ML20137R544

Discusses 950605 Complaint from GL Phipps Re Discrimination Resulting from Raising Safety Concerns While Performing Duties at Turkey Point

ML20137R544
Person / Time
Site:	Turkey Point
Issue date:	09/22/1995
From:	Uryc B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Perry A LABOR, DEPT. OF
Shared Package
ML20137R112	List: IR 05000335/1996003 ML20137R106 ML20137R236 ML20137R253 ML20137R297 ML20137R317 ML20137R468 ML20137R544 ML20137R556
References
FOIA-96-485 NUDOCS 9704140152
Download: ML20137R544 (44)

Text

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, t-5' - M aseg . UNITED STATES

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NUCLEAR REGULATORY COMMISSION - ,

REGION 11 4 101 MARIETTA STREET. N.W. SUITE 2000 0 jl ATLANTA. GEORGIA 303234190 - j I  % . September 22, 1995 1

- U.S'. Department of. Labor l Employment-Standards' Administration ATTN: Mr. Alfred H. Perry .t Regional' Director for Wage;and: Hour  ?

? 1371 Peachtree Street, N.E. >

Atlanta,. Georgia '30367

SUBJECT:

REQUEST.FOR ACCESS-TO DOL CASE FILE

Dear Mr. Perry:

On June 5,'1995, the'U.S. Department of Labor's Wage.and Hour Division in [

. Fort Lauderdale, Florida, received complaints from_ Mr. Gary L. Phipps~, an

+

employee of Florida. Power and Light Company's Turkey Point Nuclear Plant. The employee alleged that he had-been subjected to discrimination as a result of i raising safety concerns while performing his duties at the Turkey Point ,

Nuclear Plant. In response to that complai t, the Wage and Hour Division .

conducted an investigation, and in a letter dated September 8, 1995, the Assistant District Director of the Wage and Hour Division, Fort Lauderdale, Florida, found that the. evidence obtained during the Division's investigation indicated that the employee was engaged in a protected activity within the

, scope of the Energy Reorganization-Act and that discrimination as defined and  !

prohibited by the statute was a factor in the actions which comprised his ,

complaint.

The~ purpose of this letter is to request that the D0L case file pertaining to this case be made available for review by a member of my staff. Under the October 25, 1982,-' Memorandum of Understanding between D0L and NRC, D0L makes applicable case , file material available to NRC officials. In response to an NRC request for arrangements to facilitate. obtaining copies of case file documents, the Assistant Administrator, Wage and Hour Division, agreed in January 1987, that 00L will provide a copy of the Compliance Officer's narrative report if requested by NRC. If necessary, copies of exhibits,.

however, will be made by NRC personnel using D0L copying equipment at the DOL Loffice.

The material requested -and copied by.NRC will be conspicuously marked as c ' material.obtained from the Department of Labor under a special arrangement lwith the NRC and that the information may not be disclosed outside the NRC without' prior D0L;appro. val.

9704140152 970404

• PDR FOIA BINDER 96-485 PDR i ,

W.

l A. . Perry 21 When the file is available at your office, or should you have any questions regarding this request, please feel free to contact me at (404) 331-5505, or Linda Watson at (404) 331-4192. As_always, your cooperation and assistance in these matters.are. greatly' appreciated.

Sincerely, A

Brun Uryc, Director Enforcement and Investigation Coordination Staff CC:

Department of Labor /ESA Wage and Hour Division ATTN: Ana R. Moreno Assistant District Director 299 E. Broward Blvd., Room 408 Fort Lauderdale, FL 33301 '

Assistant Administrator Employment Standards Administration Wage and Hour Division Department of Labor Room S-3502 ,

200-Constitution Avenue, N.W. I Washington, D.C. 20210 l

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.e A. Perry 3 Distribution:

J. Lieberman, OE D. Rosano, OE J. Goldberg, OGC C. Evans, RII

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• a ase% UNITED STATES

? J# NUCLEAR REGULATORY COMMISSION -

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,101 MARIETTA STREET, N.W.. SutTE 2900 ATLANTA, GEORGIA 3035019e 2

i v****./ . January 4, 1996 i LMEMORANDUM TO: Ellis W. Herschoff,~ Director g- l Division of Reactor Projects yg N M

b 'h FROM: ~ Bruno.Uryc,-Director. .

Enforcement and Investigatiorts i

Coordination l Staff '

}

SUBJECT:

. PHIPPS V. FLORIDA POWER AND LIGHT COMPANY

-DEPARTMENT OF LABOR (DOL) CASE NO. 94-ERA-53 l Attached for your_information'and review is Florida Power and Light Company's  ;

l (FP&L) response, dated December 11, 1995,- to our " chilling effect" letters Jwhich were sent to FP&L on October 6 and 25, 1995, regarding the subject case. l The case involves the alleged discrimination (i.e., denial of overtime) against Mr.: Gary L. Phipps for his engaging in protected activities'at the ,

. St. Lucie Nuclear Plant. On-September 8, 1995, the DOL District Director j found thu discrimination was a factor in the actions taken against Mr. Phipps.

A chilling effect letter serves three purposes: 1) to notify the licensee of the NRC's. concern about a potential.. discriminatory act; 2) to understand the basis for the licensee's position on whether or not discrimination occurred; and 3) to obtain a description of any remedial action the licensee plans to take to address any potential chilling effect.

Your review should focus on making a determination whether the potential act of discrimination caused a chilling effect. For example, pu should attempt to determine if the general plant population's awareness of the potential discriminatory act will discourage other plant employees or contractor personnel ~from raising safety concerns. In addition, your review should also address your proposal for any enforcement action in the case.

Also be aware that on November 30, 1995, a DOL Administrative Law Judge issued a recommendation that this case be dismissed with prejudice, based on the

, settlement agreement between Mr. Phipps and FP&L. The settlement agreement is currently pending the Secretary of Labor's final decision.

Please provide us with the results of you review by January 19, 1996.

. Attachments':- 1. 'Ltr, Ebneter to Goldberg,'

dated October 25, 1995

2. Ltr, Ebneter to Goldberg,  !

dated October 6, 1995 Ltr, Goldberg to Ep.ater, l

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dated December 11, 1995 cc w/atti: C'. Evans <

W. McNulty;  ;

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2ctober 25,4395

% 95-209

lorida Power and Light Company-

TTN:: Mr. J.:H..Goldberg

, Pres 1 dent ' Nuclear Division h 0. Box-14000' Juno Beacn. FL- 33408-0420 IUBJECT:- COMPLAINT OF' ALLEGED DISCRIMINATION ,

. Cear ' Mr. ' Goldberg:

'his letter refers to your teleonone conversation with Mr. Jon R. Johnson of

. this office on October 17. 1995. in which you discussed our letter.to Florida .

4wer and Light- Company, dateo October 6.1995. That corresponcence addressed' 5 Septemoer 8,1995. Department Of Labor Assistant Distr 1ct Director finding

f discrimination assoc 1ateo with a comolaint filed oy Mr. 3ary L. Phipps-iga 1nst Florida 1 Power and Light Company.

's a result of the aforementioned discussions.. it was noted that the .

October 6. -1995, letter was incorrectly docketed to 'your Turkey Point facility and was also distributed to the standard. service list for Turkey _ Point. As l stated in the text of the letter. the subje:t Department of Labor case is.  ;

directly associated with your St. Lucielfacility, althougn the complainant was  ;

.previously employed at both sites.

l l

This letter, appropriately docketed and distributed for your St. Lucie j

facility, and its enclosure correct the official record in this matter. i Further, in consideration of this error and the information you provided  ;

during the October 17, 1995, discussion, we are extending the. time of your required response to within 45 days of the date of this letter. In preparing jour. response, however you should follow the instructions provided in the original letter. J Thank you for your cooperation in this matter. If you have any additional questions, please contact Mr. Johnson at 404-331-5501.

Sincerely, ORIGINAL SIGNED BY:

Jon R. Johnson /FOR Stewart D. Ebneter  :

Regional Administrator l 2

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Docket.Nos.. 50-335, 50-389 License Nos. DPR-67, NPF-16

Enclosure:

As. stated l ccw/e'nc1:JSee Page 2

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FP&L 2 cc w/ encl:

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D. A. Sager Bill Passetti Vice President Office of Radiation Control St. Lucie Nuclear Plant Department of Health anc P. 0. Box 128 Rehabilitative Services Ft. Pierce, FL 34954-0128 1317 Winewood Boulevara Tallahassee. FL 32399-0700 H. N. Paduano. Manager Licensing and Special Programs Jack Shreve Florica Power and Light Company Public Counsel P. O. Box 14000 Office of the Public Counsel Juno Beac,h FL 33408-0420 c/o The Florica Legislature 111 West Madison Avenue. Room 812 r J. Scarola Tallahassee. FL 32399-1400 Plant General Manager St.-Lucie Nuclear Plant Joe Myers. Director P. O. Box 128 Division of Emergency Prepareoness Ft. ?ierce. FL 24954-0128 Department of Community Affairs 2740 Centerview Drive l Robert E. Dawson Tallahassee. FL 32399-2100 1 Plant Licensing Manager i St. Lucie Nuclear Plant Thomas R. L. Kindred '

l P. O. Box 128 County Administrator Ft. Pierce, FL 34954-0218 St. Lucie County 2300 Virginia Avenue J. R. Newman. Esq. Ft. Pierce. FL 34982 Morgan. Lewis & Bockius 1800 M Street. NW Charles B. Brinkman Washington, D. C. 20036 Washington Nuclear Operations ABB Combustion Engineering, Inc.

John T. Butler, Esq. 12300 Twinbrook Parkway, Suite 3300 Steel. Hector and Davis Rockville. MD 20852 4000 Southeast Financial Center Miam1. FL 33131-2398

La nec e - UNITED STATES

• '  ;[. NUCLEAR REGULATORY COMMISSION J"', 4*

REGloN (1 i i 101 MARIETTA STREET. N.W., SUITE 2900

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j ATLANTA. GEoMGIA 3GIZ34190

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/ Octocer i ".395 EA 95-209 Florida Power and' Light Company ATTN: Mr. J. H. Goldberg -

President - Nuclear Division P. O. Box 14000 i Juno Beacn, FL '33408-0420 '

SUBJECT:

COMPLAINT OF ALLEGED DISCRIMINATION

Dear Mr. Goldberg:

On June 5,1995. the U.S. Departmerit of Labor's Wage and Hour Division in ,

Fort Lauderdale. Florida. received complaints from Mr. Gary L. Phipps, an '

employee of Florida Power and Light Company s Turkey Point Nuclear Plant ano St. Lucie Nuclear Plants. The employee allegeo that he had been suojected to discrimination as a result of raising safety concerns while performing his ,

duties at the St.- Lucie Nuclear Plant. In response to that complaint, the Wage and Hour Division conducted an investigation, and in a letter dated  :

September 8, 1995, the Assistant District Director of the Wage and Hour- l Division, Fort Lauderdale, Florida, found that the evidence obtained during  :

the Division's investigation indicated that the employee was engaged in a  !

. protected activity within the scope of the Energy Reorganization Act and that l discrimination as defined and prohibited by the statute was a factor in the  ;

actions which comprised his complaint.

l The NRC is concerned that a violation of the employee protection provisions I set forth in 10 CFR 50.7 may have occurred and that the actions taken against

~the employee may have had a chilling effect on other licensee or contractor personnel.

Accordingly, pursuant to sections 161c, 1610, 182 and 186 of the Atomic Energy

. Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.204 and 10 CFR 50.54(f), in vrder for the Commission to determine whether your license should be modified, suspended or revoked, or other enforcement action taken to ensure compliance with NRC regulatory requirements, you are required to

- provide this office, within 30 days of the date of this letter, a response in writing and under oath and affirmation that:

i 1.- Provides the basis for the employment action regarding the employee and includes a copy of any investigation reports you have rep-ding the circumstances of the action; and q

'2. Describes the actions, if any, taken or planned to assure that this employment action does not have a chilling effect in discouraging other

' licensee or contractor employees from raising perceived safety concerns. 1

_Your. response should;not, to the extent possible, include any personal privacy, proprietary, or safeguards information so that it can be released to y n g vorf 7/

ac/nn, .4  %

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a FP&L 2 the public and placeo in the NRC Public Document Room. "f personal privacy information is necessary to provide an acceptable response. then please provide a bracketed copy of your response that icentifies the personal privacy-related information and a redacted copy of your response that deletes the personal privacy-related information. Identify the particular portions of the response in question which, if disclosed, would create an unwarranted invasion of personal privacy, . identify the individual whose privacy would be invaded in each instance. describe the nature of the privacy invasion, and indicate why, considering the public interest in the matter, the invasion of privacy is unwarranted. If you request withholding on any other grounds, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g.,

, provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential comercial or financial information).

After reviewing your response. the NRC will determine wnether enforcement action is necessary at this t;me to ensure comoiiance with regulatory requirements.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice." a copy of this letter will be placed in the NRC Public Document Room.

The responses directed by this letter are not subject to the clearance  !

l procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980. Pub. L. No.96-511.

Sincerely, l l

1 jgs; /

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'S;ewart D. bneter  !

Regional Administrator Docket Nos. 50-250, 50-251 License Nos. DPR-31. DPR-41 l l

cc:

Department of Labor /ESA Wage and Hour Division  ;

ATTN: Ana R. Moreno Assistant District Director 299 E. Broward Blvd., Room 408 Fort Lauderdale, FL 33301 i cc cont'd: (See page 3) i 1

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'FP&L 3 >

-cc. cont'd:

Assistant Administrator. John T. Butler. Esq. l Employment Standards Administration Steel. Hector and Davis  :

Wage and Hour Division 4000 Southeast Financial Center '

Department of' Labor Miami, FL 33131-2398  !

Room 5-3502~ l 200 Constitution Avenue. .'t.W. Attorney General  !

Washington, D.C. 20210 Department of Legal Affairs The Capitol H. N. Paduano' Manager

. Tallahassee. FL 32304 Licensing & Special Programs Florida Power.and Light Company Bill Passetti P. O. Box 14000 Office of Radiation Control Juno Beach, FL 33408-0420 Department of Health and Rehabilitative Services l D. E. Jernigan 1317 Winewood Boulevard  ;

Plant General Manager . Tall ahassee. . FL 32399-0700 i Turkey Point Nuclear Plant' P. 0. Box 029100 Jack Shreve  !

" Miami, FL' 33102 Public Counsel  !

Office of the Public Counsel T. F. Plunkett c/o The Florida Legislature Site Vice President 111 West Madison Avenue, Room 812 ,

Turkey Point Nuclear Plant Tallahassee, FL 32399-1400 P. O. Box 029100 Miami, FL 33102 Joaquin Avino i County Manager of Metropolitan T. V. Abbatiello Dade County Site Quality Manager 111 NW 1st Street, 29th Floor l Turkey Point Nuclear Plant Miami, FL 33128 r P. O. Box 029100

' Miami, FL 33102 Joe Myers. Director Division of Emergency Preparedness E. J. Weinkam Department of Community Affairs Licensing Manager 2740 Centerview Drive Turkey Point Nuclear Plant -Tallahassee, FL 32399-2100  :

P. O. Box 4332 i Miami, FL 33032-4332  !

J. R. Newman, Esq. l Morgan, Lewis & Bockius i 1800 M Street, NW -

Washington, D. C. ~ 20036 T'

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'% UNITED STATES ,

- S NUCLEAR REGULATORY COMMISSION l{

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'$o ' REGloN N 101 MARIETTA STREET, N.W., SUITE 3D0 g- l U ATLANTA, GEoRolA 3DED4180

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%,.... ' October 6,1995 s  ;

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,o EA 95-209- .

P Florida' Powerand Light; Company i

ATTN:' Mr. J. H. Goldberg'> ,,

1 1Pr_esident -' Nuclear. Division-

! P.-0.cBox 14000 i Juno Beach, FL :33408-0420-l

\

SUBJECT:

-COMPLAINT OF ALLEGED DISCRIMINATION- i n ,

Dear Mr. Goldberg:

~

On June 5,71995, the U.S. Department of Labor's Wage.and. Hour Division in l

, . Fort Lauderdale, Florida, received complaints from Mr. Gary L. Phipps, an j n

. employee:of. Florida Power and Light Comp,~ v's Turkey Point Nuclear.. Plant and 1 St. Lucie Nuclear' Plants. The employee leged that he had been subjected to i

, discrimination as-a result of raising safety concerns while performing his ,

i duties'at the St. Lucie Nuclear Plant. In response to that complaint,'the ,!

-Wage and. Hour Division conducted a 'n investigation, and in a letter dated '

-September 8' 1995,'the Assistant District Director of the Wage and Hour Division', Fort Lauderdale, Florida, found that the evidence obtained during.  ;

, the Division's' investigation indicated that the employee was engaged in a  :

, protected activity within the-scope of the Energy Reorganization Act and that

• 4 discrimination as defined and prohibited by the statute was a factor in the ,

l actions which comprised his complaint. '

1

!' The NRC is concerned that a violation of the employee protection provisions 1

, set forth in-10 CFR 50.7 may have occurred and that the actions taken against ,

I the employee may have had a chilling effect on other licensee or contractor l

personnel.

l Accordingly, pursuant to sections 161c, 161o, 182 and 186 of the Atomic Energy  !

Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.204 and l

, 10 CFR 50.54(f), in order for the Commission to determine.whether your license  ;

should be modified, suspended or revoked, or other enforcement action taken to

-ensure compliance with NRC regulatory requirements, you are required to j provide this office, within.30 days of the date of this letter, a response in l

writing and under. oath and affirmation that:

-1. Prov. ides the basis for the employment action regarding the employee and includes a; copy of any investigation reports you have regarding the  !

circumstances of the action;'and 2.. Describes.the actions, if,any, taken or planned to assure that this employment action does.not have a chilling effect in discouraging other i licensee or contractor employees from raising perceived safety concerns. i iYour response should_ not, to the extent possible, include any personal  :

privacy, proprietary, or safeguards information so that it can be released to J

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FP&L 2 the public and placed in the NRC Public Document Room. If personal privacy information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the personal _

privacy-related information and a redacted copy of your response that deletes the personal privacy-related information. Identify the particular portions of the response in question which, if disclosed, would create an unwarranted invasion of personal privacy, identify the individual whose privacy would be invaded in each instance, describe the nature of the privacy invasion, and indicate why, considering the public interest in the matter, the invasion of privacy is unwarranted. If you request withholding on any other grounds, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g.,

provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information).

After reviewing your response, the NRC will determine whether enforcement action is necessary at this time to ensure compliance with regulatory requirements.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter will be placed in the NRC Public Document Room.

The responses directed by this letter are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No.96-511.

Sincerely, t/

ewar bneter Regional Administrator Docket Nos. 50-250, 50-251 License Nos. DPR-31, DPR-41 CC*

Department of Labor /ESA Wage and Hour Division ATTN: Ana R. Moreno Assistant District Director 299 E. Broward Blvd., Room 408 Fort Lauderdale, FL 33301 n

cc cont'd: (See page 3)

. . . ~_ . . . . _ _ . . _. _ _ . . . _ . _ _ . _ ._ _ ...- __ _

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'f FP&L 3 Ecc cont'd:'

Assistant Admin'istrator: John T.' Butler, Esq.

' Employment Standards' Administration -Steel, Hector and Davis- ,

Wage and Hour Division 4000 Southeast Financial Center -

d Department of Labor Miami,,FL 33131-2398 ,

Room 5-3502 i e s200 Constitution Avenue, N.W. Attorney General Washington,-D.C. 20210 Department of Legal Affairs .

The Capitol . l H.N.-Padu'anofManager Tallahassee, FL 32304 .

4 Licensing & Special Programs l

, Florida Power and Light Company Bill Passetti-L P. 0. Box 14000 Office of Radiation Control

-Juno Beach ..FL 33408-0420 Department of Health and. '

_ Rehabilitative Services l

'D. E. Jernigan 1317 Winewood Boulevard  ;

P1 ant' General' Manager Tallahassee, FL 32399-0700 1 4

Turkey Point Nuclear Plant >

.P. 0. Box 029100 Jack Shreve

~

Miami, FL 33102.

Public Counsel  !

Office of the Public Counsel  !

.T. F. Plunkett c/o The Florida Legislature ,

Site Vice President 111 West Madison Avende, Room 812

, Turkey Point Nuclear Plant Tallahassee, FL 32399-1400 ,

P. O. Box 029100 -

Miami, FL 33102 Joaquin Avino County Manager of Metropolitan T V. Abbatiello Dade County ,

Site Quality Manager 111 NW lst Street, 29th Floor

Turkey Point Nuclear Plant Miami, FL 33128

. P. O. Box 029100 Miami, FL 33102 Joe Myers, Director Division of Emergency Preparedness E. J. Weinkam Department of Community Affairs Licensing Manager 2740 Centerview Drive Turkey Point Nuclear Plant Tallahassee, FL 32399-2100 .

i P. O. Box 4332 Miami, FL 33032-4332 J. R. Newman, Esq.

. Morgan, Lewis & Bockius-1800 M Street, NW' .

Washington, D. C. 20036--

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- istribution:

JLieberman, OE

- JGoldberg, OGC RZimmerman', NRR-i RRosano,.0E GTracy,.OEDO

'EMerschoff,.RII.

.RCroteau, NRR Klandis, RII I Buryc,; RII I LWatson, RII H WMcNulty,.OIF0/RII- i

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Thomas P. Johnson- l 4

Senior Resident Inspector. -

' O.S. - Nuclear . Regulatory Commission I P. O. Box I448 Homestead,~FL .33090 t

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' OPPICE M.ORP /\ M;Dff M: DOS , M: ORA M:EICS / ful: ORA M81 i' 'NAME ELal ff AGheen CEvers LAsye k r DATE 09/ /M' 09 M/ M ' 09 3 09 /M M 09 / /M COPY 7 [ER) 840 YES~ [ YES M YES h) (ES ) NO YES NO.

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1. S REGION ll U o 101 MARIETTA STREET. N.W., SUITE 2000 U j ATLANTA, GEORGIA 3tXED o190

%,,, September 22, 1995 i i

, U.S. Department of Labor Employment Star.dards Administration e ATTN: Mr.' Alfred H. Perry Regional Director for Wage and Hour  :

1371 Peachtree Street, N.E. '

Atlanta, Georgia 30367

SUBJECT:

REQUEST FOR ACCESS TO DOL CASE FILE

Dear Mr. Perry:

l I

On June 5, 1995, the U.S. Department of Labor's W29e and Hour Division in ,

Fort Lauder'ble, Florida, received complaints from Mr. Gary L. Phipps, an )

4 employee o /J.orida Power and Light Company's Turkey Point Nuclear Plant. The  ;

employee alleged that he had been subjected to discrimination as a result of  ;

raising safety concerns while performing his duties at the Turkey Point Nuclear Plant. In response to that complaint, the Wage and Hour Division j conducted an investigation, and in a letter dated September 8,1995, the  !

Assistant District Director of the Wage and Hour Division, Fort Lauderdale, i Florida, found that the evidence obtained during the Division's investigation j irdicated that the employee was engaged in a protected activity within the  !

scope of the Energy Reorganization Act and that discrimination as defined and  !

prohibited by the statute was a factor in the actions which comprised his I complaint.

The purpose of this letter is to request that the D0L case file pertaining to this case be made available for review by a member of my staff. Under the October 25, 1982, Memorandum of Understanding between DOL and NRC, DOL makes applicable case file material available to NRC officials. In response to an NRC reque.t? for arrangements to facilitate obtaining copies of case file 4 documents, the Assistant Administrator, Wage and Hour Division, agreed in January 1987, that 00L will provide a copy of the Compliance Officer's narrative report if requested by NRC. If necessary, copies of exhibits, however, will be made by NRC personnel using DOL copying equipment at the D0L office.

The material requested and copied by NRC will be conspicuously marked as 1 material obtained from the Department of Labor under a special arrangement  !

with the NRC and that the information may not be disclosed outside the NRC without prior DOL appro' val.

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i, When the--file is- available- at.your' office, or should you have any questions-i!

, ;regarding this request, please feel. free to contact.me at (404)-331-5505,.or j Linda Watson:at (404) 331-4192. As always,.your. cooperation and assistance in-  !

these matters are greatly appreciated. j

.j Sincerely, '

\ l r y  !

A Brun Uryc, Director  ;

Enforcement and Investigation i Coordination Staff -!

1 .

cc: t

-Department of-Labor /ESA l Wage and Hour Division j

. ATTN

.Ana R.'Moreno .

. Assistant District Director.

~

-299 E.-Broward Blvd., Room 408 j Fort Lauderdale, FL 33301 l Assistant-Administrator Employment Standards Administration  !

Wage and Hour Division Department'of Labor  !

Room'S-3502-  !

~

- 200 Constitution Avenue, N.W. i

, Washington, D.C. 20210 i

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A. Perry 3 Distribution:

J. Lieberman, OE

0. Rosano, OE J. Goldberg, OGC C. Evans, RII

0. Demiranda, RII RII 00L File 1

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1 Page-1 of 20 ._

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' FLORIDA POWER & LIGHT COMPANY ST. LUCIE U. NIT 1 #

M OPERATING PROCEDURE NO. 1-0250020 j pse .

REVISION 35 WI f

1.0 TITLE

@'1 2g 5 '2 BORON CONCENTRATION CONTROL - NORMAL OPERATION rmy .~:;n@,M,og l 2.0 REVIEW AND APPROVAL: A Reviewed by Plant Nuclear Safety Committee 5/30 19 74 Approved by K.N. Harris Plant General Manager 6/31974 Revision 35 Reviewed by Facility Review Group 8/10 & 8/17 1995 Approved by C. L. Burton Plant General Manager 8/17 1995

3.0 P_URPOSE

' This procedure establishes a method of operation to supply makeup water to the Reac:or Coolant System (RCS), Safety injection System and Refueling Water Tank (RWD at a desired baron concentration and provides instructions for the fo!!owing modes of control:

3.1 SORATE 3.2 DILUTE 3.3 MANUAL 3.4 AUTOMATIC l l

1 3.5 Shutdown Cooling (SDC) Boron Concentration Control l l

l l

S1 OPS DATE DOCT PAOCEDURE DOCN '-0250020 SYS COMP COMPLETED ITM 35 1

1

. )

4 Page14 of 20- .,  !

7 ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1 0250020. REVISION 35 N* ,

BORON CONCENTRATION CONTROL - NORMAL OPERATION  :

8.0. INSTRUCTIONS

(continued) 8.4 (continued) -

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, a.

3. l Enter the number of gallons to be added into the PMW Batch Integrator.%

and set desired flow rate on FRC-2210X (Makeup Water Flow). "

4 Start one Primary Water Pump if not running.

5. Place V2512 in the OPEN position.

6. Pla:e Mode Selector switch in DILUTE and observe flow indication of FRC-2210X.

l

7. Monitor VCT level to ensure tank does not fill up to high level alarm. For  !

extenced dilutions. match makeuo flow with charging flow using the PMW l makeup flow controller to prevent over filling the VCT while diverting letdown.

8. Upon completion of dilution, retum V2512 control switch to AUTO or CLOSED position.

9. Return Mode Selector Switch to AUTO or MANUAL.

10. Ensure that the desired reactivity change occurs.

8.5 Manual Mode of Operation 1

k Determine the desired volume to be added to the VCT and calculate the  :

proper blend ratio using the most recent chemistry boron samples of the t 1 A or 1B BAMT and the RCS. If the chemistry sample for the RCS is not available then use the boronometer reading.

f

w Page 15 of 20-

ST. LUCIE UNIT 1 m

i"3' OPERATING PROCEDURE NO. 1-0250020. REVISION 35 BORON CONCENTRATION CONTROL - NORMAL OPERATION

8.0 INSTRUCTIONS

(continued) 8.5 (continued) 'l

[

l i

NOTE - i The following formulas can be used to determine volume and blend ratio.

Remember to make note of the current totalizer rendings.

Volume to be added = desiied VCT level % - actual VCT level % X 33.8 gal /%.

ff Blend ratio = BAMT Concentration divided by RCS Concentration minus one 1 BAMT-1 4 RCS l

2. '

Ensure Mode Select switch is selected to MANUAL.

3.

Place FRC 2210Y and FRC-2210X to manual and close FCV-2210Y and N'

FCV 2210X by taking the controller output to zero.

9

4. Ensure 1 A or 18 pnmary water pump is running.

1

5. Ensure the BAM pump recirc valves V2510 and V2511 are open.

}

6. Start either the 1 A or 1B BAM pumo.

t

7. Open the Bone Acid Makeup isolation valve FCV-2161. '

8. Ensure FCV-2210X, Reactor Makeup valve, selector switch is in AUTO. i

9. Ensure FCV-2210Y, Bonc Acid valve, selector is in AUTO.

i

10. If blending directly to the VCT, then open V2512, Reactor Makeup Water stop valve.

I t

11. If direct path to the charging pump suction is desired, then open valve V2525, Boron Load Control Valve. [

M

Page16~of 20- . . .

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ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1-0250020. REVISION 35 3ORON CONCINTRATION CCNTROL - .40RMAL OPERATICN

8.0 INSTRUCTIONS

(continued) 8.5 (continued)

CAUTION ,..,

To preclude lifting the VCT relief valve while using V2525, do not allow the combined PMW and boric acid flowrates to exceed the running charging '

l cump(s) capacity. I

~ 2. Adjust FRC 2210X ano FRC-2210Y to the aesired flow rates.

NOTE '

, Monitor VCT tevel for increase. i I

NOTE '

The addition of Boric Acid should be completed before the PMW. such that. '

the total blend volume remaining allows for at least 30 gallons of pnmary makeup water alone. to flow through the lines and flush out any remaining I boric acid. '

i

13. When the desired amount of Boric Acid has been added, place the i selector switch for FCV-2210Y to CLOSE.

i ..

14, When the Boric Acid and water flow totalizers show that the proper i amounts have been added to the VCT, then close V2512 or V2525. which ever was used.

/

15. Place the running BAM pump switch to AUTO and ensure pump stops. 'N

16. Close FCV 2161. j

17. Close FCV-2210X.

18. Monitor for any abnormal change in temperature. Check Boronometer for undesirable change in Baron Concentration.

l l

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. QI 5-PR/PSL-1 .

r

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.: Revision 67-  ;

December,1995 i Page 92 of 101 i.

3 RGURE 4  ;

. TEMPORARY CHANGE REQUEST  !

(Page 1 of 3)

A Reference informanon- (Originator to complete)

st. Lucie Unit # PSL L TC 0 A~%~ HI l Procedure

Title:

'Goeow Cses-aarx,.a' Owr #4 - #ae m e. ObernW b Procedure Number: oP f-easwa.2m Rev. 3 5~ ~ f

Reason for change

400 Phcecutu. GwdA4CC TEE CICS 6'MoA , N dfMIt =3 l l m aa n ** rhe ens . As wnwn* m e a ~ nr.w r w. er a i of A-emsaa . tiv :s.

a Originator: E UNueenA Phone: K 'ikD69 Des:Jan/ 23 /1974 3 j B Prococural Controts- (Originator to complete)

Yes l 0 is the intent of the procedure altered? (Tech. Spec. 6.8.3.A) If yes. a TC is NOT l

! applicable. A PCR is required.  !

O g is this Temporary Change for a one. time use? If yes, this TC can be executed gap.

jl[gg,only, if no, this TC may be used up to 90 days, and the originator of the TC shall 4 suomit a procedure change request incorporating this TC at the same time the TC is 1 approved.  :

Department Head or Damgnee / .t A C.i M I M/N '

O O Is this T.C. for a Q.l.7 If yes, the Quality Manager or designee and the Dept. Head or  !'

[ designee who is junsdictionally responsible for the Q.l. shall sign.

Quality Manager or Desgnee / /

Decanment Head or Designee / / '

i- C Temocrary chance contents: (originator to completei I Does this Change:

Yes No  !

O [ Incorporate complex or extensive changes? If Yes. Subcommrttee required.

Subcommrttee O g Modifyinstrument setpoints?

O A Delete an indeoendent venfication?

O [ Alter a QC holdpoint?

O A Modify a procedural step which alters a regulatory recuirement as identdied in the

procedure?

O [ Alter the first execution of a promdure? (Preop, LO!)

O g Addition of any charnicals?

NOTE i' If any of the above entena are marked yes, pner FRG review is required.

/R6'

O Ql'5-PWPSC-1 -

~

' Revision 67-  !

December,1995 Page 93 of 101 l

1 RGURE 4.

TEMPORARY CHANGE REQUEST '

3 (Page 2 of 3)

TC # .f.-% ut7  !

I D 10 CPR 50Je Seresang yen No

i. Does me cmenge represent a change e me lonely se memormed m me SAR7 i 2.

4 Does me change represent a cannge e procesures se assoreed m me SAR? . I 3.

4.

Is me onenge asessmand une a test or essenment not desenhos in me SAR7 1

CouM me snenge eAset ressear nedely n a way not pronousy evenmens h t' ?

yegany .

X.

5. Does me ehenge recuse a change to me Tecerecei a%7 M l

- E if the answer to AM,, the apove 10 CFR 50.59 screening questions are no (Questions i

1 5), Pen a safety avaitation,is n9hrequired.

STA fewour towinesen kVI/b M/  % Date /N!

E Does es snenge- (NPS e.

j Yes No

/

i. Corr rorre.e me es,e, or,, omre of e.serne,,,,

l L Poteneedylaneses pressure '

I

3. Dedest sunomaso myises?

I

4. Defeat snennereaal or missemens Acess?

' 5. Aasr the congmeson of an evesumen aus e en opensor went eroma. #

If yes to No. 5. numannuson trarn ene Plant General Manager or She Vice Pressert ensa be cotanea.

Osas / /

4 Yes No C Prior FRG towow remaree?

NOTE

if any of th ove cnteria are marked yes. ciscuss possible alternatives with the i ongtnator. \ p)[ f h ,,

NPS Signeese M V W MJu' Dae t /"*

ra

F FnG Aeeew- V Plant Generet Manager Approval Dale J /

l FRG Nw.eer .

1No enenge shed be rewowed (if pnar FRG renew a not recurse) try sne Fansdy Renew Grous ans approved try the Pterit General Meneger mulNm 14 anye of me ausnonzemon amie. (Tech. Spec sELC)

REJECTED by FRG/ Plant Genwei Manager ' '

Dean

, Ressort r-Me It is tne en r ~^i of the ongneur of me teMmese temporary enange to cancer sne cnenge m me soproonese Conent Room, cessey as seu coons one han a3 cuesseuent evonsono unng tne temporary cnenge.

i

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QI 5-PR/PSLs1. .

Revision S7' -

. December,1995  :

- Page 94 of 101 FIGURE 4 i

TEMPORARY CHANGE REQUEST

. l (Page 3 of 3)

L  !. >

. t G TC 8 M 6-8/f  ;

^

ht: (This change shall have prior app b -

management staff.) (Tech. Spec. 6.8 ) /yg NPS and one member of the plant 1

Plant Management Sta i R W

l. Date I / /

NPS Sigusture b gnatureOw _

Authonzanon Date k /O/Iti 1

H cancellation Authonzanon *

(NPS/ANPS) Date / /

) Reason:..

~

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Page-14 of 20 _, -l

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- ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1-0250020, REVISION 35 ,r

1. .f .

BORON CONCENTRATION CONTROL - NORMAL OPERATION -~

"W C 6 -

8.0 INSTRUCTIONS

(continued) jt2 W.d .

8.4 (continued)

\

j 3. Enter the number of gallons to be added into the PMW Batch intog -

and set deaired flow rate on FRC-2210X (Makeup Water Flow).

l

' 4. Start one Primary Water Pump if not running. I L

5. Place V2512 in the OPEN position.  ;

_ 6. Place Mode Selector switch in DILUTE and observe flow indication of FRC-2210X.

7. Monitor VCT level to ensure tank does not fill up to high level alarm. For a

extended dilutions, match makeup flow with charging flow using the PMW j makeup flow controlle- to prevent over-filling the VCT while diverting letdown.

a

8. Upon completion of dilution, retum V2512 control switch to AUTO or CLOSED position.

9. Retum Mode Selector Switch to AUTO or MANUAL

, 10. Ensure that the desired reactrvity change occurs.

s\

! 3 8.5 Manual Mode of Operation

\ 1. % J Bitm.D y /,g Determine the desired volume to be added to the VCT and calculate the g proper blend ratio using the most recent chemistry boron samples of the N 1 A or 1B BAMT and the RCS, If the chemistry sample for the RCS is not

, available then use the boronometer reading.

J

o P5ge_15 of 20 $

ST. LUCIE UNIT 1 -

OPERATING PROCEDURE NO. 1-0250020, REVISION 35 BORON CONCENTRATION CONTROL - NORMAL OPERATION 4, , ,

8.0 INSTRUCTIONS

(continued) i ." . "-

4 8.5 (continued) 4 *.: 1 M SiL The following formulas can be used to determine volume and blend ratio.

} Remember to make note of the current totalizer readings.

l Volume to be added = desired VCT level % - actual VCT level % X 33.8 gal /%.

Blend ratio = BAMT Concentration divided by RCS Concentration minus one 4

BAMT-1 j RCS 1 8

p Ensure Mode Select switch is selected to MANUAL C.@ Place FRC-2210Y and FRC 2210X to manual and close FCV-FCV-2210X by taking the controller output to zero.

D 4 Ensure 1 A or 1B primary water pump is running.

4 E.@ Ensure the BAM pump recire valves V2510 and V2511 are open.

N 6 @ Start either the 1 A or 18 BAM pump.

1. @ Open the Boric Acid Makeup isolation valve FCV-2161.

( @ Ensure FCV-2210X, Reactor Makeup valve, selector switch is in AUTO.

't f-@ Ensure FCV-2210Y, Boric Acid valve, selector is in AUTO.

' 3'@ If blending directly to the VCT, then open V2512, Reactor Makeup stop valve.

Y! I x:g if direct path to the charging pump suction is desired then op ,

l V2525, Boron Load Control Vaive.

1. e- -

s.ahsn A

\

2 N b' d

. - _+- , ~ pi- - y- - m

i Pcge 16 of_20 -

ST. LUCIE UNIT 1 .l"#

• OPERATING PROCEDURE NO. 1-0250020. REVISION 35 o P.g '

BORON CONCENTRATION CONTROL - NORMAL OPERATION ' ' ' 41

' g ty$5

8.0 INSTRUCTIONS

(continued) E i

8.5 (continued) h.

t@

f' CAUTION To preclude lifting the VCT relief valve while using V2525, do not allow the E '

combined PMW and boric acid flowrates to exceed the running chargh)g  ;

pump (s) capacity.

ok '$, Adjust FRC-2210X and FRC 2210Y to the desired flow rates.

i \,

t i'

l !y li M

Monitor VCT level for increase.

NATE i i-The addition of Boric Acid should be completed before the PMW, such that, the total blend volume remaining allows for at least 30 gallons of primary makeup water alone, to flow through the lines and flush out any remaining boric acid.

M' ($ When the desired amount of Boric Acid has been adde @$Iace the selector switch for FCV-2210Y to CLOSE.

" O When the Boric Acid and water flow totalizers show that the proper O amounts have been added to the VCT, then close V2512 or V2525, which I

ever was used.

$ 5Dp.Jhru,,,a BM b~?0m/

j f O' @3 Place the running BAM pump switch to AUTO, x - __ ,

P. @ Close FCV-2161. I

',U G.S. Close FCV-2210X.

N E $ Monitor for any abnormal change in temperature. Check Boronometer for undesirable change in Boron Concentration.

l la h M Y k 0 5 *2 c-- @,5,3 g;ff 0 3 i

j

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

1 ST. LUCIE UNIT 1 I OPERATING PROCEDURE NO. 1-0250020, REVISION 35 BORON CONCENTRATION CONTROL - NORMAL OPERAT10N *

' 8.0 INSTRUCTIONS: (continued) fi 8.5 - (condnued) i

2. Manual Dilution fE2.T.E VCT level equates to 33.8 gallons per percent of scale on LIC-2226, VCT Level. '

A. Determine the desired volume of water to be added. f B.. Ensure the Make-up Mode Selector switch is selected to y MANUAL.  !

sH '

C. Ensure that FRC-2210X, Make-up Water Flow, is in h MANUAL and reduce the controller output to zero (0). 4 i

D. Ensure that FRC-2210Y, Boric Acid Flow, is in MANUAL.

O and reduce the controller output to zero (0).

i E. Ensure that FCV-2210Y, Boric Acid Valve, selector is in CLOSE.

1 lg F. Ensure that either the 1 A or the 18 Primary Make-up Water Pump is running.

G. Place FCV-2210X, Reactor Make-up, selector switch in AUTO. '

H. H diluting to the VCT Than OPEN V2512, Reactor Make-up Water Stop Viv.

l. H diluting directly to the suction of the charging pumps, 4

Iban OPEN V2525, Boron Load Control Valve.

i 1

f I

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_?- ,

ST. LUC 1E UNIT 1 OPERATING PROCEDURE NO. 1-0250020. REVISION 35 i BORON CONCENTRATION CONTROL -~ NORMAL OPGRATION

- 8.0 INSTRUCTIONS: (continued) 8.5 (continued) 2.

(continued)

CAUTION -

To preclude lifting the VCT relief valve while using V2525, do NOT allow the PMW flowrate to exceed the running charging pump flow rate.

f J. Adjust FRC-2210X to the desired flowrate.

K.

11 necessary to maintain the desired VCT level, .Than divert the letdown flow to the WMS by placing V2500,  ;

@ VCT Divert Valve, in the WMS position.

I L. When the desired VCT level is reached,Ihan-

@ 1. Return V2500, VCT Divert Valve, to the AUTO I  !

position.

M i g ' 2.

Ensure that V2500 indicates CLOSED. i Q M.

When the desired amount of PMW has been added Ihan I

n place the FCV 2210X selector switch in the CLOSE l position. j N. CLOSE V2512 or V2525, whichever was used.  !

O. 9 Ensure that FRC-2210X is in MANUAL and reduce the controller output to zero (0).

P. Monitor for unexpected results:

1. Abnormal change in the RCS temperature.

2. Undesired change in the RCS baron concentration

1. by boronmeter indication.

.l l

l 1

r

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• I ST. LUCIE UNIT 1

~

OPERATING PROCEDURE NO. 1-0250020, REVISION 35  ;

BORON CONCENTRATION CONTROL - NORMAL 0"ERATION

~

8.0 INSTRUCTIONS

(continued) '

8.5 . (continued)  ;

t

3. Manual Boration  ;

k m  :

7 VCT level equates to 33.8 gallons per percent of scale on LIC-2226, VCT  !

Level. - i y

A. Determine the desired volume of boric acid to be added.

4 B. Ensure the Make-up Mode Selector switch is selected to '

, h MANUAL.

I~

) C. Ensure that FRC-2210X, Make-up Water Flow, is in g MANUAL and reduce the controller output to zero (0).

O\

I D. Ensure that FRC-2210Y, Boric Acid Flow, is in MANUAL and reduce the controller output to zero (0).

, 0 E. Ensure that FCV-2210Y, Boric Acid Valve, selector is in

CLOSE. <

e

() F. Ensure that either the 1 A or the 18 Primary Make-up N{ 4 a

Water Pump is running.

5

! E

j While it is acceptable to use either BAMT for RCS boration, it is preferable

to operate the BAM Pump for the 3AMT NOT designated as ' Tech Spec'. ,

G. START either the 1 A or the 18 BAM Pump.

4 H. Place FCV-2210Y, Boric Acid Valve, selector switch in AUTO.

I. OPEN FCV-2161, Boric Acid Make-up Isolation.

J. 11 borating directly to the VCT, Jhan OPEN V2512, l Reactor Make-up Water Stop Viv.

b

(

t

-j. -

l ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1-0250020, REVISION 35.

j BORON CONCENTRATION CONTROL - NORMAL OPERATION i i

8.0 INSTRUCTIONS:' (continued) I 8.5 (continued) l

3. (continued)  !

. i K. H borating directly to the suction of the charging pumps, i Elan OPEN V2525, Boron Load Control Valve.

L. Adjust FRC-2210Y to the desired flowrate. .

M M. H necessary to maintain the desired VCT level, Blan divert the letdown flow to the WMS by placing V2500, i VCT Divert Valve, in the WMS position.

I  ;

N. WilBD the desired VCT level is reached, BIBn:

i

1. Return V2500, VCT Divert Valve, to the AUTO l D position. l k 2. Ensure that V2500 indicates CLOSED. .

!Q . O. WilAn the desired amount of boric acid has been added,  ;

Nl l Hign place the FCV-2210Y selector switch in the CLOSE position.

j P. CLOSE FCV-2161, Boric Acid Make-up Isolation, i

i CAUTION l

k To preclude lifting the VCT relief valve while using V2525, do NOT allow j the PMW flowrate to exceed the running charging pump flow race.

. I

'l Q. STOP the running BAM pump and place the selector l switch in the AUTO position. '

I l

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

3 >

- ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1-0250020, REVISION 35 BORON CONCENTRATION CONTROL - NORMAL OPERATION '

8.0 INSTRUCTIONS

(continued) 8.5 (continued)

{ .

. 3. (continued) '

l R. 11 flushing the CVCS piping following boration is desired,  !

h:

i 4 1. Place FRC-2210X, Make-up Water Flow, controller q in AUTO.

CAUTION g To preclude lifting the VCT relief valve while using V2525, do NOT allow the PMW flowrate to exceed the running charging pump flow rate.

2. Adjust FRC-2210X to the desired flowrate to flush the lines with a total of at least 30 gallons of  ;

PMW.

D 3. W.luta the desired amount of PMW has been h added,Iban place the FCV-2210X selector switch in the CLOSE position.

4. Place FRC-2210X in MANUAL and reduce the

\ controller output to zero (0).

S. CLOSE V2512 or V2525, whichever was used.

T. Ensure that FRC-2210Y, Boric Acid Flow, is in MANUAL and reduce the controller output to zero (0).

U. Monitor for unexpected results: '

1. Abnormal change in the RCS temperature.

, 2. Undesired change in the RCS boron concentration by boronmeter indication. '

I s

, =

l 3;

.QL5-PR/P_Sli.1 ~  ;

ie4 Rension 67  !

December,1995

• i

. Page 1 of 101  ;

r l

, q I l FLORIDA POWER & LIGHT COMPANY  !

i NUCLEAR ENERGY DEPARTMENT '

A '

i ST. LUCIE PLANT i Pn0CEDURE PRobUCTION j PREPARATION. REVISION. REVIEW / APPROVAL OF PROCEDURES

1.0 APPROVAL

I i

Reviewed by Facility Review Group 1/30 1923,,  ;

Approved by J.H. Barrow (for) Plant General Manager 2/31975 Revision 67 Reviewee by FRG '12/819 1 Approved by J. Scarola Plant General Manager 12/819,,tE ,

2.0 PURPOSE

I l

i 2.1 This procedure provides administrative guidance for the preparation, review, L approval and revision of all plant procedures and letters of instruction, for use l at the St. Lucie Plant.

l 2.2 This' procedure defines the instructions that shall be used by St. Lucie Plant personnel to assure conformance with NRC Regulatory Guides 1.33 and 1.68, NUREG-0737 and the Site Quality Manual (SOM 2.1 and 5.0).

3 m

3

?

S_,,, OPS l DATE DOCT PROCEDURE DOCN Ol+1 SYS COMP COMPLETED nM 67 i

~ . _ - _ _ _ _ _ . _ __ _ ._ . _ __ . _ . _ . . _ - _ _ _ _ _

,j

. . . . _ _ _ . ..___ _ Ol 5-PR/PSLd Revision 6T December,1995 {

Page 41 of 101 i

5.0 INSTRUCTIONS

(continued) i

'5.12 (continued)

2. Controlled vendor technical manuals may be utilized as references to i safety or non-safety related NPWOs to provide technical guidance (e.g., '

DWGs, specifications, torque values, dimensional information, i voltage / current values, etc.) to supplement an invoked plant approved j procedure / guideline or the work scope / instructions without prior FRG Review / Plant General Manager approval. In this case, the vendor's '

step-by step maintenance instructions are not being used.

l I 3. Changes to technical manuals received from the vendor or changes I initiated by FPL shall be forwarded to PEG /JB for review and approval. -

4. New technical manuals received from vendors shall be numbered and controlled in accordance with O! 6-PR/PSL-1.

1

5. The maintenance and preventive maintenance requirements specified in technical manuals shall be considered when writing maintenance procedures. Vendor recommendations for preventive maintenance  :

activities or frequencies contained in these Vendor Tech. Manuals may be

! deviated from, provided a technical review is performed by the respective

! maintenance engineering group.

6. . Distribution of revisions to vendor technical manuals shall be maintained by the information Services Supervisor or designee.

5.13 Adherence to Procedures:

1. A strict adherence to procedural requirements - Verbatim Compliance - is the policy expected and required of all St. Lucie Plant personnel.

2. A procedure shall be performed in a step by step manner, with each step ,

being completed prior to the performance of the next step, unless exceptions allowed by the procedure or as specified by this procedure.

A. Procedures and Instructions of an Administrative nature (Quality ,

Instructions, ADMs, etc.) shall not be violated, but step by step ,

implementation is not required. By nature, these types of procedures n and instructions often do not lead themselves to sequential implementation. ,

B. Procedures and instructions that are of a technical nature shall be ,

r followed sequentially except as specifically allowed by approved plant

• procedures.

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9. '

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._3 5-PR98Ln1 "._..:.~ G.~

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Revision 677 December,1995 l

. Page '42 of 101 ~!

~ 5.0 INSTRUCTIONS:'(continued)-

l 5.13 -(continued)i ,

2. (continued) -

i

- B. (continued) 1.- Required sign-offs and data entries shall be made as each step is -

performed.' -l j

l

~i

2.

If a procedure stop cannot be completed as written, or if in the _.

Judgement of the individual performing a procedure, completion of  :

a specific step (s) could result in an unsafe condition (e.g., i personnel injury, damage to equipment, conditions outside the  !

limits of the procedure etc.), conduct of the procedure shall be j stopped, the system / components placed.in a safe condition and I the Nuclear Plant Superviser shall be notified.

q

3. Deviation from Procedure Valve Checklists may be made provided the deviation is noted in ink on the applicable valve - 1 alignment and is approved (initialed and dated) by the Nuclear Plant Supervisor, l i

3. Personnel shall not give directions, guidance, recommendation, or -

clarifications which conflict with approved procedures.

4. Adherence to procedures shall be accomplished by osa of one of the following methods:

4 A. Method 1 - Procedure Present Durino Performance of Activity: The types of procedures that shall be present and referred to directly are:

$ 1. Those procedures developed for extensive or complex jobs where

{ reliance on memory cannot be trusted.

2. Tasks which are infrequently performed.

3. Tasks which must be performed in a specified sequence and/or which verification is documented by initial or signature.

4

4

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j-Revision 67  :

December,1995  :

Page 43 of 101 i

5.0 INSTRUCTIONS

. (continued) )

' 5.13 (continued)'. a B. Mei.cd 2 - Memoriva4n: Method by which the procedural' steps for ~

the required actions are committed to memory. This method does not .!

permit any deviation from the Procedural Adherence Policy, i

1. Procedures for which actions should be committed to memory are  :

Immediate Actions in Emergency Operating Procedures and Off  ;

Normal Operating Procedures.

2. Procedures for which actions may be committed to memory are i routine procedural actions that are frequently repeated and may .

not require the procedure to be present during performance of the l activity. However, copies of procedures shall be available to the  !

user at his/her work location for reference during performance of i the task, if necessary.  :

. 1

5. Procedural adherence may be accomplished by use of a Temporary Change,if necessary.

6. When used in a procedure the word "shall" is used to denote a requirement, the word "should" to denote a recommendation and the word 1 "may" to denote permission, neither a requirement nor a recommendation. '

j _ 7. Independent Verification:

A. Independent Verification has been defined in ADM-17.06,

" Independent Verification." Definitions of independent Verification

should not be added to procedures as they may conflict with the 4

guidance outlined in ADM-17.06.

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-. - - - = - - --- - - - -

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I A Page.1 oL174 --

I FLORIDA POWER & LIGHT COMPANY. I ST. LUCIE PLANT j

' ADMINISTRATIVE PROCEDURE NO. 0010120  !

REVISION 79  !

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I a F f. o ,

L 1 .0. M:

CONDUCT OF OPERATIONS fo O

• L i 1

l pRoctDURE o-2.0 REVIEW AND APPROVAL: ~

Reviewed by Plant Nuclear Safety Committee 1/1719.ZE_ l Approved by J. H. Barrow (for) Plant General Manager 1/22 1911_ l Revision 79 Reviewed by Facility Review Group 12/21 19.R5  ;

Approved by J. Scarola Plant General Manager 12/21 19.91.  !

3.0 SCOPE

3.1. Purpose

l 1his procedure defines the responsibilities and conduct of the Operatxms Department during the performance and documentation of all departmental <

activities. This procedure provides instruction to ensure that plant operations 4 are conoucted in an effective, consistent, professional and businesslike manner as per the operating license, plant procedures and applicable regulatory requirements. l This procedure applies to all persons in the Operations Department. It

• identifies operational requirements and management policies necessary to ensure the daily conduct of plant operations is consistent with good

operational and engineering practices.

S__

i DATE DOCT PROCEDURE  :

DOCN 0o1o120 l SYS COMP COMPLETED ITM 79-l i

& Page.41.of 174 -

I ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 CONDUCT OF OPERATIONS APPENDIX D CREW REllEF/ SHIFT TURNOVER (Page 5 of 5)

1. (continued)

D. Instruction for an interim or Short Term Relief / Shift Tumover.

1. If a specific watchstander requires a short term relief for a period of less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the following instructions provide the minimum requirements for shift relief:

a. General watchstation status, I

b. Off-normal conditions.

c. Tests in progmss. d

2. The applicable unrt ANPS shall be notified immediately after the shift tumover nas been completed.

3. If an individual is expected to be aosent for period of greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then an Individual Relief / Split Shift Tumover snail be performed.

3 Id: . Page.42 of 174 '

ST. LUCIE P6NT  !

ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 ~I CONDUCT OF OPERATIONS -  ;

APPENDIX E ,

NQTIFICATION OF OPERATIONS SUPERVISOR /FPL MANAGEMENT i (Page 1 of 3)

~

1. The Nuclear Plant Supervisor is responsible for. notifying' higher station authonties and appropriate station personnel. - Advance notification should be made when o

possible. The following situations require prompt, verbal notifications:  ?

Notify the Operations Supervisor for the following situations: -

A. Any event that would cause entry into an Emergency Operating Procedure 5 (EOP).

! B. Any event requiring phone call notification to the NRC.

1 C. Any event that will generate an LER.

?

- D, Inadvertent radioactive liquid or gaseous release. l l

E. Major equipment failure or malfunctions.

F. Unexplained or unplanned reactivity changes.

l ,

G. Forced power reduction.

l H. Major personnel injury or radiation overexposure. I

l. Any LCO that would require unit shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. )

J. Any operational event that generates an in House Event (IHE) Report AND causes heightened awareness to FPL sources offsite.

K. Any release that is or is potentially, damaging to the environment.

L Load restrictions or inability to meet load dispatcher requirements. This includes, but is NOT limited to the following:

1. A planned power escalation is unexpectedly halted for any reason and

)'

can not be resumed within one hour.

2. If at a power level less than 100 percent, any unexpected condition that would prevent a future power escalation and can not be resolved within two hours.

3. If at a power level less than 100 percent and the plant is unable to support an unexpected request for more oower from the load dispatcher.

~

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.j-Pcge 46;c(174' _ l j 3 ST. LUCIE PLANT . . _

l ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 -

CONDUCT OF OPERATIONS j APPENDIX F  !

LOG KEEPING  !

(Page 2 of 9); ,

i

2. .Chronoloaical Loos

e A. Log books and/or computerized logs shall be maintained at the RCO, l NO/SNPO, NTO/NPO and ANPO normal stations. Entries are to be in concise l

' ~

and complete enough to reconstruct the events of the shift. .Particular ,

j a

~ ttention should be made to the entries pertaining to any abnormal condition  !

that occurs. Times for each entry chall be as near correct as possible IJsing military time. The entries are to be made in chronological order. j

1. Evolutions, manipulations and operations that are performed, observed and monitored by operators NOT actively assuming the responsibilities of a particular watch station shall be recorded in the applicable watch station  !

chronological log'and initialed by that operator. The operator should notify  ;

y the responsible watchstander of the log entry. l

, 2. When it is necessary to insert additional information after the fact, Then the entry shall be recorded with the actual time of occurrence, the words Late Entry in parenthesis, and the information to be logged.

Example: 1234 Started the 1 A EDG for surveillance run 0827 (Late Entry) Filled the 1 A2 SIT with the 1B HPSI Pump in accordance with OP 1-0410021 1345 Secured the 1 A EDG. Surveillance run SAT.

3. When it is necessary to correct information recorded in error, then the I entry shall be recorded with the actual time of occurrence, the words

" Corrected Entry" in parenthesis, and the information to be logged.

i Example: 1234 Started the 1B EDG for surveillance run l 1345 Secured ths 1 A EDG. Surveillance run SAT.

1234- (Corrected Entry) Started the 1 A EDG for  !

surveillance run

4. Entries in the RCO log should include, but are NOT to be limited to, the j

[ following:  !

, a. Conditions at the beginning of each watch.

1

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i Page 4Tof 174 . . . _

ST. LUCIE PLANT  !

ADMINISTRATIVE PROCEDURE NO. 0010120.~ REVISION 79.

CONDUCT OF OPERATIONS APPENDIX F LOG KEEPING  :

(Page 3 of 9)  !

2. Chronolooical Loos: (continued)

A. (continued) -

4. (continued)

b. Significant changes in plant conditions.

Examples: 1. Mode changes.

2. Loao changes.

J

3. Reactivity changes. l l

4. Startups and Shutdown.

'l l

5. Time of Reactor enticality. j l

c. Any new condition that would limit unit generation. j Examples: 1. Condenser back pressure at administrative limits.

2. Chemistry parameters limiting operation,

d. Special tests, including periodic and surveillance testing, for major equipment.

Examples: 1. Start and stop times for periodic or surveillance tests and outcome (SAT or UNSAT), for major equipment.

2. Post maintenance testing and outcome, for major '

equipment.

e. Control problems associated with major equipment or systems.

Examples: 1. Changes in plant work arounds.

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Page 70'of 174- l

.I ST. LUCIE PLANT L ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 j CONDUCT OF OPERATIONS - . !,

APPENDIX M '!

PROCEDURAL COMPLIANCE AND IMP 8 MENTAT10N (Page 1 of 6)-

t

1. . Controlled procedures are available in both Control Rcoms and shall be '

' implemented and complied with in accordance with the instructions provgied in ,

, 015-PR/PSL-1, ? Preparation. Revision, Review / Approval of Procedures."

2.

~

In the event of an emergency where procedural guidance does NOT exist or in 5

- which a specific emergency is NOT addressed by an approved procedure, then ~

Operations personnel shall take action to protect the health and safety of the public, .

minimize personnel injury, and damage to the facility.

t 1

3. Numerous tasks performed by the operators are repetitive and routine in nature.

i These tasks come under the guidance of the memorization method of adherence to  ;

procedures in accordance with O! 5 PR/PSL 1, " Preparation, Revision. l Review / Approval of Procedures," and may be performed from memory. These '

tasks, which are listed in the following sections,' are ~ considered to be skill of the trade for qualified operators. Each listed task shall have on2 or more of the below justification reasons:

t (A) Task is routine and not complex - satisfactory completion assured by 4

routine training and observation.

(B) Task is routine and has a low level of complexity - satisfactory completion assured by completion of verification checklist and independent verification,

, (C) Posted instructions in place as reference.

(D) Satisfactory completion assured by multiple levels of review and/or feedback from system.

A. General Control Tasks

1. Racking IN and OUT of 6.9 KV,4.16 KV, and 480V breakers. (B)

2. Tuming ON and OFF 480V MCC breakers. (D)

3. Writing clearances and NPWOs. (A,D) 7 .

4. Changing chart paper. (A,D)

5. Placing controllers in MANUAL or AUTO. (A,D) t 4 --

e , w - . -

- . . . - . - -- . - .~ .

Page.71 ~of 174 '  ;

ST. LUCIE PLANT ,

ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 _

CONDUCT OF OPERATIONS -'

i APPENDIX M f PROCEDURAL COMPLIANCE AND IMPI NNTATION (Page 2 of 6) ,

1. (continued)'

2 B. . Reactor Control Oper' ator

1. Divert Letdown to Control VCT leve!. (A,D) ,

t

2. Check Sheet 1 of AP 10010125. (A,B,D) l l 3. Refueling Operations '- movement of machine, etc. (A,D) [

4. Adjusting Main Generator loading ~, including Megavars and Megawatts 3

3 (manipulation of DEH controls). (D)  :

i

5. Swapping Auxiliary and Start-up Transformers. (D)

6. Adjusting CEA position (eg. ASI control). (D)

)

3 7. Manipulation of control valves (ADVs. FCVs) to control Heatup and l Cooldown rates. (D) j

8. Pumping down Reactor Drain Tank. (A,D) l 4

9. Placing CST on recire. (A D)

C. Senior Nuclear Plant Operator

1. Generic Rounds Sheets. (A)

2. Swapping HUTS. (A,D)

3. Blowing down BAMT level transmitters. (C)

4. Operator Readings and AP 0010125 checks. (A,B,D)

5. Recirculating of HUTS, WMTs, and AWSTs. (A,D) 6.' Backwashing ICW/CCW strainers. (C) l l

1

QI 5-PR/PSL-1

. . p- 7

• December,1995 Page 92 of 101 FIGURE 4 TEMPORARY CHANGE REQUEST (Page 1 of 3)

A Reference information:- (Originator to complete)

St. Lucie Unit # common TC # ' O- M - 0/4 Procedure

Title:

toan set or opce/ re e s 5 A# 00 / 0 / ~2 o Rev. M' Proceours Number:

Reason for change: .mmew( n a aa c raa- n,wmcs 9,s s - rc $sPercictf rt 0 - %, - o s t Originator: o "IA e w /C Phone: 704/ Date: / / A 9/ 96 B' Proceoural Controts: (Originator to complete)

Yes No O E is the intent of the proceoure attered? (Tecn. Soec. G.8.3.A) If yes. a TC is NOT applicable. A PCR is recuireo.

O E is this Temporary Change for a one-time use? !f yes, this TC can be executed gn.e time only. If no, this TC may be used up to 90 days, and the onginator of the TC shall submit a procedure enange reauest incorporating this TC at the same time the TC is approved. /

Department Head or Designee K- - / /29/'I0 O E is this T.C. for a 0.1.7 If yes the Quality Manager or designee and the Dept. Head or designee wno is junsolctionally responsible for the 0.1. shall sign.

Quality Manager or Designee / /

Department Heae or Designee / /

C Temocrary cnance contents: (originator to complete)

Does this Change:

Yes No O E incorporate complex or extensive changes? If Yes. Subcommittee reouired.

Subcommmee initials O 5 Modify instrument setpoints?

O E Delete an indepenaent venfication?

O 3. Alter a QC holdpoint?

O O Modify a procedural step whien alters a regulatory reautrement as identified in tne proceoure?

O S Alter the first execution of a procedure? (Preop. LO!)

O G Addition of any chemicals?

NOTE If any of the above entena are marked yes. pnor FRG review is required.

/R67

QI 5-PR/PSL-1 Revision 67

? December,1995 Page 93 of 101 FIGURE 4 TEMPORARY CHANGE REQUEST -

(Page 2 of 3)

TC # 0 -% ~ M 0 1o cFR so.se screemne vos No .

' Does me change represent a change to Ine inceity as oseenned m the SAR7 1.

2. Does me enenge represent a enenge to procedures as ossented m sne SAR7 .

3. Is me enenge assocated with a test or exoonment not seecnces m Ine SAR7 /

! 4 Could the enange affect nucisar safety e a way not previousy evanaiso m 7 tne SAR? ,

l S. Does ine enange focuire a enange to tne Tectncal Specificanons? /

N,j,I[

If the answer to A,.j,k the above 10 CFR 50.59 screening questions are no. (Questions 1 5), then a safety evaluation is not recutrea.

STA rewow tsignaturei AMS Date I 'dMr _

Does rus enange: INPS to comsfiese") Yes No E

1. Comoromme me seoaraton of redundant trams of souernent?

2. Potonnally isomie pressure roiefs? /

t/

3. Defeat automanc agnais?

4. Deeest mecnancal or emeincel intenocua?

/

Alter sne como6eton of an evolueen oue to an operator woric arounc. V 5.

If yee to No. 5. auenonzason from the Plant General Manager or Site %ce Preseoent snail be octamed Data r I Yes No C Pnor FRG towow reouired?

N_pQIg if any of the aDove enteny are marked yes, ciscuss cossible attematrves with the Onginat0T. 4 // / / W/ fS NPS Signature #M//~Tl Date F FRG Revow:

Plant General Manager Approval Dase _' ,J FRG Numoer - TNs enange snad be reviewed (if pnor FRG revow e not retured) by the Facurry Review Group and approvec by the Plant General Manager vnown 14 asys of the auinonzaton case. (Tech. Socc. 6.8.3.C)

REJECTED by FRG/ Plant GenereJ Manager Date ' /

Reason:

Retum to Ongmator it is tne responseility of tne ongiator of me rotected temporary enange to cancet the enange m tne approonate Control Room. oestroy ad Reed copes anc natt as sucescuent evoeupons usmo tms temporary change

QI 5-PR/PSL-1_ .. ,_

c Revision 67'

- December,1995 Page 94 of 101 FIGURE 4 TEMPORARY CHANGE REQUEST (Page 3 of 3)

G Tc a 0 - % - M ApArgvat:- (This enange shall have pnor approval by a NPS and one member of the plant management staff.) (Tecn. Spec. 6.8.3.8) .

Plant Management Staff Si tur , @ 0*f 7[/ "

~ Date / /.??/96 ,

NPS Signature Authonzaton Date / /z f i96 H Cancellation Autnenzacon (NPS/ANPS) Date / / i Reason:

e , ,e -, e- +, - , - -

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

Page-30 cf 474- ~

! l ST. LUCIE PLANT ,

ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 CONDUCT OF OPERATIONS l APPENDlX B ,

SHIFT OPERATIONS POLICIES (Page 5 of 8)

'4.. (continued) ,

'A. (continued)

?

4. P - Prove

a. Prove to yourself that the actions that were just performed produced

' the desired results.

b. Observe and verify the following: .

b '

, L'n\ 1. The task was performed correctly. ,

/- '

c-

'9

2. The actual response was the expected response.  ;

,6 3. The component / system is in the prcper configuration to support s

bQ the intended operation.

3

/4 47 4. The proper component was operated.

Y _-

Hlum mapula 5.

N 7 A. Only licensed operators are.)gmut4%anipulate the controls that directly affect the preaower level of a reactorwucegfor training purposes. A t eeinty manipulate controls only under direct visual supervisign of a licensed operator. ' N

6. Unit Reliability.

t

' A. The NPS/ANPS should make every effort to prevent putting the plant in a situation where a single f ailure would jeopardize plant safety or availability.

1 Systems listed under AP 0010142, " Unit Reliability - Manipulation of Sensitive Systems" warrant particular attention.

M.sintenance or testing should not be allowed on an in-service train or channel with the opposite train out-of-service or another channel in Trip, except for

' Tech. Spec. required surveillances or to prevent a plant shutdown.

i

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~ '

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l

' APPENDIX B.  !

SHIFT OPERATIONS POLICIES {

i l

f

, 5. Reactnrity Manipulations j I A. Reactivity manipulations in the course of normal plant operations is defined as the insertion of positive and negative reactivity due to manipulation of the

- following

j i

1. CEA insertion and withdrawal.

i '2. . Addition of water and/or boric acid to the VCT or Charging Pumps' suction. [

4-

3. - Turbine / Generator load changes. ,

i i

4. Placing a purification lon Exchanger in service, (any time V2520, "lon j Exchanger Bypass Valve," position is changed from bypassing the ion l l- exchanger (s) to directing flow through the ion exchanger (s)).

B. All reactivity manipulations in the course of normal plant operations, both l

, positive _ and negative, shall have prior approval from the SRO fulfilling the role of the Control Room Command function, except as provided for in step 5.D.

C. When reactivity manipulations are being performed, both positive and )

negative, the SRO fulfilling the role of the Control Room Command function i shall directly supervise the manipulation and additionally assume the role of a i i reactivity manager, except as provided for in step 5.D.

D. In the event of off-normal and emergency con'ditions, Reactor Control

Operators are authorized to perform reactivity manipulations without the

' presence of and approval of an SRO, if in his/her judgement immediate

, intervention is required to protect the health and safety of the public and/or challenging of plant safety functions. The SRO fulfilling the role of the Control Room Command function shall be notified of the manipulation as soon as possible.

1 E. . Crew Relief / Shift Tumover shall NOT take place for Reactor Control , 1 Operators or the Assistant Nuclear Plant Supervisor while reactivity manipulations are in progress.

i

'I

TC (' - 9 (s - OIY APPENDIX B SHIFT OPERATIONS POLICIES ,

5. (Continued) i F. Reactivity manipulations shall be performed only by those individuals .

possessing an active license applicable to the unit on which the manipulation is being performed. The only exceptions are persons reactivating a license or in a bonafide training role in pursuit of obtaining a license; they may perform reactivity manipulations under direct visual supervision of a licensed operator with an active license.

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P ge-40 of174 _

l ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 CONDUCT OF OPERATIONS APPENDIX D CREW RELIEF / SHIFT TURNOVER (Page 4 of 5)

1. (continued)

C. Instructions for an Individual Relief / Split Shift Tumover

~

1. If a specific watchstation shift is being split t:y two individual watchstanders, then the following instructions provide the minimum requirements for shift relief:

a. The off going watchstander shall review applicable plant log sheets to determine the existence of any off normal condition or trends.

' , ; L' b. The off-going watchstander shall complete the applicable Tumover

- Check Sheet (Data Sheet 1) for their watchstation.

@ c. The off-going watchstander shall verbally transmit and explain the

'~ information as recorded on their applicable Tumover Check Sheet

1. (Data Sheet 1) to the on-coming watchstander.

z g f. The on-coming watchstander shall review the following and c

k acknowledge that review by initialing Check Sheet 1 of AP 1(2)-0010125, " Schedule of Periodic Test. Checks, and g)>'@'

Calibrations.'

y

1. Applicable Watchstation Chronological Log.

2. Applicable Watchstation Operator Log Readings.

3. Night Order Book.

4. NPWO, ANPS, and NWE shall review equipment out-of-service log.

The applicable unit ANPS shall be notified immediately after the shift

'6.

b tumover has been completed.

[

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. .. . . . . . _n i

.- ~T C 0 - 9(, - 014 l APPENDIX D  !

CREW RELIEFISHIFT TURNOVEM )

I

1. l l

C. l 1

1. l

d. On-coming and off-going control room watchstanders shall conduct a face-to-face complete walkdown of the RTGBs and control panels.  ;

e. The on-coming watchstander shall make a chronological log ently indicating he/she has assumed the responsibilities of the watchstation.

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Page 41Tf 1742-

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ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 CONDUCT OF OPERATIONS APPENDIX D '

CREW RELIEF / SHIFT TURNOVER (Page 5 of 5) 1

1. (continued)

D. Instruction for an interim or Shon Term Relief / Shift Tumover.

1. If a specific watchstander requires a short term relief for a period of less

' than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the following instructions provide the minimum requirements for shift relief:

'~

4

,0 a. General watchstation status.

I b. Off normal conditions.

g$ c. Tests in progress. '

& jr , / ~"?-

3_ 2. The applicable unit ANPS shall be notified immediately after the shift tumover has been completed.

ga(

3. If an individual is expected to be absent for period of greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then an Individual Relief / Split-Shift Tumover shall be performed.

[

l l

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APPENDIX D l CREW RELIEFISHIFT TURNOVER 1.

D.

1.

d. Control room watchstanders with the responsibility of the Operator at the Controls or the Control Room Command function shall conduct a face-to- .

face complete walkdown of the RTGBs and control panels with the individual assuming their responsibility.

4 4

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Uedated Der Amendment 134 dated 3/15/95 DPR-67

,e- Page 1 W . W:;i %

7, FLORIDA POWER & LIGHT COMPANY QOd[y 3 -

~

y h$i ,

DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1

~

FACILITY OPERATING LICENSE f PRODUCnON <

1. The Nuclear Regulatory Commission (the Commission) having found that:

A. The application for license filed by Florida Power &

Light company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions's rules and regulations set forth in 10 CFR Chapter 1 and all required notifications to other agencies or bodies have been duly made; B. Construction of the St. Lucie Plant, Unit No. 1 (facility) has been substantially completed in conformity with Construction Permit No. CPPR-74 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the commission; I

l D. There is reasonable assurance: (i)' that the activities authorized by this operating license can be conducted j without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the commission; E. The licensee is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the commission; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the commission's regulations; I G. The issuance of this operating license will not be I

inimical to the common defense and security or to the l health and safety of the public;  ;

- - ~-. - . - . --- --

, e ,

s i Uodated Der Amendment 134 dated 3/15/95 DPR-67 l p 'Page 3 l

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time i byproduct, source and special nuclear material as 1 sealed neutron sources for reactor startup, sealed  ;

sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (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 physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 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 following Commission regulations in 10 CFR Chapter I: Part 20, Sections 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below; (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2700 megawatts (thermal), provided that the construction items, preoperational tests, startup tests, and other items identified in Enclosure 1 to this license have been completed as specified in Enclosure 1. Enclosure 1 is an integral part of, and is hereby incorporated in this license.

(2) Technical Snecifications l The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 134 are hereby incorporated in the license. The l licensee shall operate the facility in accordance I with the Technical Specifications.

l l-

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DEFINITIONS kE RATED THERMAL POWER j ., e

_ ,~ - /Te th rea t o to O t- ,

W Y

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TI shall'$rthetimeintervalfrom when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

i REPORTABLE EVENT 1.27 A REPORTASLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHIELD BUILDING INTEGRITY 1.28 SHIELD BUILDING INTEGRITY shall exist when:

a. Each door is closed except when the access opening is being used for normal transit entry and exit;

b. The shield building ventilation system is in compliance with Specification 3.6.6.1, and

c. The sealing mechanism associated with each penetration (e.g.,

welds, bellows or 0-rings) is OPERABLE.

I SHtITDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be suberitical from its present condition assuming all full-length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn. e ,

SITE BOUNDARY 1.30 site Boundary means that line beyond which the land ar-property is not owned, leased, or otherwise controlled by the-licenses.

SOURCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

ST. LUCIE - UNIT 1 1-6 Amendment No.27.32.59.55.g.125

y g y n_-

. . . . a.

/

• y TEST BASIS shall consist of:

c

[ test schedule for n systees, subsystems, trains or other signated components obtained by dividing the specified at interval into n equal subintervals, and X

The testing of one system, subsystem, train or other designated fcomponent at the beginning of each subinterval.

p -! ,

L POWER shall be the total reactor core heat transfer rate to tc,r coolant.

'ONIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED E or CONTROLLED LEAXAGE.

t

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0

/1.35 Unrestricted area means an area, access to which is j neither limited nor controlled by the licensee.

t

! / UNR000ED INTEGRATED RADIAL PEAKING FACTORr - F i

P 1.36 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.

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, 9 's 1-7 Amendment No. 50,50, 100 . 1 ST. LUCIE - UNIT 1 g

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v, TEST BASIS shall consist of:

[kest schedule for n systems, subsystems, trains or other signated components obtained by dividing the specified est interval into n equal subintervals, and M

}Thetestingofonesystem, subsystem,trainorotherdesignated p ' component at the beginning of each subinterval.

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L POWER shall be the total reactor core heat transfer rate to ctor coolant.

ONIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED E or CONTROLLED LEAXAGE.

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lfl.35 Unrestricted area means an area, access to which is neither limited nor controlled by the licensee.

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!? UNRODDED INTEGPATED RADIAL PEAKING FACTORr - F j J O' 1,36 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is.the ratio of the peak

f pin p5wer to the average pin power in an unrodded core, excluding tilt.

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l 1-7 Amendment No. 00 ,00 , ',00 . I ST. LUCIE - UNIT 1

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