ML17301A147

Proposed Tech Specs Deleting License Conditions Completed to Satisfaction of NRC

ML17301A147
Person / Time
Site:	Saint Lucie
Issue date:	01/25/1985
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17301A146	List: ML17301A145 ML17301A147
References
NUDOCS 8502010516
Download: ML17301A147 (14)

Text

4 ~

4 Envi ental gualification of tlechanical an ui ment tion ica1 Age>>

Prior to startup first refueling outage but not later arch, 1985 the i

11 environtaentally go.

u all electrical equipment as required y

0.49.

5.

go.

Axia h (Section 4.2.3.1(

)

SSER 3)

Prior to startup following

'rst re ou ge, the licensees shall provide an analysis are modi ficati ons to assure that the shoul c earance between fuel d fuel assembly end s is adequate.

6.

Inser 's ection Pro ram for Class 1

2 and Section 5.2.

6 SER onents Within six (6) months e

this license, the licensees P~

~ ~

shall submit a

'd inservice inspection m for Class 1,

2 a

omponents for NRC approval.

7.

Natura culation Cooldown and Boron Mixin Test (Se

.4.3, 8.

Prior to completin'g the rtu~ tMt program, the licensees shall either a) provide a repo a

San Onofre Unit 2 test justifying that the test dat

'pplicable to ie 2 assuring adequate boron mixin d

ing natural circulation cool o

b) perform the test to onstrate adequate boron mixing during natura

'lation co wn.

Conti s Containment Pur e

S stem (Section 6.2.4 >S~)

d 7"'

)tlala

/Ja.

9.

g g'719 8~

Prior to excee 5% of rated thermal-wer, the licensees will make the necessary ification to assure the operability of the Continuous Purge Sy n the event of a loss of coolant accident.

!'rior to startup-ollowing the fi refueling outage, the licensees 1 install testing capabi 'or the 8 inch purge valve i ch would allow for testing to the dard Technical S

fications requirements of every 92 days.

Barrier for Hi h Ener E ui ment (8.4.1 SSER 3)

Prior to s following the first refuelin

, the licensees shall have instal arrier aro rans former i n the cable spreading area th table to the NRC.

Prior to installation censees shall su NRC review and approval the b

'esign to be used and justificatio acceptability.

• The paren e

'ollowing the tit1e of-.many license conditions denotes the section of the Safet~

-mn ort and/or its supplements wherein the li se-conZition is '6i ~cusse,d.

850201051g 850'g'DR ADOCN 05000389 PDR 10.

Non-Sa SSER Loads on Emer enc Power Sources

{Section 8.4.2 Prior to startup following ueling outage, the licensees shall implement the design

'ca disconnect four-,

kilovolt loads on de

'on of a safety injec 'ignal and provide two i s on devices in series for those non-t electri oads that are not disconnected by a safety injec or 1 oss of offsi te power.

Containme ctrical Penetrations (Section 8.4.3 12.

Prior to startup following refueling outage, the licensees shall complete the de 'fications ide independent primary and ault protection for each elec

'onductor pen ng containment.

Heav Loads (Section

9. 1.4 SSER 3) anct Prior to thirty days of startup following the second refueling

outage, the licensees shall have made commitments acceptable-to the NRC regarding the guidelines of Section 5.1.2 through 5.1.6 of NUREG-0612.

Fire Pro on (Section 9.5.1.11(a)

The licensees shall 'he fire protection program on a schedule ied in Section..

) and (b) of Supplement No he Safety Evaluation Report.

1'4.

Emer iesel Generator Modifications (Section 9.5.4. 1 SER)-

gggai Ja>~

15.

Prior to startup fol 'he firstwefueHng outage, the licensees shall a) install and ve-fu.

tional the automatic prelube pump and b) te instruments and con cated on the di ngine skid to the floor-mounted panel.

ctive Maste Mana ement (Section 11.2 11.5 SER 'SS~)

Within 14 mon after core load, the licens s all a) implement the design modific to automatic shut off the waste management condensate an i

d condensate pumps prior to the level reaching t er nozzle of the Primary Mater Storage Tank and b

plement the de 'odification to automatically isolate the L

ressure Safety Injection p

ischarge to the Refueli ater Tank upon receipt of a refueling tank hi ater level alarm.

Pr tor o

wing the first ',

s all a) install waste co tanks

and, b) install a second cont'en analyzer.

16.

itial Test Pro ram (Section 14 SER)

'he

'nsees shall conduct the post-fuel loading initial st program (set forth in Section 14 of the St. Lucie 2 Fin Safety

):lou ~

Analysis

port, as amended through Amendment 13 and F &t's letter po L-83-207) w'thout making any modifications to this ogram unless such modifica 'ons are in accordance with the pr sions of 10 CFR Section 50.59.

n addition, the licensees sha not make any major

'odifications to is program unless modific ions have been identified and have ceived prior NRC app val.

Major modifications are defined as:

a.

b.

Elimination of any test identif d as essential in Section 14 of the Final Safety An

's Report, as amended through Amendment 13 and FP&L's le r L-83-207; Modification of test o gectives,

ethods, or acceptance criteria for any test identif ed as essenti in Section 14 of the Final Safety Analysis R

ort, as amended th ough Amendment 13 and FPEL's letter L 3-207; "c ~

Performance of any test at a power level di erent from that describe 1n the program as limited by this l ense authorization; and d.

17.

NUR

~~+a.

bAa4d I'~

sic Fa're to complete any tests included in the descry d program armed or scheduled) for power levels up to the auth ized power level.

-0737 Conditions (Section 22 SER Section 13.3 SSERW)

Emer c

Res onse Ca abf lit (I.C.9, I.D.1, I

.2, 7.5.4 1)

The licens shall implement t requirements of Generic Letter No. 8 on the fol ing schedule:

a) b)

Prior to startu ollowing the first refueling outage, the Safety P

amete isplay System (SPDS) shall be operable, includin raining of rators.

8 eptember 30, 1983 the lice e shall submit for NRC review and approval a detailed con 1

room design review summary report.

c)

By Novem 30, 1983 the licensee shall submit~ r NRC review and a

oval a Regulatory Guide 1.9~&valuation Report describin ow Regulatory Guid M97 has been met and justifications any deviat s.

d)

By November 1, 1983 the 1' shall submit for NRC review and approval t speci 'mergency Operating Procedures descrip sons.

By July 1, 984, the licensee shall implement'he upgraded Emergency crating Procedures including SPDS and control room upgrades.

e)

By October

1983, the permanent Emergency Operating ility

~-shall be operational.

2)

The license all maintain interim emergency support facilities (Techns port Center, Operations Support Center and the Emergency'ions Facility) until the

, upgraded facilities are co;Apl'ete

~ I

~

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7 b.

Contro om Desi n Review {I.D.1 A

endix E,

Also.-Part A of A

endix C

ER 1

SSER 3

Prior to exceeding (5) pe~re rat of rated thermal

power, the licensees shall comp correction of the human engineering discrepancies as not

'n App

'x E of this license.

Prior to s

up following the first re ing outage, the licens shall rearrange the instruments des bed in Appendix F.

ce Reactor Co t

S stem Vents (II.B.l SSER 2) d.

e.

Prior to exceeding five r

FPKL shall have the re coola and operati Pos cident Sam lin S stem

( II.B.3 SSER 3)

Prior to excee 'nitial criticality, FPhL shall have installed and opera al the Post Acct-d~ent Sampling System.

Prior to startup followin t e st refueling outage, the licensees shall submi or NRC appr 1

a revised core damage assessment pro~c e which incorporates, a minimum, hydrogen levels, rector coolant system pressure, cor xit thermocouple tempe~rtQres and containment radiation levels in dition to radionuclide data.

ITr ntainment Hi h Ran e Radiation Monitors.(II.F.1(2c) rated thermal

power, m vents installed SSER 3~

Prior to exceeding.five-(5). percent of rated thermal. po~er, FPKL shall have the-i'n-containment high range radiation monitors insta>led and operational.

de uate Core Coolin Instrumentation

( II.F.2 SSER.l')

The lice ees shall have:

1)

The final ign core exit thermocouple (CET) system installed wit isplays in the gualified Safety Parameter Display System

{

DS) cabinets, by initial criticality.

2)

The instrumentation nece ary to monitor and display subcooling margin installe the

(}SPDS cabinets and operable by initial criticality.

3)

The heated~junction thermocouples (HJ installed in the gSPOS cabinets and operable by June 3.

4)

The final Inadequate Core Cooling System checko and test report completed and submitted by January 15, 84.

~

~ 18.

Reactor pgJ;eL P~

reakers Post-Tri Review Procedures n 7.2.3.1, Within 60 days of'e of this

ent, the licensee shall provide t graded post-trip review proce NRC staff re

'19)

Prior to storing extended burnup fuel in the modified spent fuel pool (greater than 38,000 Mw-days/Metric ton) the licensee must submit and obtain approval of a new analysis that addresses the potential of large gap releases for the extended burnup fuel.

0.

F.

G.

The licensees shall fully implement and maintain in effect all the provisions of the Coomission-approved physical security, guard traini ng and qualification and safeguards contingency plans including amendments made pursuant to the authority of, 10 CFR Section 50.54(p).

The approved plans, which -contain information described in 10 CFR Section 73.21, are collectively entitled "Florida Power and Light Company, St. Lucie Plant Security Plan," Revision 6, dated August 9, 1982; St. Lucie Plant Safeguards Contingency Plan" dated June 19, 1980; and "St. Lucie Plant Training and gualification Plan" dated April 29, 1981, as revised by pages dated June 23, 1981.

Prior to initial criticality, the licensees shall satisfy the comnitments in FP&L's letters L-83-215 dated April 5, 1983 and L-83-217 dated April 6, 1983.,

Also prior to initial criticality, the licensees shall perform a reevaluation of vital areas with due regard to the safety-safeguards interface, and provide the NRC the results of their reevaluation.

Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that i s s i gni ficantly greatei than that evaluated in. the Final Environmental Statement dated April 1982, the licensees shall provide written notification to the Office of Nuclear Reactor Regulation.

The licensees shall report any violations of the requirements contained in Section 2, Items C.(1), C.(3) through C.(17), 0;.

and E. of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirm by telegram, mailgram, or facsimile transmission to the NRC Regional Administrator, Region II, or his designee, no later than the first working day following the violation, with a written followup report within fourteen (14) days.

The licensees shall notify the Comnission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Comnission.

H.

The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended,'o cover public liability claims.

I.

In accordance with the Commission's direction in its Statement

~

of Policy, Licensin and Re ulator Polic and Procedures for Environmental Protection Uranium Fuel C cle Im acts, October 29, 1982, thi s li cense is subject to the final resolution of the pending litigation involving Table S-3.

-See, Natural Resoruces Defense Council v.

NRC No. 74-1586 (D,C. Cir. April 27 1982 J.

This license is effective as the date of, issuance and shall expire at midnight, on April 6, 2023.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosures:

1.

2.

Appendix A 3.

Appendi x 8 4.

Appendi x C 5.

Appendi x D

6.

7.

Harold R. Denton, Director Office of Nuclear Reactor Regulation Ild<dp' (Technical Specifications)

(Environmental Protection Plan)

(Antitrust Condi tions)

(Antitrust Conditions)+sc~ancies+

Dc,(d-e~

P QggegeZ p.< @wc~dme~

AJc'.

Date of Issuance:

APR 6

]9)3

APR 6

ATTACHY=NT 1 TENS TO BE COMPLETED PRIOR TO INITIALCRITICALITY I.

The licensee wi ccmplete to the satisfaction of NRC Re on II the following open it s:

A.

Completion of re 5, Sr-89/90

. aciochemical a

lysis procedures (82-72-01)

'B.

Modification o= parti ulate sampling col ector on plant vent so isotopic analysis can performed (8 2-03)

C.

Resolve remote shutdown de onstrat n test followup items (82-63-04);.

D.

Resolve undervol age relay se rgs for emergency-bus transfer (83-30-01)

The licensee will resolve to e sa.isf tion of NRC Region II the following Construction Deficiency Repo s (50.5""(e) items):

A.

B.

C.

D.

PORV Solenoids Long erm Reliability De 'ciency (CDR-83-01).

Westinghouse Ga+e Valves -

Prema

.ure Indica

'on of Closure (CDR-83-03).

Boric Acid Y> k=up (BAYi) Sys.em Safety Injection ctuation.System (SIAS)

Pump Start/Logic (CDR-83-06).

r HPSI P

mp Bear'.ng Bracket Drain Deficiency (CDR-83-07)

E.

Con ensate S orace Tank Implosion (CDR-83-09).

The l>f'censee will inspect and clean as necessary, the electrical'ab'nets assyciated with saf=ty-related equi"ment -o verify that conditions are acceptable and cons',stent with the'u;..per/lif ed lead records.

t

e ITEYiS TO BE COYiPLETED PRIOR TO EXCEEDING 5% RATED POMER I.

The li ensee will complete to the satisfaction of NRC Region II the require-rents o

the following bulletins:

B.

e S

Pipe s

port base plate designs using concrete expansio anchor bolts (79-BU-

).

~

~

Seismic ana sis for as-built safety-related pipi g systems (79-BU-14).

C.

Engin ared Sa ty Feature (ESF) reset control~s 80-BU-06)

D.

D cay Heat Remova system operability (80-BU 12).

E.

Electrical connector assemblies (77-BU-05 (77-BU-05A).

F.

Yasonary wall design (8 -BU-ll) (CDR 8 -24).

G.

Possible loss of emergency notific ion system (ENS) with loss of off-site power (80-BU-15).

(

II.

The licensee will resolve to the sa sfaction of NRC Region II the following Notices:

J.

Des',on miskpplication of B

(:EN 83-13).

Fa i 1 u."e of, General El e ric III. The

': icensee wi 1 1 resolv to the cpen i=ems:

a gen-Pat rson standard strut restraint clamp type HFA re ys (IEN-82-13).

satisfac ion os NRC Region II the following 3.

Review shieldin adequacy of CVCS letdown monit sample lines (S2-70-02).

Conduct an countabi lity drill for bo.h Units 1 and following imspl esmsenta i on of the Unit 2 Securi ty Pl an (82-05-10).

C.

Proaram o rev'sew and document safe y

uestions for tests and Eval ate need for shielding of s""nt resin tank valve gallery 10 CFR 50.59 evaluations r unreviewed experiments (82-64-01).

penetrations in ion exchange c bicle and (82-70-05).

!V.

The 'ensee will resolve to the satisfaction of NRC Region II the iss e of pro

=". labeling and accessibility control of motor operated valve therm 1

ov

-. load pro. ection bypass switches and control room/remote shutdown pan 1

t c

n rol diversion switches.

1)4C!-6~

IO i-)m~J W F) r

I Appendix E

Human Engineering Oiscrepancies License No. NPF-16 Ke storage will be provided as well as the nec ssary key acc ss cont I procedures for those keys used in the Control Room and Remote hutdown Panel.

A re-evalua on of the glare problem will be performed after the diffusing gri has been installed.

Those items then s.ill found to have glare p oblems will have suitable backfits implemented.

The Remote Con rol Transfer Panels will have a security seal for securi.ty purposes.

perations of any control transfer switch is annunciated in the co trol. room.

The SL-2 cc~unications

'stm is currently under design.

The system wil be r viewed in ccordance with the communications section of HUREG-0700.

Yiultiple input annuncia or'in ws will undergo assess~ont as to reflash capability.

Any~ ".hat do ot "reflash" and require the

'unction will be provided with the urei'lasn" and "r edible' uncil Gn ~

Blank annunciator,& les will be exting shed.

~ Glare and potegial face plate scratching ill be addr ssed through displpg shielding to reduce inciden light to he display surface and protect face plates.

/

A lighting color convention will be established.

This item will be addressed as part of the ongoing beling and

~

~

dema ation orogram.

T e boron conc ntration recorder will use lined unscaled aper.

ecorder Panel 201 will have proper scales.

Recorder Pane 202 uill have 'proper scales.

All labels will be reviewed as par of the labeling study.

Those missing labels will be installed and those incorrect label will be corrected.

j5ENDt',FNT NO, 2

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APR 6

too3 APPENDIX F CONTROL BOARD 206 E()UIPMENT REMORK A.

Oisp ays to be relocated'(Total 12) 1.

Sa ty Injection Tanks a;

L A-3311 b.

L

-3312 c.

PI -3311 d.

P IA 319 e.

LIA-21 LIA-3 2

g.

PIA-33 h.

P IA-332 2.

LPSI a.

F1-3312 b.

Fl-3312 Label 103 Label 102 Label 101 Label 100 Label 97 Label 96 Label 95 Label 94 L bel 67 L

el/57 Loop Zg Loop 2A2 LoopfZAZ Loo( ZA2 Loep 2A1 Loop 2A1 Loop ZA1 Loop 2A1 Loop 2A2 Loop 2A1 B.

3.

HPSI a.

Fl-3311 Label 66 Loop 2A2 b.

Fl-3321 Label 6

Loop 2A1 Hand controllers to be rel cated (Total 2) 1.

Safety Injection Tanks a.

HIC-3618 Label 98 Loop 2A2 b.

HIC-8628 Label 93 oop 2Al Hand switches to be relocated (T tal 10)

I 1.

Safe,ty Injection Tanks a.

HS-242-1 b.

HS-3612 c.

HS-3733 d.

HS-3614 e.

HS-242-2 f.

HS-3622 g.

HS-3735 h.

HS-3624 2.

LPSI Label 192 Label 225 Label 258 Label 291 Label 189 Label 222 Label 255 Label 288 Loop A2 Loop 2 2 Loop 2A Loop 2A2 Loop 2A2 Loop 2A2 Loop 2AZ Loop 2A2 a.

HS-3615 b.

HS-3625 Label 293 2A2 Loop 2A2 Label 292 2A2 Loop 2A1 Ame lo e 4 do.

~

~ D.

Indicating 11 ts to be relocated (Total

)

1.

Safety injecti tanks - 12 la s for associated hand switches in C.l above.

2.

LPSI - 4 lamps for as iated hand swi tches in C. 2 above.

E.

New wires to be pul d (Total 5

F.

Wires to be re ed i.e. repulled and c

at new location (Total 55)

G.

Wire mark changes (Total 349)

~

• l STATE OF FLORIDA

)

)

ss.

COUNTY Of DADE

)

C.

O. Woody, being first duly sworn, deposes and says:

That he is Vice President Nuclear Operations of Florida Power 8 Light Company, the licensee herein; That he has executed the foregoing document; that the statements made in this document.are true and correct to the best of his knowledge, information, and

belief, and that he is authorized to execute the document on behalf of said Licensee.

C. 0.

Wood Subscribed and sworn to before me this day of

, 1989.

C 4

ARY PUBLIC, in and for the County of D,;"dF.'. State of Florida.

~"Horace", PUB1.IC SIan pF Fl.pRIpA HY,CPHHISSIOH E'XP.

FEB 14,1988 (BQtt6FP IHRU GEHERAL IHS.

UHO.

~ My>'commi ssion expires:

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