ML20028H223

From kanterella
Jump to navigation Jump to search
Notice of Consideration of Issuance of Amends to Licenses DPR-33,DPR-52 & DPR-68 & Proposed NSHC Determination & Opportunity for Hearing
ML20028H223
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 11/09/1990
From: Ross T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20028H224 List:
References
NUDOCS 9011190095
Download: ML20028H223 (9)


Text

.

T l

  • b i:

7590-01 i

UNITED STATES NUCLEAR RFCULATCRY COMMISSION

)

TENNESSE,E, y,A,LLE,Y, [,l'Tfp,RJ,Ty -

)

98.Cf,E,T, p,0,S,.,,5,0,,2,5,9,,, 50-260, A,ND 50-296 tiOT I CE,0f,,C,0p,S I,DEp,A,TJ 0!I, Of, J,SS,U,A!!,C,E, Of..,AFEl'pf,EF,T, T,0 f

TACILITY CPEPATIt'C LICEllSE AND PROPOSED t'C SIGN!f1 CANT HAZARDS d

CONS I DE RATI,0N, p,EJ,ERMJpAJJ 0F, ffp, pffppJU,NJ Jy, f 01 f EfpJ p0 q

si The U.S. Nuclear Regulatory Comission (the Comission) is considering 1

7 issuance of. an amendrent to facility Operating Licerse Nos~. DPR-33, DPR-52, and 1

DPR-68. issued to the Tennessee Valley Authority (TVA) (the licensee) for

]

. operation cf' the B' owns Ferry Nuclear Plant, Units 1, 2, and 3 located in r

y

. l.imestone County Alabama.

The. proposed amendu.ent would ' revise Technical Specifications (TS) as a.o J:

follows:-(1) clarify equipment crerebility requirements for. Table 3.2.B'and.

j s

c

  • ^
Liniiting Conditic'ns for Operation (LCO) 3.5.B.11,: 3.5.E.1, 3.5.F.1, 3.5.G.1,.

j

' 3. 6. D. 1 ', And the Bases lSection of 3.6'.0/4.6.D, when the reactor is ;in the'. cold.

~

lI shutdownfcondition,'(2). correct the maxirum operating ' power ' level, allowed by i

w, 6

,T3ble-3.2,B for aniinoperable Recirculation' Pump ~ Trip (PPTh system (.s),rfrom h

.85. percent to 20 percent: power, and (3) correct twoitypographical errors in; Table 3.2iB. This amendment wa's originally proposed by TVAtin.a letter

[date'dMay"18,1990, which!waspublishedintheFederalRegister(FR)onJune.27-1

', ' !!990[(55FR 2'6295) as. a proposed no significant ha:ards consideration-(NSHC)'..

U gp The licensee has since superseded, by letter dated October 30f, ~1990, their

{I.

ioriginal amendment application. TVA's new amendment application only x.

changes thei revised LCO requirements of TS section.3.6,0,as specified in TS q'

5

~, '

1 3

1 w

w d

9011190095 % h f9,

[

Y W PD4 ADOCK pg-o p

i-

~

s

_ u._ __

i.

revision (1),identifiedabove. Consequently, the Comission is publishing another FR notice of propcsed NSHC. Although, in this case, the Commission's prict proposed deta mination of NSPC hos not changed, as documented belew, the Certrission is cor. strained by its rule to re-assess and renntice its prior determination of PSHC in the FP.

Before issuance of the proposed license amendrent, the Cona.ission will have made findings required by the Atomic Energy Act of 195a, as amended (the Act) and the Comission's regulations.

The Comission has made a proposed determination that the request for amendment involves-no significant hazards consideration.

Under the Commission's regulations in 10 CFR 50.92, this means that operatier: cf the f acility in accordarce with the propcsed amendment would not involvt t significant increase.in the probability or consequences of an accident pre-vicusly evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.

In the October 30, 1990 letter, the licensee prov.ided the folicwing revised analysis of their rodified TS changes, as required by 10 CFR 50.92:

1.

The pro >osed (TS amendment =does; not involve a significant increase in the prc:abilit or consequences of an, accident previously evaluated.

'[TS revision-(y), identified above,) clarifies equipment operability 1

requirerents with the reactor in the cold shutdown condition. With-the reactor in the cold' shutdown condition, primary system energy _i:

~

minimal and the control. reds are inserted.

Reactor pressure-is normally atmospheric except during performance of inservice hydrostatic tests, inservice leakage tests, and Integrated L.eak Rate Tests m

(ILRT). This charge would inhibit the drywel high pressure instruments which function to detect primary system leaks. With minimal system energy-and no steam generation, this function is not required. The High Pressure Coolant Injectic.n (HPCI) and Reactor o

Core Isolation Cooling-(RCIC) systems are not required because there is no steam supply to operate them and Residual Heat Removal (RHR) and Core Spray-(CS) are operable and capable of providing rakeup in a

m

-umumum-

~. -

nq

..c.

i.

3 h;

I case of leaks to protect the fuel from being uncovered. The Automatic Depressurization Syster (ADS) is not required for leaks considered possibit-during the inservice hydrostatic test.

Reactor pressure would decrease fast enough to allow residual heat removal and core

. spray injection in tire to preclude water level decreasing to an

-unsafe level. The relief velves are not required to be operable because alternate reans of overpressuri:ation protection are provided in the tests. During inservice hydrostatic testing, 11 of the 13 relief valves are disabled by removing the pilot cartridges and blanking the pilot ports.

Overpressure 3rotection is provided by the two remainino-relief valves which-have tacir sett.oint established in m,

ceccrdance with ASME Section XI. The RHR crosstic is not required b(c6use there is no high energy potential to breach the torus in the cold shutdown condition.

The change is consistent with industry

(

_ practice and the GE BWR-Standard TSs (HUREG 0123).

[TS revision (2), identified above,] is a more conservative requirement.

The RPT system provides an automatic. trip of both recirculation pumps after atturbine trip or a generator load reject. This reduction in

flow increases the-core voids and provides immediate negative reactivity to reduce the severity of the transient. There are two RPT. systems.

If. both RPT systems are inoperable or if one RPT system _

is inoperable for moreLthan 72-bours, reactor power shall be less than'30. percent within four hours (vs. the current 85 percent). The c'.

proposed value.of 30 percent power 1s-consistent with the BFN RPT analysis and the BFN Updated Final Safety Analysis Report. Therefore, this change' involves no significant increase in the probability or consequences of an4ccident previously analyzed.

.[TS revision-(3), identified above] is an administrative change that lcorrects typographical errors.

2.

The-proposed [TS amendment] dces not create the possibility of a new or different kind'of accident from an accident previously evaluated.

[TS revision.(1), identified above~,] does notEinvolve changes in _

h plant hardware or method of operation from that currently. practiced.

< The changes ~ are clar',Tications to TSs. to f acilitate performance of.

required TS testing <with,the reactor in the cold' shutdown condition.-

The nathods of' performance are consistent with industry practice.

[TS revision (2), identified above,] will-cnsure that when both RFT systems are~ inoperable or when one RPT system-is inoperable more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,. reactor power-is' dropped to a level consistent with the 7

analysis' performed for~the RPT installation.

R

-[TS revision (3), identified above,) corrects two typographical errors so the TSs-will be more consistent.-

3.

The proposed:[TS amendment' does]'not involve.a significant reduction in the margin; of safety.

[TSrevision'(1),identifiedabove,) clarifies equipment operability requirements with the reactor in the cold shutdown condition.

Sufficient safety equipment is still available s

i h?

Y, BanBHEEDabErEEEP -

, m i...

4

.z i

to ensure the fuel remains covered, even in the event of leaks.

It does not reduce the equipment available to mitigate an accident and as such does not reduce the margin of safety.

~

[TS revision (2), identified above,) is more conservative than the current TS. Vhen the RPT system is inoperable the maximum allowed reactor power will be reduced.

This is consistent with the analysis performed for the RPT installetion and the FSAR and does not reduce the margin of safety.

.[TS revision (3), identified above,] is an administrative change which does not reduce the. margin of safety.

The staP has reviewed the licensee's no significant hazards considera-tion determination and agrees with the licen:ee's analysis,.Therefore, based on the above considerat' -

'he staff has made a proposed determination that the amendment request involves no significant hazards consideration.

The Comission is seeking public coments on this proposed determination..

N

. Any' corrents received.within. 30 days af ter the date of publication of this i

notice will be considered in making.any. final determination. The Corrission will not normally make a final determinatien unless it receives a request for 6

-hearing.

L Written coments may be submitted'by mail to the Regulatory Publications -

p ye

Branch,' Division'of freedom of' Infornation and Publications, Services, Office of wx l.

l Administration, U' S. Nuclear Regulatory Comission,. Washington',;D.C. t 20555, 2Q; ind should cite the publication'date and page number of this FEDERAL REGISTER notice. Written consnents,may also be delivered to Room r-223,- Phillips-s

Building, 7920- Norfolk Avenue, Bethesda, taryland, from,7:30 a.m. ; to 4:15 p.m.

M^

Cop'ies 'of written comunents received may be examined >at the NRC Public Document

[

. Room,Jthe G'elman Building, 2120 L Street, N.W., Washington, D.C.

The filingtofJ m

requests;for hearing and petitions for leave to intervene.is discussed below.

m l

w e

~

4 f

vg 4

i T

e :

By December 14, 1990, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene.

Request for a hearing >and petitions for leave to intervene shall be filed in accordance with the Connission's " Rules of i

Practice for Domestic Licensing Proceedings" in 10 CFR Part ?.

Interested a

persons should consult a current copy of 10 CFR 2.714 which is available at the I

Commission's Public Document Room, the Gelman Building, 2120 L Street, N.W.,

Washington, D.C.- 20555 and at the Local Public Document Room located at the Athens Public Library, South Street, Athens, Alabama.

If a request for a hearing or petition for leave to intervere is filed by the above date, the

. Commission or an Atomic Safety and Licensing Board, designated by the Commis-

- sion or by, the Chairman of the Atomic < fety and Licensing Board Panel, will m

rule on the request and/cr petition and the Secretary or the designated Atomic j,

. Safety and Licensing Board will issue a notice of hearing or an appropriate order.

~

As required by 10 CFR 12.714, a petition for leave to intervene shall set

"us l.

forth with particularity the interest of the pe' tio'tr in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be fj permitted with particular reference to the follcwing' factors:

(1) the nature u

- of the petitioner's right under the Act'to be made party tc the proceeding; I

15 t

h'

Lf' m

2

e t

e 6-(2) the, nature and extent of the petitioner's property, financial, or. other.

interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the preteeding as to which petitioner wishes to intervene. Any person who has filed a petition E

for leave to intervene or who has been admitted as a party may amerd the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.

Not later than fif teen'(15) days prior to the first prehearing conference

[

- scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must. include a list of-the contentions which are i

sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or' fact to be raised or controverted.

.In addition, the petitioner shall provide a brief explanation of the bases of

' the c)ntention and a concise statunent of the alleged facts or. expert opinion-which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner rust also provide references to'those specific sources and documents of which the petitioner is aware'and on which the petitioner intends to rely to establish those facts or-expert opinion. Petitioner must provide sufficient information to show that a i genuine dispute exists with the applicant on a material issue of law or fact.

Contentions shall be limited to matters within the-scope'of the amendment

+

j!

.i,

+, '

.;.t

7-under consideration. The contention must be one which, if prouan, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will-not be permitted to participate as a party.

Those perritttd to intervene beccme parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the-opportunity to participate fully in the ccnduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.

If a hearing is requested, the Commission will v.6ke a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held, if the final determination is that the request for accrdment involves no sist.'#icant hazards considcration, the Conmission may issue the amendment and make it affective, notwithstanding the request for a hearing. Any hearing-held would take place after issuance of the amenA snt.

If a final determination is that the arendrent involves a significant hb ards consideration, any bearing held.would take place before the issuance of ary arendment.

Normally, the Commission will not issue the amendment until the expiration of the 30-day notice period.

However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amei:dvent before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State ccmments received. Should the Cormission take this action, it will 4

\\

.l 1

,g, p,.

f publish a notice of issuance and provide for opportunity for a hearing after issuance. The Comission expects that the need to take this action will occur

' very inf requently.

H A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, Attention:

Docketing and Services Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building,

[

F 2120 L Street, N.W., Wasb%gton, D.C., by the above date.

Where petitions are filed during the last ten (10) days of the notice period, it is requestsd thet i

the petitioner promptly so inform the Comission by a toll-free telephone call to Western Union at 1-(800) 325-6000 (in Missouri 1-(800)342-6700).'The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Frederick J. Hebdon, (petitioner's name and telephone number)-(date petition was mailed), (plant nare),-and publication -

date and page runter of this FEDERAL REGISTER r.otice). A copy of the petition should also be sent to the Office of'the General Counsel, U.S. Nuclear Regula-L; tory Commission, Washington,. 0.C. 20555, and to General Counsel, Tennessee l-A Valley Authority, 400. West Sumit Hill Drive, Ell B33, Knoxville, Tennessee g

237902, attorney for the. licensee.-

~

Nontimely filings of petitions for leave to intervene, amended petitions, L

supplemental petitions and/or requests for hearing will not be entertained i

'^

absent' a determinatica by the Consission, the presiding cfficer or the Atomic w

['

Safety and Licensing Board that the petition and/or request should be granted i

' based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v)

.and2.714(d).

x

/

'l i

f'%

.I

a 9

l i

d l

For further details with respect to this action, see the applications for erendment dated March 18, 1990 as superseded by October 30, 1990, which are l

I available for public inspection at the Comission's Public Document Room, the i

1 Gelman Building, 2120 L Street, P.W., Washington, D.C. 20555 and at the Local i

i Public Document Room located at the Athens Public Library, South Street, l

Athens, Alabama, j

i Dated at Rockville, Maryland, this 9th day of November 1990 i

FOR'THE NUCLEAR REGULATORY COMMISS10r I

l J

Thierry Poss, Project Manager L

Project Directorate 11-4 l-Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation 1

i i

.1 ),

If j

l 1

o i

1 l'

L L

L L

i N.

a