ML20137R236

Informs That IA Number 96-019 for Operator Involved in St Lucie Dilution Issue & Discusses Whether Separate EA Number Needed

ML20137R236
Person / Time
Site:	Saint Lucie
Issue date:	03/28/1996
From:	Linda Watson NRC
To:	Boland A, Long A, Uryc B NRC
Shared Package
ML20137R112	List: IR 05000335/1996003 ML20137R106 ML20137R236 ML20137R253 ML20137R297 ML20137R317 ML20137R468 ML20137R544 ML20137R556
References
FOIA-96-485 IA-96-019, IA-96-19, NUDOCS 9704140069
Download: ML20137R236 (46)

Text

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From: Unda Watson To: ATb, ARL, BXU ,

Date: 3/28/9611:24am  !

Sut$ect: St. Lucie IA No. l 1

I got the IA number (IA 96 019) for the operator involved in the ST. Lucie dilution issue .

and put it in the package. Both documents are sdll in Ebneter's ofRce. Hellan said she -i mendoned them to him before Current Events. I have revised the letters to include date -  ;

and " signed by" notes and a printout is on my desk for the Anal version. When I called  ;

' Dawn, she indicated we needed an EA number for the operator. This is not what Joe Gray said last week. He indicated no EA number would be used. Only the IA number. Dawn will call us if a separate EA number is pulled for the operator.

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9704140069 970404 PDR FOIA  !

BINDER 96-485 PDR ..

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

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I U.S. Nuclear Regulatory Commission 101 Marietta St., N.W.

Suite 2900

[

Atlanta, GA 30323 No: II 96 36 FOR IMMEDIATE RELEASE

Contact:

Ken Clark (404) 3315503 (Friday, March 29, 1996)

Roger Hannah (404) 331-7878 NRC STAFF PROPOSES $50.000 CIVIL PENALTY AGAINST ST. LUCIE NUCLEAR POWER PLANT The Nuclear Regulatory Commission staff has proposed a $50,000 civil penalty against Florida Power & Light Company for alleged violation of NRC safety requirements at the St. Lucie nuclear power plant, located on Hutchinson Island near Ft. Pierce, Florida.

NRC officials said the fine is being proposed because a Unit 1 control room operator on January 22, 1996 failed to follow procedures for diluting the boron concentration in the reactor coolant system, causing reactor power to rise above authorized limits for a short period of time.

Boron is used in reactors to absorb neutrons and hel] control the fission process. As reactor fuel ages, boron concentrations are diluted to help maintain operating power levels.

The NRC said the operator was diluting reactor coolant in a procedure requiring the addition of from 25 to 40 gallons of water which should have taken i less than a minute to perform. Instead, the operator and other crew members

/

conducted an inadequate watch turnover during which a temporary relief operator l and the senior reactor operator were unaware that a boron dilution was in progress. This resulted in an unplanned reactivity increase since the operator failed to stop the addition of primary makeup water until approximately 400 gallons were added. l NRC officials said the actual safety consequences of the event were low l  !

because the operator recognized the error, and the crew took prompt actions to ,

restore plant parameters. However, they said the event demonstrated operator l performance problems because (1) the method routinely used by St. Lucie operators l to dilute reactor coolant was not authorized by procedt ces: (2) the metbod used l was not as described in an updated plant Final Safety Analysis Report: (3) operators routinely performed the dilution procedure from memory instead of referring to written procedures as required: and (4) o mrators failed to give i prompt verbal notification to the Operations Superv sor that an unplanned l reactivity change had occurred.

The company has 30 days from receipt of the Notice of Violation to either pay the fine or to protest its imposition.

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2 1 b.. Inadequate design control, in that Unit 1 procedures for adding a j 1 mixture of domineralized water and boric acid to the reactor coolant system in manual and directly to the suction of the j .

charging pumps)(did not implement the procedure as stated in the -

FSAR, Chapter 15; (in automatic and to the VCT) and had not done so since before Unit I was licensed. ,

c. Inadequate 10 CFR 50.59 evaluation, in that the licensee made a . -

- change to the Unit I dilution procedure on January 23, 1996 (after the event), to allow adding pure domineralized water in manualcand directly to the suction of the charging pumps, that was different  ;

from the procedure as stated in the FSAR, Chapter 15 (in automatic and to the VCT) without a 10 CFR 50.59 safety evaluation. - l Part 55 Licensees: No official enforcement action, but the NRC will ask the licensee to bring three licensed operators from the event (the NPS, 4

' board R0, and desk RO) to the enforcement conference with the utility.

Also, the staff is considering sending letters to the three operators expressing NRC concern with their actions.  !

3. - Soecial Insoection and FSAR Review Repion II was notified of this event at.approximately 10:00 a.m. on

Monday, January 22, when the licensee delivered a copy of the In-House

' Event Report to the NRC residentiinspector. At the time, RII had an ongoing corrective action program inspection at the site including

' region based inspectors R. Schin, M. Thomas, and L. Moore. On Thursday, January 25, RII management organized a special event followup inspection 4

- to begin on Friday, January 26, and continue through the weekend until completed. The special inspection included lead inspector R. Schin plus Turkey Point resident inspector B. Desai and St. Lucie acting resident i

inspector S. Sandin. The special inspection exit interview was conducted at 10:00 a.m. on Tuesday, January 30.

The inspectors included FSAR review in the inspection plan, and B.

Desai's review of the FSAR identified that the licensee's operating procedures for boron dilution were not consistent with the FSAR Chapter i

15 accident analysis procedure for boron dilution. Further review of this issue resulted in proposed violations b. and c. above. At the exit interview .the licensee had seven dissenting comments to this finding.

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.i Page 91 of D4l"

$ ST. LUCIE PLANT

1 ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 CONDUCT OF OPERATIONS

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l$ i Undated ner Amantiment 134 dated 3/15/95 DPR-67 h Page 1 1 1

FLORIDA POWER & LIGHT COMPANY  !

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DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 l FACILITY OPERATING LICENSE ,

LN PRODUCMON ,  !

1. The Nuclear Regulatory Commission (the Commission) having .

,found that:

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, A. The- application for license filed by Florida ' Power & l t Light Company (the licensee) complies with the standards '

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and requirements of the Atomic Energy Act of 1954, as

amended (the Act), and the Commissions's rules and j j regulations set forth in 10 CFR Chapter 1 and all required notifications to other agencies or bodies have ,

been duly made I

2

! 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; i i 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; D. There is reasonable assurance: (i) that the activities  ;

authorized by this operating license can be conducted without endangering the health and safety of the public, i and (ii) that such activities will be conducted in 5 complinnce with the rules and regulations of the

commission;

a

!' E. The licensee is technically and financially qualified to engage in the activities authorized by this operating 4 license in accordance with the rules and regulations of 1 the Commission; F. The licensee has satisfied the applicable provisions of

, 10 CFR Part 140, "Finanrial ivotection Requirements and 1 Indemnity Agreements," of the Commission's regulations; G. The issuance of this operat4.ng license will not be inimical to the common defenso and security or to the health and safety of the public; 9

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!A Undated ner Amendment 134 dated'3/15/95 DPR  ;

'Page 3 (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and une at any time

- byproduct, source and special nuclear material as I sealed neutron sources for reactor startup, sealed sources for reactor. instrumentation and radiation i

monitoring equipment calibration, and as fission 4

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 i required any byproduct source or special nuclear i material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactiva

! apparatus or components; l'

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and i

special nuclear materials as may be produced by the

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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 i i

j 50.59 of Part 50, and Section 70.32 of Part 70; and is l subject to all applicable provisions of the Act and to l the rules, regulations, and orders of the Commission now ,

or hereafter in effect; and is subject to the additional l

l conditions specified or incorporated below; Mmvimum Power Level l

(1)

The licensee is authorized to operate the facility {

i

' at steady state reactor core power levels not in )

i excess of 2700 megawatts (thermall, provided that t

the construction items, preoperational tests, l

startup tests, and other items identified in ,

Enclosure 1 to this license have been completed as l specified in Enclosure 1. Enclosure 1 is an  ;

' integral part of, and is hereby incorporated in l this license. l I

(2) Technical snacifications 9 contained in

• . The: Technical Specifications Appendices A and B, as revised through Amendment i i '

' No.'134 are hereby incorporated in the license. The 4

licensee shall operate the facility in accordance

' with the Technical Specifications.

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DEFINITIONS RATED TFQMal POWER j i 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.

6 REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

4 i

REPORTABLE EVENT

- I 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section

, 50.73 to 10 CFR Part 50. l I

l 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; l

1- l

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

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

welds, bellows or 0-rings) is OPERABLE.

i-l SHUTDOWN MARGIN 1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which l the reactor is suberitical or would te suberitical from its present condition  !

i assuming ali full-length control element assemblies (shutdown and regulating)  !

are fully inserted except for the single assembly of highest reactivity worth 4

which is ar.sumed to be fully withdrawn.  !

• I s.

4 SI_TE BOUNDARY 1.30 site Boundary means that line beyond chich the land or- l i

property licensee.

is not owned, leased, or otherwise controlled by the- l 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.27.32.55.55.g,125 i

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DEFINITIONS

. ........... ............................. ..... ........ . l STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of: ,

a. A test schedule for n systems, subsystems, trains or other  ;

designated components obtained by dividing the specified {

test interval into n equal subintervals, and

, b. The testing of one system, subsystem, train or other designated

- component at the beginning of each subinterval. l

' j THERMAL POWER .

1.33 THERMAL POWER shall be the total reactor core heat transfer rate to l the reactor coolant. '

UNIDENTIFfED-LEAKAGE 1.34 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED ]

LEAKAGE or CONTROLLED LEAKAGE. i

! UNRESTRICTED AREA )

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

i i

UNR000ED INTEGRATED RADIAL PEAKING FACTOR - F P i 1.36 The UNR00DED INTEGRATED RADIAL PEAKING FACTOR is.the ratio of the peak j

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

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1-7 Amendment No. 00,00, .00,12! l ST. LUCIE - UNIT 1 l

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'15.2.4- CHIMICAL AND VOL1HE CONTROL SYSTDI MALyUNCTION - BORON' DILUTION EVENT

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15.2.4.1 Identificatio af causes -

The chealcal and volume control system (CVCS) described in Section 9 3.4

- regulates both the chemistry and the quantity of coolant in the reactor i . coolant system. Changing the boron conce~ntration in the reactor coolant 7

. system is a part of normal plant operation, compensating for.long-tera

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reactivity effects, such as fuel burnup, xenon buildup and decay, and plant

startup and cooldown. For refueling operations, borated water is supplied from the refueling water tank, which assures adequate shutdown margin. An. '

insdywrtent boron dilution in any operational mode adds positive reactivity, produces power and possibly temperature increases, and, in Modes 1 and 2  ;

(startup and power operations) can cause an approach to both the DNBR and CTM

. limits. 1

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lioron dilution is conducted under strict administrac'ive procedures which specify permissible limits on.the rate and magnitude of any required change in boron concentration. Boron concentration in the reactor coolant system can be 1

decreased either by controlled addition of unborated askaup water with a corresponoing removal of reactor coolant (f eed and bleed) or by using the deborating ion exchanger. The deborating. ion exchanger is normally used for j 3 boron removal when the boron concentration is low ((ppa) and the J feed-and-bleed method becomes inef ficient. A boronometer is located in a line i

upstream of the deborating and purification ion exchangers in the CVC5. This

! instrueent provides a continuous measure of boron concentration and high-low boron concentration alaras.

7 During normal operation, concentrated boric acid solution is mixed with

! desineralized makeup water to the concentration required for proper plant j F operation and is automatically introduced into the volume control tank in .

response to a low water level signal free the volume control. To effect boron

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dilution, the makeup controller mode selector switch must. be set to " Dilute' f,i l

and the domineralized water batch quantity selector see to the desired quantity. When the specific amount has been injected, the desineralizer water Qli

[ control valve is shut automatically.

I Dilution of the reactor coolant can be terminated by isolation of the askeup j water system, by stopping either the askeup water pumps or the charging pumps, I or by closing the charging isolation valves. A charging pump must be running in addition to a makeup water pump for boron dilution to take place.

F The CVCS is equipped with the following indications and alarm functions, which will inform the reactor operator when a change in boron concentration in the reactor coolant systen may be occurring:

a) Boronometer high and low alarms and concentration indication b) Volume control tank le. vel indication and high and low alarms i-15.2.4-1 8

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c) Makeup flow indication and alaras

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d) Volume control tank isolation. ,

Otanges in boron concentration while the reactor is on automatic control at

. full power are compensated for by repcsitioning the CEA's. hwever, to assist -

the reactor operator in maintaining an adequate shutdown margin, CEA insertion

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below a position that would provide a minimum of one percent ' shutdown margin *

(assuming one stuck CEA) is accompanied by control room alarms. Because of -

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the procedures involved and the numerous alarms and indications available to the operator, the probability of a sustained or erroneous dilution is very-low.

i 15.2.4.2 Analysis of Effects and Consequences ,

15.2.4.2.1 Method of Analysis ,

. The time required to achieve criticality from a suberitical condition due to

. boron dilution is based on the initial and critical boron concentrations, the

- boron reactivity worth, and the rate of dilution. Reactivity increase rate @

due to boron dilution are based on the boron worth and the dilution rate. ,

cases have been analyzed f or all six operational modes, i.e. , power operation, startup, hot standby, hot shutdown, cold shutdown, and refueling.* In each

- case, it is assumed that the boron dilution results from pumping unborated domineralized water into the reactor coolant system at the maximum possible rate of 132 gym (3 x 44 gym per charging pump) snd that the boron concentrations are uniform at all times.

The boron dilution rate is calculated by CESEC f or all cases except dilution during refueling. CESEC described in Section 15.1.4-1 divides the reactor #.

coolant system into 15 control volumes with the continuity equation beia* y., , :

satisfied by all nodes. The charging rate of non-borated water and the FrJiE lj i

content of the system are inputs to CESEC. The maximum dilution rate , t ,i 8

(10.5 pps/ minute) occurs at the initiation of the transient. Per dilution ,

during refueling the reactor coolant system is assumed to be one control .o volume with the boron concentration calculated by: the time rate of chansa a,E boron equals, flow in times the boron concentration 1minus flow out times boron-concentration.

The uniformity of the boron concentration can be assured for the different modes of operation as follows:

a) During refueling Prior to cooldown, the resetor coolant system boron concentration is increa.ed to a miniaua of 1720 ppa. The boron is mixed by the reactor

< coolant system pumps. Because the boron is chemically dissolved in the resctor coolant , it will not precipitat e. The only possible means of ,

obtaining a nonuniform solution is by the addition of domineralized '

water via the charging pumps. hwever, because the maximum water l e An additional boron dilution event would be via the Iodine Removal Systes (NaOH spray additive). This event is not governing, however.

See Reference 42.

15.2.4-2

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. - . ._ Page_1 oL174 _

!" FLORIDA POWER & LIGHT COMPANY ST. LUCIE Pl. ANT

~ ADMINISTRATIVE PROCEDURE NO. 0010120 REYlSION 79 PSL f

1 0 1.0 TQ4

0

• l CONDUCT OF OPERATIONS j

2.0 REVIEW AND APPROVAL

!

l Reviewed by Plant Nuclear Safety Committee 1/17192E.

!- Approved by J. H. Barrow (for) Flant General Manager 1/22192E_ .!

1 l l Revision 79 Reviewed by Facility Review Group 12/21 19.95.  !

i Approved by J. Scarola Plant General Manager 12/21 19.2E_ l 4

3.0 SCOPE

l

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3.1 Purpose

This procedure defines the responsibilities and conduct of the Operations Department during the performance and documentation of all departmental activities. This procedure provides instruction to ensure that plant operations f,

are concucted in an effective, consistent, professional and businesslike manner as per the operating license, plant procedures and applicable  ;

regulatory requirements.

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.

. i 4-oo  !

. s_._ OPS i DATE DOCT PROCEDURE l DOCN Ooio12o SY3 >

COMP COMPLETED

. ITM 79

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, (n Page 41 of-174 -

ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 CONDUCT OF OPERATIONS APPENDIX D CREW RELIEF / 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. l l

b. Off-normal conditions. l

c. Tests in progress. .

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

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.

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~Paga 42~of 174" ~

l' l- ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 CONDUCT OF OPER/TIONS APPENDIX E NOTIFICATION OF OPERATIONS SUPERVISOR /FPL MANAGEMENT (Page 1 of 3)

1. The Nuclear Plant Supervisor is responsible for notifying higher station authorities

'and appropriate station personnel. Advance notification should be made when possible. The following situations require prompt, verbal notifications:

Notify tho' Operations Supervisor for the following situations:

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

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

C. Any event that will generate an LER.

D. Inadvertent radioactive liquid or gaseous release. j 1

E. Major equipment failure or malfunctions.

F. Unexplained or unplanned reactivity changes, j G. Forced power reduction.

H. Major personriel injury or radiation overexposure.

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. 1

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

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' P;ge 48 of 174 ,_ ,

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ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 CONDUCT OF OPERATIONS APPENDIX F LOG KEEPfNG (Page 2 of 9)

2. Chronolooical Loos:

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

'and complete enough to reconstruct the events of the shift. Particular attention should be made to the entries pertaining to any abnormal condition that occurs. Times for each entry shall be as near correct as possible using military time. The entries are to be made in chronological order.

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 ~

the responsible watchstander of the log entry.

2. When it is necessary to insen 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 18 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 entry shall be recorded with the actual time of occurrence, the words

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

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

1234 (Corrected Entry) Started the 1 A EDG for surveillance run f

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

a. Conditions at the beginning of each watch.

4

Page'4Tof 174 . . . _

-ST. LUClE PLANT

' ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 .

CONDUCT OF OPERATONS APPENDIX F LOG KEEPING (Pace 3 of 9)

2. Chronolooical Loos: (continued)

A. (continued)

~

4. (continued)

b. Significant changes in plant conditions.

Examples: 1. Mode changes.

2. Load changes.

3. Reactivity changes.

4. Startups and Shutdown.

5. Time of Reactor criticality.

1 I

c. Any new condition that would limit unit generation.

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. 4 Examples: 1. Changes ir. Jant work arounds.

.6 Page.70 of 174- l l

ST. LUCIE PLANT

+

ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 l CONDUCT OF OPERATIONS 1

APPENDIX M i PROCEDURAL COMPLIANCE AND IMPLEMENTATION (Page 1 of 6)

1. Controlled procedures are available in both Control Rooms and shall be implemented and complied with in accordance with the instructions provided in 1

Ol 5 PR/PSL-1, " Preparation, Revision,- Review / Approval of Procedures." j

~

4- 2. In the event of ha emergency where procedural guidance does NOT exist or in l I

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.

i

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

4 These tasks come under the guidance of the memorization method of adherence to

) procedures in accordance with O! 5-PR/PSL-1, " Preparation, Revision, 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 fer qualified operators. Each listed task shall have one or more of the below 1 justification reasons: I t

(A) Task is routine and not complex - satisfactory completion assured by routine training and observation.

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

l (C) Posted instructions in place as reference.

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

1 A. General Control Tasks i 1. Racking IN and OUT of 6.9 KV,4.16 KV, and 480V breakers. (B) i

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

3. Writing clearances and NPWOs. (A,D) l i 4. Changing chart paper. (A,D)

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

' ~g Page.71 of 174

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ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO.- 0010120. REVISION 79 CONDUCT OF OPERATIONS -

APPENDIX M PROCEDURAL. COMPWANCE AND IMPLEMENTATl_QM (Page 2 of 6) j

1. '(continued)

B. Reactor Control Operator -

~

-1. ' Divert Letdown to Control VCT level. (A,D)

2. Check Sheet 1 of AP 1-0010125. (A,B,D)

3. Refueling Operations - movement of machine, etc. (A,D)

4. Adjusting Main Generator loading, including Megavars and Megawatts

- (manipulation of DEH controls). (D)

5. Swapping Auxiliary and Start-up Transformers. (D) 1

)

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

7. Manipulation of control valves (ADVs. FCVs) to control Heatup and Cooldown rates. (D) j 8. Pumping down Reactor Drain Tek. (A,D)

9. Placing CST on recire. (A,D) i C. Senior Nuclear Plant Operator

1. Generic Rounds Sheets. (A) i 2. Swapping HUTS. (A,D)

3. Blowing down BAMT level transmitters. (C)

J

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)

- 4 Qi 5-PR/PSL m 67--

~~ '

' r -- ,

" December,1995 Page 92 of 101 ,

RGURE 4  ;

TEMPORARY CHANGE REQUEST

' (Page 1 of 3) ,

A Reference information: (Originator to complete)

St. Lucie Unit # chmmu TC # o- % - 0/4 Procedure

Title:

cos w i or opte/rs os5 '

Rev. 74 '

Proceeurs Number: Ar oo /0 /2 o Reason for change: ,,a an ts, { m a as e ru ra- naim racs ,

1

," rre s ve SJPCRC(Off TL 0-4l-01f o7Ac d Phone: 70G/ Date: / / A 9I 9c-Originator: I

, B Proceourat Controts: (Originator to complete)

Yes No f O E is the intent of the procedure altered? (Tech. Spec. 6.8.3.A) If yes, a TC is NOT applicable. A PCR is recuired. {

I O E is this Tsmporary Change for a one-time use? If yes, this TC can be executed gg, t,irg, only. If no, this TC may be used up to 90 days, and the onginator of the TC shall submrt a prx.edure enange request incorporating this TC at the same time the TC is approved. ,

Department Head or Designee k .

// 2 9 / / C-O E' is this T.C. for a o.l.? If yes, the Quality Manager or designee and the Dept. Head or designee who is jurisdictionally responsible for the O.l. shall sign.

/ /

4 Quality Manager or Designee l Department Head or Designee / /

C Temocrary Chance Contents: (Originator to complete)

Does this Change:

• Yes No i O 9 incorporate complex or extensrve changes? If Yes. Subcommittee required. l Subcommrttee;

' initials O 5 Modify instnament setpoints?

O E Delete an independent verification?

E Alter a QC holdpoint? I O

' l O O Modify a procedural step which atters a regulatory reautrement as identified in tne procedure? i O S Alter the first execution of a procedure? (Preop, LOI) l l

r O G Addition of any chemicals? -

NOTE l 11 any of the above enteria are marked yes, pnor FRG rowew is required.

/Rt..

l

Qt 5-PR/PSLd . .

- ~ ~ ~ -

Revision 67 December,1995 Page 93 of 101 FIGURE 4 TEMPORARY CHANGE REQUEST 4

(Page 2 of 3)

TC # 0 -96 ~ O/Y ,

Yes No ,

O to CPR 50.59 Seroenmg

' Does the ehenge represent a change to the tecdity as essented an the SAR1

1.

2. Does m change represent a change to pmceoures as seecnced 6n me SAR?

3. Is me enange -== wnh a test or expenment not - in ine SAR7

! 4. Could the snange affect nuesaar safety e a way not pronously evaluatec in 7 ,

l tne SAR?

5. Does me enange recure a enange to the Tectmcal SpecrAcanons?

/

f i i M9.I.fr.

If the answer to &M,, the above 10 CFFI 50.59 screening questions are no. (Questions 1 5), then a safety evaluation is not requirec. ,

a N Date ' I /b.((r

! STA review (signaturel 5 Yes No

!' E Does rus enange (NPS to cometeui) 4 1. Compromme the senarsson of reoundant trams of souement? "

• /

2. Potensally 6solate prosaure rehels?

Defeat automane egnais?

/

3.

f/

4. Defeat rneenancat or e4ecincal interlocks?

V ,

s. Aner ine comoienen of an evoluson oue to an operator work amune.

l if yee to No. 5. autnonzason from tne Plant General Manager or Site Ves Promoern snalt be ootamec l

oate r I Yu No O I Pnor FRG rowew rootared?

- \

t

.N,[QIf, l i

i If any of the aDove enteriy are marked yes, ciscuss possible alternatives with the '

onginator. A ff ' ' 2 'f / IS NPS Signaus #M//T/ Date -

F FRG Rev*w:

Date ' / 1 Ptent General Manager Approval FRG Numoer - TNs change snad be revowed (it pnor FRG towow a not reenred) by the Fantity Rowow Group and approved by tne Plant General Manager

! wnhin 14 asys of the auenonzason cate. (Tech. Spec. 6.8.3.C)

Date ' '

REJECTED by FRG/ Plant General Manager i

Ream-I Retum to Ongmator l tt is the responst2 sty of the ongnator of me te,ected temporary change to cancel me enange m the soproonste Control Room. coetroy 40 Sold copees and helt al guesecuent evoeubens usmg ins temporary change l

I

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

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

G Tc # o - x- oN ADDrDvat: (This change shall have pnor appnwal by a NPS and one member of the plant management staff.) (Tech. Spec. 6.8.3.8)

Plant Management Staff Si 2 0*T'S[u / -- Date / /d 7 / ffc  !

NPS Signature _

Authonzation Date / /t f /96 H Oancenanon Autnonzanon (NPS/ANPS) Date / /

Reason:

9 t

l l

'* i C..

Pcge40 cf V74- ~

i ST. LUCIE PLANT i

, ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 CONDUCT OF OPERATIONS APPENDIX B l SHIFT OPERATIONS POLICIES l (Page 5 of 8)

4. (continued)

I i A. (continued)

4. P - Prove  ;

1

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

i the desired results.

Observe and verify the following:

b.

1. The task was performed correctly.

/- ~

n 'gv

2. The actual response was the expected response.

,6 3. The component / system is in the proper configuration to support j

' "" d} the intended operation.

$A 4

4. The proper component was operated.

4p

Y ,

Mi(2o M nipula -

j  : 5.

A. Oniy licensed operatoDM controls that directly affect the rea wer level of a reactormepifor training purposes. A sem1 y maniputtte esntrols only under direct visual supervishtof a _

N 1

licensed operator.

6. Unit Reliability i

A. The NPS/ANPS should make every effort to prevent putting the plant in a situation where a single failure would jeopardize plant safety or availability. l Systems listed under AP 0010142, " Unit Reliability - Manipulation of Sensitive Systems" warrant particular attention.

Maintenance 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.

6

~

. .i a -- . . . - - >

.. n. c - %, - 0 / 4 APPENDIX B SHIFT OPERATIONS POLICIES

5. Reactivity Manipulations

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

1

1. CEA insertion and withdrawal.

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

i I 3. Turbine / Generator load changes. ,

4. Placing a purification ion Exchanger in service, (any time V2520, "lon

Exchanger Bypass Valve," position is changed from bypassing the ion exchanger (s) to directing flow through the ion exchanger (s)).

B. All reactivity manipulations in the course of normal plant operations, both j positive and negative, shall have prior approval from the SRO fulfilling the role l 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 shall directly supervise the manipulation and additionally assume the role of a ,

j reactivity manager, except as provided for in step 5.D.

! D. In the event of off-normal and emergency conditions, Reactor Control

Operators are authorized to perform reactivity manipulations without the e 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 4 possible, d '

E. Crew Relief / Shift Tumover snall NOT take place for Reactor Control ,

Operators or the Assistant Nuclear Plant Supervisor while reactivity

manipulations are in progress.

,----n,g ,-,.v..,-,1.- ..-e- -n m e. .n.. ,- - - - - --

~

~

yc C C f

g - Old APPENDIX B SHIFT OPERATIONS POLICIES

~

4 l

i 5. (C'ontinued) 4 F. Reactivity manipulations shall be performed only by those individuals i

possessing an active license applicable to the unit on which the manipulation i 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. .,

)

't l

i e 1 k-

. e ,

~' -

P;ge-40 of174 _

ST. LUCIE Pl. ANT ADMINISTRATIVE PROCEDURE NO. 0010120. REVISION 79 -

CONDUCT OF OPERATIONS APPENDIX D CREW RELIEF / SHIFT TURNOVER (Page 4 of 5)

1. (continued) .

C. Instructbns for an Individual Relief / Split Shift Tumover 4

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

J

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

j The off-going watchstander shall complete the applicable Tumover

,@ b.

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

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

. @4 information as recorded on their applicable Tumover Check Sheet

!~

9 6 (Data Sheet 1) to the on-coming watchstander.  ;

@j% g f. The on-coming watchstander shall review the following and e

k acknowledge that review by initialing Check Sheet 1 of c

AP 1(2)-0010125, " Schedule of Periodic Test, Checks, and

,d e

gp' Calibrations.'

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.

a f. The applicable unit ANPS shall be notified immediately after thel J tumover has been completed.

I l

t 4

i .

~

~I (.- 0 - 9(, - 014 APPENDIX D CREW RELIEFISHIFT TURNOVER 1.

C.

1. ,

?

d. On-coming and off-going control ioom watchstanders shall conduct a  ;

face-to-face complete walkdown of the RTGBs and control panels.

I

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

P 9

e j

t

p, j ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0010120, REVISION 79 o CONDUCT OF OPERATIONS

+

APPENDIX D CREW RELIEF / SHIFT TURNOVER (Page 5 of 5) t

1. (continued)

D. Instruction for an interim or Short Term Relief /ShlM 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 Q >

, a. General watchstation status.

., V i

" ~

~

b. Off-normal conditions. }

i  :

i f c. Tests in progress. -

9 . , w .

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

.pa(

, 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 />,

.y then an Individual Relief / Split-Shift Tumover shall be performed.

c l

i ~ . . .

~

i T( O ^ - 1(, . OlY

^

APPENDIX D 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. .

p i l 4

l 1 .

f 1

4 9

't a

N'

, _ . . . _QL5-PR/RSLd_ . ..

,1 Rension 67 December,1995 i Page 1 of 101 ,

Pst l FLORIDA POWER & LIGHT COMPANY.  !

4 NUCLEAR ENERGY DEPARTMENT '

L  !

I ST. LUCIE PLANT PROCEDURE PRobuCTION PREPARATION. REVISION. REVIEW / APPROVAL OF PROCEDURES

1.0 APPROVAL

, Reviewed by Facility Review Group 1/30 1925_ j Approved by J.H. Barrow (for) Plant General Manager 2/31975 l

. Revision 67 Reviewed by FRG 12/8 19.95_

Approved by J. Scarola Plant General Manager 12/8 19.25_

2.0 PURPOSE

i 2.1 This procedure provides administrative guidance for the preparation, renew,

. approval and revision of all plant procedures and letters of instruction, for use at the St. Lucie Plant.

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).

h I

4 i

gD 9 i

S._ OPS DATE DOCT PROCEDURE DOCN OI-6-1 SYS ,

i COMP COMPLETED  :

ITM 67

h .

i Ql.5-PR/ pat -1 Revision 6T December,1995 Page 41 of 101

5.0 INSTRUCTIONS

(continued) l 5.12 (continued)

2. Controlled vendor technical manuals may be utilized as references to .  :

safety or non-safety related NPWOs to provide technical guidance (e.g.,

DWGs, specifications, torque values, dimensional infonnation, voltage / current values, etc.) to supplement an invoked plant approved i 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.

3. Changes to technical manuals received from the vendor or changes 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 016-PR/PSL-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.

l 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.

I 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 and instructions often do not lead themselves to sequendal implementation.

B.

' Procedures and instructions that are of a technicai nature shall be followed sequentially except as specifically allowed by approved plant procedures.

y . .

-- . _ . , . . . . . . . . . . .__.Q15-PRPSL 17 ._t~~l Revision 67-- i y Dooomber,1995. l

, Page.42 of 101  :

f

5.0 INSTRUCTIONS

(continued)- -!

l

' 5.13 , (continued) l 4  ;

2. (continued)  !

'~

B. .(continued)

, i i

1. Required sign-offs and data entries shall be made as each stop is i

performed. '

.  ?

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 - l limits of the procedure etc.), conduct of the procedure shall be j

stopped, the system / components placed in a safe condition and

the Nuclear Plant Supervisor shall be notified.  !

3. Deviation from Procedure Valve Checklists may be made [

provided the deviation is noted in ink 'on the applicable valve.  ;

alignment and '2 approved (initialed and dated) by the Nuclear

, Plant Supervisor.

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

clarifications which conflict with approved procedures.

4. Adherence to procedures shall be accomplished by use of one of the

following methods

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 venheation is documented by initial or signature.

4 4

4 a

,n- - , ---,w ~, - .- , - , - - . - , . , - - - , - , - , - - -r - - - ,

l

{ ,

_.. . . . . _ . _ _ _. _.. '.. ...QL5-PR/PSL .1

• Revision 67 -

December,1995 Page 43 of 101

5.0 INSTRUCTIONS

(continued) 5.13 (continued) 4 B. Method 2 - Memor%4n: 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.

1

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  ;

routine procedural actions that are frequently repeated and may <

not require the procedure to be present during performance of the i activity. However, copies of procedures shall be available to the i user at his/her work location for reference during performance of !

. the task, if necessary. _

f a

l

5. Procedural adherence may be accomplished by use of a Temporary e

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 "may" to denote permission, neither a requirement nor a recommerxW!on.

7. Independent Venfication:

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.

r l

i

l Page 1 of 20. ,.._ .,

o ' _

i FLORIDA POWER & LIGHT COMPANY

~#

E ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1-0250020 i pse- .

REVISION 35 Wl f 5'I 4g

1.0 TITLE

$  ?.

BORON CONCENTRATION CONTROL - NORMAL OPERATIOh mMConr/M, Mon l 2.0 REVIEW AND APPROVAL:

Reviewed by Plant Nuclear Safety Committee 5/30 1974 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 19.9)_

3.0 PURPOSE

This procedure establishes a method of operation to supply makeup water to the Reactor Coolant System (RCS), Safety injection System and Refueling Water Tank (RWT1 at a desired baron concentration and provides instructions for the following modes of control:

3.1 BORATE 3.2 DILUTE 3.3 MANUAL 3.4 AUTOMATIC 3.5 Shutdown Cooling (SDC) Boron Concentration Controi o

DDD S1 OPS DATE DOCT PROCEDURE DOCN '0250020 SYS COMP COMPLETED ITM 35

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

l l 0 --- , ,

Page 14 of 20 " ..

"' ' ST. LUCIE UNIT 1 OPERATING PROCEDURE NO. 1-0250020, REVISION 35 Y

l BORON CONCENTRATION CONTROL NORMAL OPERATION

8.0 INSTRUCTIONS

(continued) ,

l 8.4 (continued) l s p.

3. Enter the number of gallons ta be added into the PMW Batch integrator and set desired flow rate on F RC-2210X (Makeup Water Flow). '

4  :

4. Start one Primary Water Pump Li not running. ,

5. Place V2512 in'the OPEN position. [

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

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

extended dilutions, match makeuo flow with charging flow using the PMW

, makeup flow controller to prevent over filling the VCT while diverting  ;

letdown.

t

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

9. Retum Mode Selector Switch to AUTO or MANUAL.

. i

). 10. Ensure that the desired reactivity change occurs.

8.5 Manual Mode of Operation J

1. 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 i 1 A or 1B BAMT and the RCS. If the chemistry sample for the RCS is not 4

available then use the boronometer reading.

a A

4 L

e 4

o

.I a PCge 15~of 20 ~

.h o

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

8.0 INSTRUCTIONS

(continued)

A -

,I 8.5 (continued) .

l sy ,

NOTE ii The following formulas can be used to determine volume and blend ratio.  ;

Remember to make note of the current totalizer readings. d 1

Volume to be added = desi;ed VCT level % - actual VCT level % X 33.8 gal /%.

Blend ratio = BAMT Concentration divided by RCS Concentration minus one f ,

, l BAMT-1 '

RCS l ,

2. Ensure Mode Select switch is selected to MANUAL.

'3. 4' Place FRC-2210Y and FRC-2210X to manual and close FCV 2210Y and FCV-2210X by taking the controller output to zero, f

4. Ensum 1 A or 1B primary water pump is running.

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

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

i

7. Open the Boric Acid Makeup isolation valve FCV 2161. #

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

\

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

\

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

L

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

J 4 ( .6

. Pege16 of 20- '.- "

.. ST. LUCIE UNIT 1

?

OPERATING PROCEDURE NO. 1-0250020. REVISION 35 i

3ORON CONCENTRATION CCNTROL - WORMAL CPERATICN a 8.0~ INSTRUCTIONS: (continued) i i

l 8.5 (continued)

I

' 7 CAUTION j To preclude lifting the VCT relief valve while using V2525, do not allow the l j-combined PMW and boric acid flowrates to exceed the running charging pump (s) capacity.

j 12.' Adjust FRC 2210X and FRC-2210Y to the desired flow rates.

i NOTE  :

1 Monitor VCT level for increase. I i

t l- NOTE 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 4

' maksup 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.

l'

15. Place the runnir.3 BAM pump switch to AUTO and ensure pump stops.

i 1

16. Close FCV-2161.

j 17. Close FCV-2210X.

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

4

l' .

i . . ' QI 5fRPSL.1_ , ___ j m 67- ~~~!

December,1995 l

Page 92 of 101 i RGURE 4 i TEMPOBARY CHANGE REQUEST

.(Page 1 of 3)

A Reference Informaten- (or6ginosor to comptene)

St.Lucie Urdt e PSL i TC # I'%~ W7 l Procedure

Title:

h Gw.emarma dwrA - demar. GhernW

!: Proceeurs Number: oP f-e m ra.om Rev. 3 5'" *  ;

i Reason for change: A00 Plexcutu. c,wAA4CC rEE CICS CWbf.4 TM , sWnum dfMIA d [

\ A** benrw

• The des. As worwma a u er . x e ,se.,ar a  ;

of 2-casuaac , 21v as.

i.

j Origmator: E YNEA Phone: K D6D Date:d'd/ 23 / 1994 .

I B. Procedurst fantrois- (originetor to complete) i Yes O Is the intent of the procedure C.ered? (Tech. Spec. 6.8.3.A) If yes, a TC ls E applicable. A PCR is required.

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

jf!Df.only. If no, this TC may be used up to 90 days, and the onginator of the TC shall

. j sutxrnt a procedues change request incorporating this TC at the same time the TC is '

approved.

Department Head or Designee / .- 1LL C.1 M I MIN i 0 O

is this T.C. for a C.I.? If yes, the Quality Manager or designee and the Dept. Head or

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

t Quality Manager or Designee / /

Department Head or Designee ,

/ /

! C Temoorsrv Chance Contents: (Originator to complete)

I Does this Change:

]

Yes No O [ Incorporate complex or extensive changes? It Yes, Subcommrttee required.

Subcommittee initials l O [ Moolfyinstrument setpoints?

O g Delete an independent venficaten?

1 O g Alter a OC holdpoint? j O y Modify a procedural step which alters a regulatory lequirement as identified in the

. procedure?

O g Alter the first execution of a procedure? (Proop, LO!)

l O g Addition of any chemicals?

NOTE i 11 any of the above criteria are marked yes pnor FRG review is required. l

/R l

l-i

,l QI 5-PR/PSL-1 1 m y ..

!> December,1995 Page 93 of 101 RGURE 4 TEMPORARY CHANG 5! REQUEST (Page 2 of 3) l m ,.L- * -or7 l D to CPR 80A0 Screenmg Yes No

1. Does me mange represent a mange a me teosty as esenneed in the SAR7 L Does me ehenge supresent a change to pecondwee es descreed in me SAR? .

I 3.

1 4.

le me ehenge esensasse unm a test er essenment not dessened in the SAR7 Couk! the mange esent numiner sessey a e esy not pronousy evenaams h h

the SAR7 cf A- 1

5. Does the ehenge remare e ehenga en the Techneet Sassammene?

i M If the answer to & the 10 CFR 50.59 screerung questaons are no, (Questions

1 5), then a safety evah 'on,is ngsfecuired.

STA renew feignonson b'VI N 4 M i % Dess / N/b

. E Does run enange: (NPS to Yes No

{ . 1. Congsomme me esperaten of trame ed eguprnent?

i L Poennessyinesensprunews l 3. Dedest suusmens egnalet '

l 4. Desent mennenes or siasmess ineeaome?

j g s. Aner the sempeeman at an eumumen am to en openner wenc enema. #

)

• W yes a No. s, emnoneesen frern me Piere Genorm Manager or Sib Ves Premment ened be ceaned.

i Date / /

I Yes No O Prior enG ,onow teamed?

. M If any of threbove cntena are traArad yes, ciscuss possible altomatives with the onginator. Q[ l O ,, ,

NPS $1r Je M \_ M Ju' n

Date I /"

F Pmo Revow: V Plant Geneel Manager Appnrvel Dels ,, J f

, P71G Number -

7Ne enange shed be renewed (if pner FMG renew a not i

segused) by me Fashly Rowow Gmup and approved by me Plant General Meneger esten 14 anye of me enneneesen case. (Tech. Spec. 6A.3.C)

RsJacrun by Fmuriere General Manager '

Dans '

Reason.

Resum to Origmenor

!!is the reasonatedly of the ongmesor of me sepeeses temponry cnenge to cancel the change a the soproonste Conect Room, deseoy mR Reid cepee and het es subseeuent ewelumons unng than tangerary change.

QI 5-PR/PStr_1. - ..

. Revision 67' -

December,1995 Page 94 of 101

{

RGURE 4 TEMPORARY CHANGE REQUEST l (Page 3 of 3)

G Tc e set,,gry w_t (this change shall have prior

%,t NPS and one member of the piant management sten.) (Tech. Spec. s.a.:rg) .

_g .

Plant Management I\R  ;- )MMk Date I / 23 /

NPS Signanre b_ - w Authonzanon Date k~ /O/k H cancettation Authonzanon "

(NPS/ANPS) Date - / /

Reason:

I 9

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Page-14-o_f _20 - _;

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

"""

M; f i-BORON CONCENTRATION CONTROL - NORMAL OPERATION - :r  ;

,q . 4.

8.0 INSTRUCTIONS

(continued) P.. . .. .

8.4 (continued)

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

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

4. Start one Primary Water Pump if not running.

5. Place V2.512 in the OPEN position.

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

I

7. Monitor VCT level to ensure tank does not fill up to high level alarm. For i extended dilutions, match makeup flow with charging flow using the PMW I makeup flow controller to prevent over-filling the VCT while diverting istdown. J l

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

9. Retum Mode Selector Switch to AUTO or MANUAL

10. Ensure that the desired reactivity change occurs.

k 3 8.5 Manual Mode of Qperation

\ 1. Mn d Bit.J/

g p,g Determine the desired volume to be arjded to the VCT and calculate the proper blend ratio using the most recent chemistry boron samples of the g

N 1 A or 1B BAMT and the RCS. If the chemistry sample for the RCS is not available then use the boronometer reading.

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ST. LUCIE UNIT 1 -

OPERATING PROCEDURE NO.1-0250020; REVISION 35 . . . -

BORON CONCENTRATION CONTROL - NORMAL OPERATION 4 ,;

8.0 INSTRUCTIONS

(continued)  !:.i.? {

8.5 (continued)

.tiQE. l$ -

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

Remember to make note of the current totalizar readings.

Volume to be added = desired VCT level % - actual VCT level % X 33.8 gal /E 5 Blend ratio = BAMT Concentration divided by RCS Concentration minus one BAMT-1 RCS '

B g Ensure Mode Select switch is selected to MANUAL 1

C. $ Place FRC-2210Y and FRC-2210X to manual and close FCV-2210Y and FCV-2210X by taking the controller output to zero.

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

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

4 h' 6 @ Start either the 1A or 1B BAM pump.

N Open the Boric Acid Makeup isolation valve FCV-2161.

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

[

I

, f-@ Ensure FCV-2210Y, Boric Acid valve, selector is in AUTO.

1

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

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

A hs' f.a2 SN3 '

N R~ -

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e ST. LUCIE UNIT 1 MM!

OPERATING PROCEDURE NO.1-0250020, REVISION 35 3 < ^#

BORON CONCENTRATION CONTROL NORMAL OPERATION ~ d'

8.0 INSTRUCTIONS

(continued) n 8.5 (continued)  :

S.

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  !

pump (s) capacity.

ik  % Adjust FRC-2210X and FRC-2210Y to the desired flow rates.

N i i i

/y s M

4 Monitor VCT level for increase, i

j M \

The addition of Boric Acid should be completed before the PMW, such that,  ;

the total bland volume remaining allows for at least 30 gallons of primary makeup water alone, to flow through the lines and flush out any romaning

. boric acid. ,

i '7 A l M d$ When the desired amount of Boric Acid has been add @ lace the '

selector switch for FCV-2210Y to CLOSE.

O " ' O When the Boric Acid and water flow totalizers show that the proper  !

' amounts have been added to the VCT, then close V2512 or V2525, which ever was used.

f snHh na.,~a Bwfu-p ad O' {@7 Place the running BAM pump switch to AUTO.

P. @ Close FCV-2161.

',U G.8. Close FCV-2210X.

s R. $ Monitor for any abnormal change in temperature. Check Boronometer for '

undesirable change in Boron Concentration.

M W MM b E 2- ~

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ST. LUCIE UNIT 1

" OPERATING PROCEDURE NO. 1-0250020, REVISION 35 BORON CONCENTRATION CONTROL - NORMAL OPERAT10N

8.0 INSTRUCTIONS

(continued) 8.5 (continued) i

2. Manual Dilution L htQ.js

' 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.

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

@ MANUAL.

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

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

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

O i

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

I ig F. Ensure that either the 1 A or the 1B Primary Make-up l Water Pump is running.

G. Place FCV-2210X, Reactor Make-up, selector switch in AUTO. 5 H. E diluting to the VCT,3han OPEN V2512, Reactor Make-up Water Stop Viv.

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

4 Ibs.n OPEN V2525, Baron Load Control Valve.

4 4

1 s

.6 _ .

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

8.0 INSTRUCTIONS

(continued) 8.5 (continued)

2. (continued) i CAUTION To preclude lifting the VCT relief valve while using V2525, do NOT allow '

1 the PMW flowrate to exceed the running charging pump flow rate.

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

K. If necessary to maintain the desired VCT level, .Ihan divert the letdown flow to the WMS by placing V2500, i

h VCT Divert Valve, in the WMS position.

i

{-

L Whnn the desired VCT level is reached, Ihan:

4 -

l

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

position.

H '

t g 2. Ensure that V2500 indicates CLOSED.  !

Q M. When the desired amount of PMW has been added,Ihan

n place the FCV-2210X selector switch in the CLOSE j position.

N. CLOSE V2512 or V2525, whichever was used.

O.

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

! P.

1 Monitor for unexpected results:

1. Abnormal change in the RCS temperature.

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

l 4

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

8.0 INSTRUCTIONS

(continued) 8.5 (condnued)

3. Manual Boration

)

2.

M22A l VCT level equates to 33.8 gallons per percent of scale on LIC-2226, VCT l

Level. 1 A. Determine the desired volume of boric acid to be added.

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

I C.

Ensure that FRC-2210X, Make-up Water Flow, is in '

g MANUAL and reduce the controller output to zero (0).

1 i O\

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

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

Q F. Ensure that either the 1 A or the 1B Primary Make-up N Water Pump is running.

I

l N While it is acceptable to use either BAMT for RCS boration, it is preferable to operate the BAM Pump for the BAMT NOT designated as ' Tech Spec'.

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

i j

H. Place FCV-2210Y, Boric Acid Valve, selector switch in i i AUTO. l 1

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

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

I t

i

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. ST. LUCIE UNIT 1 4

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

8.0 INSTRUCTIONS

(continued) 8.5 (continued) j

3. (condnued) l

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

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

i M M, g necessary to maintain the desired VCT level,Ihan j divert the letdown flow to the WMS by piacing V2500, VCT Divert Valve, in the WMS position.

I N. When the desired VCT level is reached, Ihan: I

1. Return V2500, VCT Divert Valve, to the AUTO D position.

k 2. Ensure that V2500 indicates CLOSED.

Q , O. When the desired amount of boric acid has been added, N Iban place the FCV-2210Y selector switch in the CLOSE

, position.

P. CLOSE FCV-2161, Boric Acid Make-up isolation.

CAUTION

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

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

I i

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

8.0 INSTRUCTIONS

(continued) 8.5 (continued) 1

3. (condnued) l

{

R. If flushing the CVCS piping following boration is desired, Ihan: 1

$ 1. Place FRC-2210X, Make-up Water Flow, controller 4

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 g the lines with a total of at least 30 gallons of PMW.

D 3. .When the desired amount of PMW has been h added. 3han 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. I T. Ensure that FRC-2210Y, Boric Acid Flow, is in MANUAL l and reduce the controller output to zero (0).

U. Monitor for unexpected results

t

1. Abnormal change in the RCS temperature. I

2. Undesired change in the RCS baron concentration l by boronmeter indication.

i l