system installed and operational by July 1,1981.

r. - Uograde Emergency Succort Facilities (Section 22.2, III. A.l.2)

(1) In accordance with the implementation schedule which~the NRC will establish, TVA shall comply with the guidance of NUREG-0696,

" Functional Criteria for Emergency Response Facilities."

(2) NA will provide a conceptual design of the. emergency support facilities in June 1981.

(3) TVA shall have in operation the upgraded emergency support

~

facilities by Cctober 1,1982 that ccmply with the guidance of NUREG-0696.

(4) TVA shall maintain interim emergency support facilities (Technical Support Center, Operations Support Center and the Emergency Cperations Facility) until such time as the final facilities are complete.

s.

Long-Tern Emergeacy Precaredness (Section 22.2. III. A.2)

Additional implementation dates for tne meteorological program are:

(1) Prior to exceeding 5 percent power level of Unit 2, TVA will comit to providing for direct telephone access to the individual responsible for making off-site dose projections in the event of a radiological emergency.

(2) Functional description of upgraded capabilities shall be provided by January 1,1982.

Installation of hardware and software shall be completed by July 1,1982. Full cperational capability is required by October 1,1982.

t.

Primary Coolant Outside Containment (Section 22.2, 111.0.1.1)

Prior to exceeding 5 percent power level, TVA is required to submit the' leak test results of Unit 2.

O.

Etscotions fecm certain requirements of Accendices G, and J to 10 CFR Part 50 are cescribed in the Office of Nuclear Reactor Regulatien's Safety Evaluation Report, Supplements No.1 and No. 5.

These exemptions are authorized by law and will not endanger life or property or the comon defense and security and are otherwise in the public interest. Therefore, these exemptions ar.

o

indicates that such activity may result in a significant adverse environmental _ impact tnat was not evaluated, or that is significantly greater tnan that evaluated in the Final Environmental Statement prepared by tne Tennessee Valley Autnority and tne Environmental Impact Appraisal prepared by the Commission in May 1979, the Tennessee Valley Authority shall provide a written evaluation of such activities and ootain orior approval from the Director, Office of Nuclear Reactor Regulatic i.

H.

If TVA plans to remove or to make significant changes in the normal operation of equipment that. controls the amount of radioactivity in effluents from the Sequoyan Nuclear Plant, the Cennission shall De notified in writing regardless of whether the change affects tne amount of radioactivity in tne effluents.

I.

T/A shall report any violations of tne requirements contained in Sections 2.C(3) through 2.C.(16), 2.E, 2.F, 2.G, and 2H of this license ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telepnene and confirmed by telegram, nailgrim, or facsimile transmission to the Director of the Regional Office, or his designee, no latar than the first norking day following One violatien with a written followup report witnin la days.

J.

T/A snall 1:cediately notify the Commission of any accident at tnis f acility wnicn coula result in an unplannec release of quantities of fission procacts in excess of allowabia ifmits for normal Operati:n estaolisned oy the Ccmcission.

K.

TVA snall nave and maintain financial protection of sucn type and in sucn amounts as the Commission shall retuire in ac:Ordance with Section 170 of tne At mic Energy Act of 1954, as amencec, to cover public liability claims.

L.

This license is effective as of trie date of issuance and snall expire May 27, 2010.

FCR THE NbCLEAR REGULATCRY CCFNISSION narola R. Dent:n, Director

.'ffice of.uclear ieactor Regulaticn atta:- eat:

ta:-'ert i 2.

eaci:es A anc i Tecr.ai:al 5:ecifi:sti:ns

ata :# *ssaa :e:

~

ATTACHMENT 1 CONSTRUCTION RELATED ITEMS TO BE COMPLETED This attachment identifies certain ittms which must be completed to the satisfaction of the NRC Office of Inspection and Enforcement in accordance with the schedule listed below. Tennessee Valley Authority shall not proceed beyond the authorized events without prior written authorization frem the Office of Inspection and Enforcement.

Prior to Fuel Loading 1.

Complete a verification that preservice 'nspection data reveals no rejectable indications.

2.

Complete all applicable preoperational testing, including the integrated test of the Engineered Safety Features Systems. As of May 22,1981, three test procedures have not been started and twenty tests are in progress.

3.

Evaluate adequacy of the nydrostatic test performed on safety-related systems and satisfactorily resolve deficiencies. (INF, 80-21-01,80-z1-02).

4.

Determine that features not included in preoperational testing are appropriately tested.

(UNR, 80-23-11).

5.

Repair damaaed fire barrier for pressuri:er and steam generator instrun.entation ci rcuits.

[UNR, 81-14-04).

6.

Resolve construction deficiency NE3 8023, Baron Dilution.

(LII,81-02-07).

7.

Resolve construction deficiency NCR 2398, Faulty Fillet Welds. (LII, 31-02-18).

8.

Resolve construction deficiency SWP 8025, Fillet Weld Misspecification.

(LII, 81-02-29).

9.

Resolve construction deficiency NCR 2547, Reactor Vessel Field Welds.

(LII,81-20-06).

10. Fully implement security plan, in particular, consider the containment as a vital area and meet all requirements for alarming normally unoccupied vital areas.

(Ref.10 CFR f,73.55(d)(7), 573.55(d)(8), 573.55(e)(1)).

Prior to Initial Criticality 1.

Resolve construction deficiency EEB 8054, Failure of Generatcr to Supply Adequate Voltage to Safe.y-Related 3 cards. (LII, 31-02-37).

2.

Resolve construction deficiency NEB 8013, Limit Switch Actunor for Masoneilan Air-0perateo Valves. (LII, 81-20-05).

I

. 3.

Resolve construction deficiency NEB 8110, Blown Fuse Alann in Auxiliary Control Circuits.

(LII, 81-20-09) 4.

Resolve construction deficiency NE3 8122, Power Operated Relief -Valvv Operating Time. (LII, 81-20-19).

5.

Resolve construction deficiency NCR 28P, Inadequate Cladding Thickness on the 28-B Centrifugal Charging Pump Casing.

(LII, 81-02-21).

6.

Comolete applicable preoperational testing and resolve significant test deficiencies. As of May 22, 1981, seventeen test procedures have not been started and four tests are in progress.

7.

Resolve IE Bulletin 79-14, Need for Seismic Reanalysis of As-built Safety-related Piping Systems.

8.

Determine the repeatability of test W-6.2, UHI Precperational Test, and conduct testing as necessary. (UNR, 8r 23-08).

9.

Verify adequac/ of retest for adjusted Upper Head Injection ficw centrol valves and perforn further testing as necessary.

(UNR,80-23-09,80-23-10).

10. Determine adequac't of specificatiens to ensure off-line sampling is effective for fit.sning.

(UNR, 80-23-12).

11. Resolve construction deficiency CEB 79-19, Containment Piping Support Design Basis. (LII, 79-15-04).

12. Resolve construction deficiency CEB 79-36, Seismic Analysis of Uppet Head Injection Piping. (LII, 79-35-C6).

13. Resolve construction deficiency.vE3 79-4, High Flcw Alarm in Essential Raw Cooling Water Piping.

(LII, 79-07-10).

14. Resolve construction deficiency CEB 8005, Valve Operator Weight.

(LII, 80-09-04).

15. Resolve constructitn deficiency NCR 27P, SI Pump 3reaker Lockout.

( LII, 81 03 ).

16.

Resolve construction deficiency NES 8017, CSCS Centrifugal Charging Pumos.

(LI*, 31 06).

17. Resolve construction deficiency NES 8025, Safety Injection Train B Flew Deficiency. (LII, 91-02-11 ).

18. Resolve construction deficiency SWP 3023, Seismic Analysis for As-Built Safety-Relatec Piping Systems. (LII, 31-02-25).

i

o 19. Resolve construction deficiency CE3 8037,_8101, 01screpancies in As-built Versus As-analyzed Piping Locations. (LII, 81 26).

20. Resolve construction deficiency CEB 8039, Non-conservative Loads on Pipe Support Design Modifications. (LII, 81-02-33).

21. Resolve construction deficiency 1EB 8115, Possible Error in Safety Injection System Preoperational Test.

(LII, 81420-12).

22. Resolve construction deficiency SWP 8112, Spacial Separation for Conduit and Cable Trays. (LII,81-20-15).

23. Resolve construction deficiency EEB 8111, relating to service rating for 460 Volt Motors. ( L II, 81 21 ).

24.

Resolve construction deficiency EE3 8115, 8034, Oc; 'ded Voltage Requirements for 460 Volt Motors. (LII, 81 22, 81-02-17).

25. Resolve IE Sulletin 79-13, Cracking in Feedwater System Piping.

26. Resolve IE Bulletin 79-27, Loss of Ncn-class IE Instrumentation and Control Pcwer System Bus.

27. Resolve IE Eulletin 60-05, Engineered Safety Features Reset Controls.

28. Resolve construction deficiency NE3 3123, Containment Hydrogen Analyzer, (LII,A1-20-20).

29. Evallate correct inadequate circuit separation between the positive displacement charging pumps and charging pump A.

(UNR, 81 02).

30. Evaluate / correct the lack of a provision for fire detection over the Essential Raw Cooling Water pumos. (UNR, 81-14-03).

31. Resolve IE Bulletin 81-02, Failure of Gate Valves to Close Against Differentia. Pressure.

Prior to Reaching Full Power 1.

Resolve con ~struction deficiency NES 8035, Corrosion of Carbon Steel Piping.

(LII, 81-02-35).

2.

Resolve ca.'struction deficiency MES 3006 R1, Excessive Pressure D p Across Essential Raw Cooling Water Strainers. (LII, 31-20-07).

i O

[

1

v

-~

P UNITED STATES NUCLEAR REGULATORY COMMISSION 00CXET NO. 50-328 TENNESSEE VALLEY AUTHORITY NOTICE OF ISSUANCE OF FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Facility

- Operating License No. DPR-79, to Tennessee Valley Authority (If censee) which authorizes operation of the Sequoyah Nuclear Plant, Unit 2 (the facility), at reactor core power levels not in excess of 3411 megawatts thermal (1C0 percent power) in accordance with the provisions of the license and the Technical Specifications.

The Setuoyah Nuclear Plant, Unit 2, is a pressurized water nuclear rcictor located at the licensee's site in Hamilton County, Tennessee, about 9.5 miles northeast of Chattanooga. - The license is effective as of the date of issuance.

The application for the license complies witn the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Occmissien's regulations.

The Ocamission has made accropriate findings as required by the Act and tne Commission's reguletions in 10 CFR Chapter I, which are set forth in the license. Prior public notice of the overall action involving the proposed issuance of en cperating license was published in the FEDERAL REGISTER on March 25, 1974 (39 FR 11131).

The Commission has determined that the issuance of this license will not result in any environmental impacts other than : nose evaluated in tne Final Environmental Statement since the activity authorizec cy the license is encompassed by the overall a:ti:n evaluated 19 tra ri cal Envi ronmeata' Itate' eat.

4 t

w r-

.6 2-For further details with respect to this action, see (1) Facility Operating License No. OPR-79, complete with Technical. Specifications; (2) the reports of the Advisory Comittee on Reactor Safeguards dated December 11,1979, July 15, 1980, September 8,1980, and January 31, 1981; (3) the Comission's Safety Evaluation Report (NUREG-00ll) dated March 1979, Supplement No.1 dated February 1980, Suppletent No. 2 dated August,1980, Supplement 3 dated September 1980, Supplement 4 dated January 1981, and Supplement 5 dated June 1981; (4) the Final Safety Analysis Report and amendmants thereto; (5) the Final Environmental Statement prepared by Tennessee Valley Authority in July 1974; (6) the Ccm"if ssion's Environmental Impact Appraisal dated May 1979; (7) NRC Flood Plain Review of Sequcyah Nuclear Plant Site dated July 18, 1930; and (8) Discussion of the Environmental Effects of the Uranium Fuel Cycle dated September 3,1980.

These items are available for public inspection at the Ccmmissien's Public Occument Room,1717 H Street, N. W., Washington, D. C., and the Chattancoga Hamilton County Bicentennial Library,1001 Broad Street, Chattanooga, Tennessee 37402. A copy of Facility Operating License No. OPR-79 may be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attention:

Director, Division of Licensing. A copy of item (3) may be purchased at current rates from the National Technical Information Service, Department of Commerce, 5285 Port Royal Road, Soringfield, Virginia 22161, and through the NRC GPO sales program by writing to U.S. Nuclear Regulatory Comission, Attention: Sales Manager, Washington, D. C. 20555. GPO deposit account holders can call 301-492-9530.

Dated at Bethesda, Maryland, this day of June,1981.

i FOR THE NUCLEAR REGULATORY COMMISSICN Eliner Adensam, Acting Chief Licensing Bran:n No. 4

)

Division of Licensing o

1. 4;f.

DISTRIBUTION Docket File (50-328)

NRC PDR Local PDR LB-2 File-NRR Reading H. Denten/E. Case J. McGurren, CELD D. Eisenhut R. Purple.

~ R. Tedesco A.~Schwencer

'C.

Stahle M. Service H. Berkow/W. Russell IE C5)

A. Marshall, MPA G.

Deegan (4)

R. Diggs, ADM R. Mattson S. Hanauer B. Scharf-(10)

R. Vollmer D.

Ross B. Grimes W. Pasciak C.~ Miles, PA C. Gaskin, NMSS M. Virgilic L. Reidinger, IE-Chat tancoga bec:

NSIC TERA ASLBP ASLAB ACRS (16)

_..m_

j

SEQUOYAH UNIT NO. 2-LICENSE REVISIONS TMI ITEMS

. ITEM (16)E TRAINING DURING LOW-POWER TESTING ADD:

ONE EXPERIENCED OPERATOR TRAINED ON UNIT 1 LOW POWER TESTING FOR NATURAL CIRCULATION OPERATION SHALL BE ASSIGNED TO EACH SHIFT PRIOR TO EXCEEDING 5 PERCENT POWER LEVEL.

THIS REQUIREMENT REMAINS IN EFFECT UNTIL TVA SUBMITS A REPORT AND NRC AGREES WITH FINDINGS THAT AN ACCEPTABLE LEVEL OF TRAINING AND EXPERIENCE ON UNIT 2 HAS BEEN ATTAINED.

ITEM (16)t RELIEF AND SAFETY VALVE TEST REQUIREMENTS TVA IS COMMITTED TO CONFORM TO THE RESULTS OF THE EPRI TEST PROGRAM.

DOCUI'ENTATION FOR QUALIFYING THE REACTOR COOLANT SYSTEM RELIEF AND SAFETY VALVES UNDER EXPECTED OPERATING CONDITIONS FOR DESIGN BASIS TRANSIENTS AND ACCIDENTS IS TO BE COMPLETED BY OCT, 1981.

DOCUMENTATION ON PIPING AND SUPPORTS IS REQUESTED BY JANUARY 1982.

BLOCK VALVES ARE TO BE CUALIFIED BY JULY 1982.

ITEM (16)N VOIDING IN REACTOR COOLANT SYSTEM ADD:

ANALYSIS WILL BE SUBMITTED BY JANUARY 1, 1982.

ITEM (16)o SECUENTIAL AUXILIARY FEEDWATER FLOW ANALYSIS ADD:

ANALYSIS WILL BE SUBMITTED BY JULY 1, 1982, ITEM (16)P CALCULATIONS FOR SMALL-BREAK LOCAs ADD:

ANALYSIS' F06 MOCEL JUSTIFICATION WILL BE SUBMITTED BY JANUARY 1,1982.

ITEM (16)a UPGRADE EMERGENCY SUPPORT FACILITIES i

-(3) TVA SHALL HAVE IN OPERATICN THE UPGRADED EMERGENCY SUPPORT FACILITIES BY OCTOBER 1, 1982, THAT COMPLY WITH THE GUIDANCE OF NUREG-0696.

...==

-,,. ITEM (16)R UPGRADE EMERGENCY SUPPORT FACILITIES (CONTINUED)

(4) TVA SHALL MAINTAIN INTERIM EMERGENCY SUPPORT FACILITIES (TECHNICAL SUPPORT CENTER, OPERATIONS SUPPORT CENTET, AND EMERGENCY OPERATIONS FACILITY)

UNTIL SUCH TIME AS THE FINAL FACILITIES ARE COMPLETE.

ITEM (16)s LONG-TERM EMERGENCY PREPAREDNESS (1) PRIOR TO EXCEEDING 5 PERCENT POWER LEVEL OF UNIT 2, TVA WILL COMMIT TO PROVIDING FOR DIRECT TELE? HONE ACCESS TO THE INDIVIDUAL RESPONSIBLE FOR MAKING OFF-SITE DOSE. PROJECTIONS IN THE EVENT OF A RADIOLOGICAL EMERGENCY, (2) FUNCTIONAL DESCRIPTION OF UPGRADED CAPABILITIES SHALL BE PROVIDED BY JANUARY 1, 1982.

INSTALLATION OF HARDWARE AND SOFTWARE SHALL BE COMPLETED BY JULY 1,1982, ' FULL OPERATIONAL CAPABILITY IS REQUIRED BY OCTOBEh 1,1982, 0

e

- -, - =

o

s o.o i ITEM (16)s(2)(A)

-(A) TVA SHALL AMEND ITS RESEARCH PROGRAM ON HYDROGEN CONTROL.

MEASURES TO INCLUDE, BUT NOT LIMITED T0, THE FOLLOWING ITEMS:

1) IMPROVED CALCULATIONAL I'ETHOD FOR CONTAINMENT TEMPERATURE AND ICE CONDENSER RESPONSE TO HYDROGEN CONBUSTION.

2) RESEARCH TO ADDRESS THE POTENTIAL FOR LOCAL DETONATION.

3) CONFIRMATORY TESTS ON SELECTED EQUIPMENT EXPOSED TO HYDROGEN BURNS.

4) NEW CALCULATIONS TO PREDICT DIFFERENCES BETWEEN EXPECTED ECUIPMENT TEMPERATURE ENVIRONMENTS AND CONTAINMENT TEMPERATURES.

5) EVALUATE AND RESOLVE ANY ANOMALOUS RESULTS OCCURRING DURING THE COURSE OF ITS ONGOING TEST PROGRAM.

ITEM 2 C. (16)F REACTOR COOLANT SYSTEM VENTS IMPLEMENTATION DATE WILL BE CHANGED FROM JULY 1982 TO PRIOR TO STARTUP AFTER FIRST REFUELING l

0

9p.

O SEQUOYAH UNIT NO 2 LICENSE REVISIONS NON-TMI ITEMS DESIGN OF SEISMIC CATEGORY STRUCTURES (SECTION 3.8)

PRIOR TO STARTUP FOLLOWING THE FIRST REFUELING, OR AS DIRECTED BY THE COMMISSION, TVA SHALL EVALUATE ALL CATEGORY I MASONRY WALLS TO FINAL STAFF CRITERIA AND IMPLEMENT REQUIRED MODIFICATIONS THAT ARE INDICATED BY THAT EVALUATION (NEW ITEM)

ITEM 2.C.(11) INSTRUMENTATION AND CONTROLS (A). PRIOR TO STARTUP AFTER FIRST REFUELING, TVA SHALL HAVE INSTALLED INSTRUMENT DOWNSCALE FAILURE ALARMS FOR THE EFFLUENT MONITORING INSTRUMENTATION CRANNELS FOR RADI0 ACTIVE GASEGUS AND RADI0 ACTIVE LIQUID EFFLUENTS,

ITEM 2C.(13)FI.4EPROTECTIONSYSTEM (c)

TVA SHALL RE? LACE THE CONTROL ROOM CEILING PANELS WITH ACCEPTABLE PANELS BY SEPTEFBER 1, 1981

SCHEDULE CHANGES ACCEPTABLE-T0 STAFF (REFERENCE TVA LTR 06/08/81)

NOTE:

(1) APPENDIX H EXEMPTION NOT REQUIRED o

e e

ML20005A214

Contents

Text

2 p

Dear Mr. Parris:

SUBJECT:

Enclosures:

Navigation menu

ML20005A214

Text

2 p

Dear Mr. Parris:

SUBJECT:

Enclosures:

Navigation menu

Search