ML20199E411

Operating Procedure 7201.1, Standby Steam Generator Feedwater Sys - Operating Instructions. Related Info Encl

ML20199E411
Person / Time
Site:	Turkey Point
Issue date:	08/22/1985
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20199E404	List: L-85-372, Commits to Apply Appropriate Tech Spec Requirements to Address Auxiliary Feedwater Pump Availability & Performance Monitoring.Several Items Discussed in IE Operational Readiness Insp Team 850913 Exit Meeting Resolved ML20199E398 ML20199E411 ML20199E432 ML20199E453 ML20199E461 ML20199E480 ML20199E486 ML20199E503
References
FOIA-85-729 7201.1, NUDOCS 8603270210
Download: ML20199E411 (33)

Text

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1 FLORIDA POWER ~AND LIGHT COMPANY TURKEY. POINT UNITS 3 AND 4 OPERATING PROCEDURE 7201.1 AUGUST 22. 1985

1.0 Title

STANDBY STEAM GENERATOR FEEDWATER-SYSTEM - OPERATING INSTRUCTIONS 2.0 Acoroval and List of Effective Pages:

2.1 Approval

Change Dated 8/22/85 and Approved by Plant Manager - Nuclear: 8/22/85 2.2 List of Effective Pages:

i Page.

Date Page Date Page Date

~

1 8/22/85 3

8/22/85 5

8/22/85 2

8/22/85 4

8/22/85 6

8/22/85 3.0 Purcose and Discussion:

3.1 Purpose

This procedure provides instructions for operation of the standby steam generator feedwater pump (S S.G.F.P) and related piping systems.

3.2 Discussion

3.2.1 The system consists of two electrically driven pumps rated at 850 gpm 1

each when pumping against a 2510 ft. head. Suction water is supplied from the demineralized water storage tank and pump discharge is i

routed to the discharge header of the steam generator feed pumps.

Recirculation from. the pump discharge is routed.to the demineralizer water storage tank to prevent pump damage if operated in a no-flow mode.

3.2.2 The system is designed for ~ manual operation and the pump may be' started from the Control Room or locally.

The primary purpose of the system is to provide feedwater to the units during nonnal plant-

~

startup, shutdown and hot standby modes of operation

, therefore the need for AFW pumps to perform plant power generation i' unctions will not be necessary.

Although the system is not safety related, the pumps will also provide an alternate source of feedwater for plant cooldown in the event of a loss of Feedwater capabilit Feedwater and Auxiliary Feedwater) to the Steam Generators.ly (normal l

8603270210 860106 PDR FOIA WEISS85-729 PDR D

8/22/85

_ 4 OPERATING PROCEDURE 7201.1, PAGE 2 STANDBY STEAM GENERATOR FEEDWATER SYSTEM - OPERATING INSTRUCTIONS 4.0 Precautions and Limits:

4.1 Before placing the system in service, verify that the demineralized water

. storage tank level is greater than 10 ft. to ensure adeqaute suction head pressure to the pumps.

4.2 When using the standby steam generator feed pumps to supply feedwater to one unit, the isolation valve to the other unit feed system should be closed.

4.3 If a feedwater isolation signal is present on the unit to be supplied witn feedwater, the isolation signal must be " reset" to pennit use of FCVs *-479, 489 and 499.

hP5sysMip?ng**MniM*Ind"t#e Di#-mis **rti bea*ri"n9 oil *PevMi'in"tna St 5

• pum nomal range.

4.5 The SSGFP should be shutdown if bearing temperature exceeds 180*F.

The alternate pump shall be started if required for feedwater supply.

INITIALS 5.0 Related System Status:

5.1 JThe feedwater system is in operation in accordance with Operating Procedure *-0P-074, Steam Generator Feedwater Pump.

5.2 A SGFP Disch M0V Downstrm Warmup Bypass *-20-120 and B SGFP Disch MOV Downstnn Warmup Bypass *-20-220 are closed.

5.3 4160 Volt busses aC anu 4C are energized.

5.4 The following breakers are RACKED IN with their associated Charging Spring toggle switch in the ON position and charging springs ' flag indicating SPRINGS CHARGED.

5.4.1 4160V Bus 3C 3AC06 Standby SGFP A 5.4.2 4160V Bus 4C 4AC10 Standby SGFP Bl 5.5 The demineralized water storage tank is in service with a water level 1 10 feet.-

5.6 The instrument air system is in service in accordance with Operating Procedure *-0P-013, Instrtment Air System.

5.7 Level and feedflow indicators. for the steam generator (s) to which feedwater is being supplied are operable.

l

~

8/22/85 OPERAT!NG PROCEDURE 7201.1, PAGE 3 STANDBY STEAM GENERATOR ~FEEDilATER SYSTEM - OPERATING INSTRUCTIONS 6.0

References:

6.1 l Operating Procedure *-0P-074, Steam Generator Fee'dwater Pump 6.2 Operating Procedure *-0P-073, Condensate System 6.3 Operating Procedure *-0P-075, Auxiliary Feedwater System l 6.4 Off-Normal Operating Procedure 7308.1, Malfunction of the Auxiliary Fecdwatar System 6.5 Emergency Operating Procedure 20007, Loss of al.1 A.C. Power 6.6 FPL Drawing 5610-T-E-5062, Sheet 2 of 5 6.7 Bechtel Drawing 5610-T-E-4062/82-296 6.8 Pacific Pumps Instruction Manual No. 2902 (Bechtel Ref. No. 5177-090-M-0808) 6.9 Reliance Electric Instruction Manual. B-3628-4 6.10 Operating Procedure 7001.1, Condensate and Feedwater System - Prestart Yalve Alignment for Normal Operation 7.0 Records Required:

7.1 The date, time and 'section started and the date, time and s?ction completed shall be logged in the Reactor Control Operator (RCO) logbook.

Also, any problems encountered while performing the procedure should be logged, i.e.,

malfunctioning equipment, delays due to a change in plant conditions, etc.

Completed co of the below listed section(s) enclosure (s),

and/or 7.2 attachment (s) piesconstitute Quality Assurance Records, and therefore, shall be transmitted to Document Control and be retained for a minimum of 5 years in accordance with Quality Assurance record requirements:

7.2.1 Section 5.0 7.2.2 Section 8.0 7.3 Completed copies of. the below listed section(s), enclosure (s),

and/or attachment (s) shall be retained in the Plant Supervisor-Nuclear's file until the next performance of that section, enclosure, or attachment.

7.3.1 Section 5.0 7.3.2 Section 8.0l e

r

+

9 8/22/85 OPERAT1NG PROCEDURE 7201.1, PAGE 4 STANDBY STEAM GENERATOR FEEDWATER SYSTEM - OPERATING INSTRUCTIONS

8.0 Instructions

8.1 ISSGFP System Normal Standby Valve Alignment:

8.1.1 Perform the following valve alignment.

INITIAL VALVE VALVE DESCRIPTION REQUIRED POSITION DWDS-016 SSGFW Suction Isol from D.W.S.T. to Pumps 10 PEN DWDS-023 Pump combined Recirc. to D.W.S.T.

OPEN DWDS-3-012 SSGFW Disch. to Unit 3 CLOSED DWDS-4-012 SSGFW Disch. to Unit 4 CLOSED DWDS-148 SSGFP Disch. to Header Vent Valve

-CLOSED DWDS-4-149 SSGFP Disch to Unit 4 Drn Valve CLOSED DWDS-3-149 SSGFP Disch to Unit 3 Drn Valve CLOSED DWDS-131 SSGFP Disch Header Drn Valve CLOSED DWDS-152 SSGFP Disch Header Vent Valve CLOSED DWDS-153 SSGFP Disch Header Drn Valve CLOSED

~

DWDS.50 SSGFP Disch Header Vent Valve CLOSED DWDS-4-154 SSGFP Disch to Unit 4 Drn Valve CLOSED,

DWDS-3-154 SSGFP Disch.to Unit 3 Drn Valve CLOSED}

Standby SGFP A (S.S.G.F.P)

DWDS-006A SSGFP A Suction Valve '

OPEN DWDS-007A SSGFP A Disch Valve OPEN DWDS-003A PX Isol. Valve, SSGFP A Suction OPEN j

DWDS-155A PI 6511A Isol Valve, SSGFP A Disch.

OPEN DWDS-156A SSGFP A Recire. Valve OPEN Standby SGPPB (S.S.G.F.P)

DWDS-006B SSGFP B Suction Valve OPEN DWDS-007B SSGFP B Disch. Valve OPEN DWDS-0038 PX Isol. Valve, SSGFP A Suction OPEN i

DWDS-155B P16511A Isol. Valve, SSGFP A Disch.

OPEN DWDS-156B SSGFP A Recire. Valve OPEN Completed by:

Date:

Reviewed by:

Date Plant Supervisor-Nuclear or SR0 Designee

--- - A

8/22/85 OPERATING PROCEDURE 7201.1, PAGE 5 STANDBY STEAM GENERATOP. FEEDWATER SYSTEM - OPERATING INSTRUCTIONS INITALS 8.2 Placing SSGFP A (B) In Service:

8.2.1 Perform the following steps to place SSGFP A (B) in service:

1.

Verify Section 5.0, Related System Status, has been completed.

2.

Verify the SSGFP System has been aligned in accordance with Section 8.1, SSGFP System Normal Standoy Vaive Alignment.

3.

Verify normal oil levels in the outboard and inboard pump and motor bearings.

4. -Open SSGFP Disch Header Vent Valve, DWDS-148 until a solid stream of water emits and then close the valve.

5.- Open the following valves until a solid stream of water emits and then close the valve:

(1) DWDS 150 SSGFP Disch Header Vent Valve (2) DWDS 152 SSGFP Disch Header Vent Valve-6.

Verify motor bearing temperature pyrometer is set at 180*F.

7.

Start SSGFP A (B) from the Control Room or locally.

j Pump (s) Started:

8.

On the unit which is to be supplied feedwater, open-DWDS *-12.

Valve Opened:

9.

Notify the Control Room that feedwater is available up to the following feedwater regulating valves.

(1) FCV *-479 A S/G FW Bypass Valve J

(2) FCV *-489 B S/G FW Bypass Valve (3) FCV *-499 C S/G FW Bypass Valve

10. At the Control Room adjust the Flow Control Valve to achieve the desired flow to the steam generator (s).

4 4

6 OPERATING PROCEDURE 7201.1, PAGE 6

- 8/22/85

)

STANDBY STEAM GENERATOR FEEDWATER SYSTEM - OPERATING INSTRUCTIONS

11. Visually monitor pump operation for any of the following abnormalities:

4 NOTE:

The Plant Supervisor - Nuclear shall be notified of

~

any abnonnal system operation.

(1)

Excessive oil usage on pump or motor bearings, low oil level in sightglasses.

(2) Excessive pump seal leakage (grener than 300 drops per minute)

(3)

Excessive motor bearing temperature (greater than 180*F). Shutdown pump if temperature reaches 180*F. -

Normal range is 155'F to 160*F.

8.3 Removing SSGFP A (B) From Service 8.3.1 On the unit that is receiving feedwater, close DWDS *-012.

Valve Closed:

t 8.3.2 Stop the o^perating SSGFP(s) from the Control Room or locally.'

8.3.3 Return the SSGFP System to normal standby valve alignment 'in accordance with Section 8.1 of this procedure.

Completed by:

Date:

Plant Supervisor-Nuclear or SRO Designee

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no ca powen a uci.e couramv LNTER4FFICE CORRESPONDENCE JPE-PIPO-85-873 l

Juno Building Juno Beach, Fla.

tocarioes K.L. Jones - PTP Technical Dept.

DATE July 26, 1985 y,

S.G. Brain - Power Plant Engineering

, q, COP'ESto C.J. Baker suaJscT:

TURKEY POINT UNIT 3 & 4 J.M. Denis J.D. Evans AUXILIARY FEEDWATER SYSTEM UPDATE AND SCHEDULE L.C. Huenniger REA-TPN-85-30 W.H. Rogers, Jr.

M C.M. Wethy H.T. Young W. Raasch J. Price Re ference 1.

JPE-PTPO-84-1900 dated January 11, 1985 2.

JPE-PTPO-85-305 dated June 28, 1985 3.

JPE-PTPO-85-316 dated June 28, 1985 4.

JPE-PTFO-85-231 dated March 1, 1985 5.

JPE-PTPO-85-534 dated May 22, 1985 6.

JPE-PTPO-85-812 dated July 11, 1985 7.

JPE-PTPO-84-1861 dated December 18, 1984 8.

JPE-PTPO-85-98 dated January 30, 1985 9.

JPE-PTPO-85-102 dated January 29, 1985

10. JPE-PTPM-84-209 dated February 24, 1984

11. JPE-PTPM-84-638 dated April 18, 1984

12. JPE-PTPO-85-303 dated July 15, 1985

13. JPE-PTPO-85-762 dated July 1, 1985

14. JPE-PTPO-85-579 dated June 4, 1985

15. JPE-PTPO-85-771 dated July 1, 1985 This letter provides an update on the status of the tasks associated with the subject REA dealing with the auxiliary feedwater cystem.

This letter supercedes the status provided by JPE-PTPO-85-544 dated May 30, 1985.

A current status and schedule is provided below numbered in the sequence identified within REA-TPN-85-30.

1.

Minimize AFW Plow Control Oscillation This task involves the replacement of the trim in the flow contral valves to allow the valves to operate in a more suitable range (257. - 757 open) for better control.

Reference 1 requested Bechtel to provide a schedule and cost estimate to modify the system to eliminate flow escillation.

DWA 061133 has been prepared to initiate this work and was issued per Reference 2.

A schedule to provide PC/Ne ser this sash by December 6, 1985 was transmitted to the plant per Reference 3.

W2.

PEOPLE... SERVING PEOPLE

e ! " ci 12:r1 ~ Se e t -60 le A3Meni Det.sn'Uf :

K.L. Jones - PTP' Technical Dept.

TURKEY POINT UNIT 3 & 4 AUXILIARY FEEDWATER SYSTEM UPDATE AND SCHEDULE Page 2 2.

AFW Technical Specification Revision A preliminary copy of the Standard Technical Specification for the Auxiliary Feedwater System was reviewed by JPE and comments were provided to the plant.

,JPE will support any further review of these documents as required.

3.

AFW Governor Performance Item 1:

This task is to develop testing guidelines to determine present governor performance (i.e.,

high speed and electric and mechanical trip setpoints).

It will also determine the ability of the governor to control the pump during major variations in load.

In addition it will determine the bleed down rate of governor oil after pump shutdown.

JPE has provided recommendations for testing the turbine governors to determine their present operability (Reference 4).

Test results will be reviewed when available to determine necessary modifications.

Item 2:

Automatic shutdown devices ' are to be installed on the governors to discontinue the requirement for cycling the manual speed control knob after pump shutdown.

This should eliminate pump overspeed problems on restart.

Per teference 5 JPE provided the necessary technical information on RFA 411037 for the plant's purchase ~ of the automatic shutdown devices.

A PC/M for thier installation will be provided by August 23, 1985.

4.

Review seismic support of AFW Flow Control Valve Nitrogen Supply Lines Reference /6 provided an evaluation for the supports for the nitrogen supply lines.

This evaluation concluded that some copper lines needed to be resupported but continued operation is justified until the modifications are made under NCR 341-85.

5.

AFW T&T Valve Switches and Local Indicating Lights JPE completed a cost estimate (REE-84-E-14) to implement a solution in order to reduce the maintenance requirements for these components

~

(Reference 7).

A PC/M will~te scheduled upon budget - approval for this project.

51 d 22:ri SE/EI/60

• 1e ADeM den 5n W0es j

K.L. Jones - PTP Technical Dept.

TURKEY POINT UNIT 3 & 4 AUXILIARY FEEDWATER SYSTEM UPDATE AND SCHgDULE Page 3 6.

Design Basis Document A design basis document was issued per Reference 8.

This document will be updated as the system is modified or as otherwise necessary.

7.

AFW - Nitrogen Backup System 1

Item 1:

This task is to determine. the necessity of a N2 backup supply for the AFW turbine differential pressure controller.

Per Reference 9,

this project is currently scheduled for completion j

by January 31, 1966.

Item 2:

The design basis for the nitrogen supply system and surveillance requirements will be provided by August 30, 1985 for inclusion within the design basis document.

8.

AFW System Accessibility Item 1:

Per the plant's request, a cost estimate for shortening the ATW turbine inlet piping will.be provided by August 30, 1985.

Item 2:

A scope and schedule for providing access platforms to the Unit 3 train 2 flow control valves will be provided by July 1

31, 1985.

Item 3:

RPA 400179 was provided to purchase nine chain operators-per Reference 10.

Purchase Order 65380-99800P was prepared for purchase.

JPE is presently reviewing the piping stress _ analysis for this addition to provide a PC/M for - this modification.

The chain operators will be installed on valves 3-141,241,341.AFPD-3-006,007 and 008 and AFPD-4-006,007 and 008.

The remaining three valves (4-20-141,241,341) -are located above a horizontal section of security fencing.

Therefore a platform is recosanended for their access.

To support this effort, JPE provided PC/M 84-67 per Reference 11.

9.

AFW System Steam Leakoffs This project involves a review of steam blowing from the above and below seat drains on the T&T valve through the T&T valve gland leakoffs.

This task will also review the excessive steam passing through orifice steam traps in r.he system.

In addition, a review of the steam header leakoff system will be performed.

i Per Reference 9,

these items will be completed by November 29, 1985.

s

91 e 22:rI s5 61/60 le'Abeni 6e*isa C e:

K.L. Jenos - PTP Technicci Dapt.

b TURKEY POINT UNIT 3 & 4 AUXILIARY FEEDWATER SYSTEM UPDATE AND SCHEDULE Page 4 10.

ATW-AFP RPM ~ Monitoring DWA 061133 has been prepared for Bechtel to provide a PC/M for installing AFW RPM indicators in the Control Room.

Per Reference 12, JPE expects to provide PC/Ms for this modification by December 6, 1985.

11.

AFW-Electrical Conduit Reroute This project involves the review of the failures of solenoid valves SV-2919,2917 and 2915 on FCV 2833,2382 and 2831 due to weather exposure.

A scope and schedule was provided per Reference 15 which stated that an evaluation of alternative solutions and corresponding cost estimates would be provided by September 6, 1985.

12.

AFW-Removal of Obsolete Equipment Per the REA, the unused equipment to be removed includes pressure switches in front of the turbine, AFW flow indicators on the Unit' 3 feedwater platform, 3/8" tubing near the "A"

AFW turbine and the junction box for old AFW flow indicators.

A cost estimate for this task will be provided by December 27, 1985.

13.

Single Failure Analysis JPE is to provide a single failurs analysis of the current AFW i

configuration.

This s'nalysis should be completed by September 27, 1985.

14.

Misalignment of AFW This task is to address a concern whether a single component can be misaligned to completely disable the feedwater system.

JPE will complete this task by October 10, 1985.

15. AFW - Auxiliary 011 Pump This task is to summarize the design basis for the motor driven auxiliary oil pump.

The design basis was transmitted by Reference 13.

_ ov-

_. e m w_ c, m4 It K.L. Jones - PTP Technical Dept.

TURKEY POINT UNIT 3 & 4 AUXILIARY TEEDWATER SYSTEM UPDATE AND SCHEDULE Page 5 16.

Auxiliary Feedwater Supply from the DWST This task is to review the present procedural valve -line-up to decernine limitations for its use.

This review was transmitted by P.sference 14.

If you have any questions or concerns about the current status or schedule for these projects, please contact me or Steve Cornell at 863-3132.

e

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ce.% P.AL - tv atomoa powia a ocar co a INTEROFFICE CORRESPONDENCE AU612 E FIA PWR. & UCHT Co.

EN#

Nuclear Energy i.ocarion H. 3. Dager yo August 7,1985 oarc

,nou

3. W. Williams, 3r.

co,ics To E. A. Adomat h. W. Dickey h-E.,

svasocT, TURKEY POINT UNIT NOS. 3 & 4 3

AUXILIARY FEEDWATER SYSTEM H. N. Paduano

3. E. Price

/

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W. H. Rogers, 3r.

h yy / # #'

j L. D. Slepow

[dM d#

C. M. Wethy f

C. O. Woody PNS-PS-85-114/1 The configuration of the Auxiliary Feedwater System at Turkey Point has evolved over the years since original design. This evolution has been as a result of FPL desired enhancements and NRC mandated changes following Three Mile Island.

Currently the performance of the system is less than desired, and several measures have been instituted to improve the system. Investigations by both Nuclear Energy Department personnel and Power Plant Engineering have suggested a course of action. The recommendations are contained in Request for Engineering Assistance (REA) TPN-85-30, Auxiliary Feedwater System Improvements.

l Because of the sensitive nature of the Auxiliary Feedwater System and my desire to ensure that this project recieves an appropriate level of attention, I am requesting that you name a Project Manager. This action must ensure an intense, focused effort which will result in expedited resolution to the REA items.

It is my expectation that significant improvement, i.e., resolution of short term items, will be achieved by November 15.

Additionally, Nuclear Energy has named Mr. 3. E. Price as the representative to this In concert with the Project Team, Mr. Price will be addressing Auxiliary team.

Feedwater System operation and maintenance issues not covered by the engineering request, e.g., procedures, preventive maintenance, spare parts, etc.

To achieve the necessary rapid resolution to these projects, I am requesting weekly status reports to Mr. C. O. Woody by both the Project Manager (on REA activities) and Joe Price on the above Nuclear Energy issues.

While *.hese items address the short term, there may be some longer term improvements that will be generated as a result of these endeavors. These items will be addressed as the project evolves.

kh J. W. Williams, Jr.

Group Vice President Nuclear Energy 3WW/myt Attachment b/a PEOPLE... SERVING PEOPLE Form 1000 (stocked) Rev. 8/01

g pg.

g.

TD - 3 f 2.

-l RE, uD. W^! U-30

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Florfde Power & Ltght Conceny RTA IG.

8EglEST FGt DGlIEERilG A551STA8EE SYST.IID.

7S FUt IEELEMt PUWT5 Title Aurl s tary Feedseter System leprovement s Plant Turkey point Plant Unit No.

3&4 Priority A++

Description of lYobles/ Engineering Requested:

The Auull tery Fueduster Syster taprovement Project identif tes ver tous erees of the AFw system requietnq taprove.

eent or voereding, mtle the issuance of this REA, the enof neering support recutrod to perfore these AFw tasks had been requestw on s ptocement bests. As e result, the budaetina has also been done on a pieceneel bests This REA combines all the Arw uork under one REA and one budget to ensure adequate project control, tSee des tree project constdorations.)

Engineering / Project Recutred by (Dete)

OrIgtnoted by T. Reed 3////4T (Dete)

Estimated Cost t.a ter PLAffT RDUTIIS INITIAL DATE oudget I,.m.. ut.

En uter De,er-,

S..

nf 2-<r.r r o& N Acc. No.

Technicei Dept.tRevie.)- MR S /, */35 CC N.P. AL R su,v.

V/drf h N0 h YES ALNtA Revlow

/

Plant Services 8tgr.

h NO h if YES, CTRAC No.

USt#tC Commitment Config. Control Supv.

M*

/M kifYES,utg.Date: //2/V PR8 Approved NO

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n hA 4lWW-Y:ubr Gh2hl Aeproved:

plCA<Dm.s.P..g

.m P-

.o h Chief Engineer, Power Plant Engineering TO:

Director of Projects Please proceed alth the project above. Irltten conf freetton is required within 15 working days from the below este.

All correspondence concernIng this project should be addressed to the Technical Department Supervisor eith copies to the Plant tennager, the Conf fguretton Control Supervisor, the Plant Support Section Supervf sor -

PNS/GO, the $1te Resident Engineer, the Startup Superintendent, and the following:

Please notify the TechnIcel Department Supervisor prior to proceeding If the services of a consultant will be r ouir. or the - ir.d.u. date can, be met.

1. A/sW H & Wc' Auth.,I d:

VICE'PRESIDDIT j

DATE l

E.

s

[

Florida Power & Light Company REQUEST FOR ENGINEERING ASSISTANCE FOR NUCLEAR PLANTS Title Auxiliary FeedwateL Jystem Improvements REA No.

Background and Necessity:

The AFW Improvement Project can be more effectively implemented by combining all the AFW work under one REA and one budget.

4

\\

Desired Project Considerations:

This all-enconpassing AFW REA performs two functions:

1.

This REA requests that Project Management (PGM )

assist in the AFW Improvement Project and perform the necessary project scoping scheduling and coordination needed to implement these AFW upgrades.

2.

This all-encompassing AFW replaces all the previous piecemeal AFW RE As.

These previous AFW REAs are ' closed out with the approval of this REA.

All future engineering work on the AFW Improvement. Project will be performed under this REA.

The budgeting for all the AFW : tasks should be combined under one budget.

The attachment to this REA describes each AFW task to be (or being) performed, giving the following information:

1.

The Problem Description 2.

Review / Recommendation 3

Status 4.

Priority (3. general categories: First, Second, and Third)

=

0 r

AFW REA ATTACHMENT 1.

Minimize AFW Flow Control Oscillation 2

AFW Technical Specification Revision 3.

AFW Governor Performance

.4 Upgrade of AFW Flow Control Valve Nitrogen Supply Lines 5.

AFW T 4.T Valve Switches and Local Indicating Lights 6

Design Basis Document 7

AFW - Nitrogen Backup System 8.

AFW System Accessibility 9.

AFW System Steam Leakoffs

10. AFW = AFP RPM Monitoring

11. AFW - Ele:trical Conduit Reroute 12 AFW - Removal of Obsolete Equipment

13. Single Failure Analysis 14 Misalignment of AFW

15. AFW - Auxiliary Oil Pump 16 Auxiliary Feedwater Supply From the DWST

' AFW REA ATTACNNT Page 2 Old Reference Number 1.

Minimize AFW Flow. Control Oscillation RTA-1671 Problem

==

Description:==

The AFW system exhibits an oscillation phenomenon when in the auto control mode.

This is indicated by oscillating flow on the control room HICs.

(AFW Report Task #2)

Review:

This is a very important problem to resolve.

Its solution may alleviate other AFW problems.

-Status:

JPE is to provide scope and schedule by 2/28/85.

Priority:

First Priority.

1 Also, under "AFW Auto Flow Control" is the new 125 r,PM setpoint. PUP is in the process of updating the operating procedures to include 125 GPM.

The new setpoint should be completed by 3/19/85.

(i.e. ; procedures updated, so that HICs can be set 9125 GPM.)

2.

AFW Technical Specification Revision Problem

Description:

Current AFW Technical Specification is ambiguous and needs clarification as well as a Tech. Spec.

basis.

This REA provides a formal means of involving JPE in the AFW Tech. Spec. submittal.

j Review:

Meeting should be held between J. Arias, C. J.

Baker, and 'J.

M.

Donis to clarify the Tech.

Spec. direction.

JPE -should be involved in the front end of the AFW. Tech. Spec. submittal to avoid the generation ' of an unnecessarily too restrictive Tech. Spec.

J. Arias is the single point of contact on the AFW Tech. Spec.

. Status:

The AFW Tech. Spec. revision.is underway.

Priority:

First Priority.

3.

AFW Governor Performance

• Old Reference Number TD-329 i

Problem Description 1: Should the Woodward governor respond more quickly to avoid turbine overspeeds? Also, the steady (state speed (5900 RPM) and trip set points both electrical and mechanical) may have drifted.

(AFW Report Task F26a, 26b, 27)

Review 1:

JPE will address the above concerns with a governor test program.

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AFW REA ATTAC N NT l

Page 3 Status -1:

Test requirements are to be provided from JPE by 3/1/85 JPE is to review pump performance data and make recommendations by 7/26/85 Problem Description 2: After operation of the. AFW ' pump ' the governor speed control knob must be cycled manually in order to avoid pump overspeeding upon a quick sta rt.

Review 2:

JPE recommends a pressure actuated shutdown device.

Status 2:

The schedule for installation of this device will be prepared pending the results of the governor test program.

4 Uperade of AFW Flow Control Vaive Nitrocen Supply Lines Old Reference Number REA TD-337 Problem

Description:

The train 2 nitrogen backup supply lines to AFW flow control valves 2831,.2832, and 2833 are copper tubing and do not appear to be seismically supported.

Review:

These-lines were walked down by Site Engineering and do not appear to be seismically supported.

If seismic support is needed, then the.1/4 in.

Cu lines should be replaced with 3/8 in..

stainless steel with seismic support.

Status:

Currently, Bechtel is being asked to determine if these lines are seismically supported.

Priority:

If not seismically supported - First Priority.

i If already seismically supported - the item can be closed out.

5.

AFW T & T Valve Switches and Local Indicatine Lights Old Reference Number REE 84-E-14 Problem

Description:

Recurring failure of T & T switches, indicating lights, and fuses (AFW Report Task #21A).

Review:

JPE has already determined the cause and provided a solution.

Status:

PC/M is to be scheduled upon budget approval.

Priority:

Second Priority.

AFW REA-ATTAC N NT Pa ge 4 6.

Desian Basis Document Problem

Description:

There is no design basis for the current AFW configuration (AFW Report Task #20).

Review:

This item is part of this REA, to provide a means of updating and revising the AFW design basis document.

Status:

The AFW design basis has been issued as REV 0 Priority:

Second Priority, whenever updating or revising is necessary.

7 AFW - Nitrocen Backuo System Problem Description 1:

Is nitrogen backup required to the AFW pump DP dell?

Review 1:

Without DP cell (current configuration) the AFW pumps operate 9 5900 RPM.

JPE should determine if N. backup is required.

(Since f ailure allows 2

punps to still operate 9 5900 RPM.)

Status 1:

JPE is-to perform a study with cost estimate for removal by 1/31/86.

Priority 1:

Second Priority.

Problem Description 2:

~

What is the design basis for the station 1 and station 4 N. backup for the AFW flow control 2

valves?

For the N2 backup system what are the

(

surveillance test requirements? And how often?

Review 2:

JPE should provide this information necessary to generate an N2 backup surveillance procedure.

Status 2:

Letter sent from J. M. Donis to G. P. Nutwell requesting this information.

Priority 2:

First Priority.

8.

AFW System Accessibility Old Reference Number TD-328 Problem Description 1: Extra steam line length at inlet to the AFW turbine makes access difficult.

Review 1:

Determine the cost of shortening this steam l

line.

s

~. _

AFW REA ATTACMNT Page 5 Status 1:

No work done or currently scheduled.

I Priority 1:

If not costly - Second Priority.

If costly - Close out item.

Problem Description 2:

There is no access platform for the Unit 3 flow control valves.

Review 2: '

Currently, operators must climb temporary scaffolding to gain access to these valves.

A platform should be provided (been done on Unit 4).

Status 2:

Work is not currently scheduled.

Priority 2:

Second. Priority Problem Description 3:

The position of the flow control valve isolation valves makes operation difficult.

Review 3:

Provide chain operators for these valves (AFPD 3-20-141, 241, 341; AFPD 4-20-141, 241, 341; AFPD 4-006, 007, 008; AFPD 3-006, 007, 008).

Status 3:

No work has been done or scheduled.

Priority 3:

Second Priority.

4 9.

AFW System Steam Leakoffs Old Reference Number REE 84-E-12 i

Problem Description 1: High pressure above and below seat drains on T & T valve blow steam back through the T & T valve gland leakoffs.

Review 1:

JPE should resolve.

Consideration should be given to where the steam leakoff lines should be routed.

(To condenser?) Al so,' consider. routing steam leakoff lines out of AFW access area.

~

Status 1:

JPE to review concerns, provide. evaluation and cost estimate by 11/29/85.

Priority 1:

Second Priority.

Problem Description 2:

Orifice steam traps allow too much steam to blow by.

Review 2:

JPE re?olve.

Also consider the steam line routing concerns of above. (P.eview 1.)

AFW REA ATTAcmqENT Page 6 Status 2:

JPE to review and provide evaluation and costing by 11/29/85.

j Priority 2:

Second Priority Problem Description 3:

What is the design basis for the steam header leakoff controls?

Is the pressure setpoint

[

appropriate.

. Review 3:

JPE should provide this information as' part of 1

the design basis document.

Priority 3:

Second Priority.

10. AFW - AFP RPM Monitorine Old Reference Number 4

REE 84-E '

TD-343 Problem

Description:

There is.no control room indication for AFP j

RPM.

(AFW Report Task #17)

Review:

The primary concern is to allow the operator to determine if the pumps are in " slow roll" which currently renders the governors inoperable. ~The governor shutdown device solves this problem.

Generally, flow indication.will give the

/ -

operators a good indication whether the pumps are operating normally. However, RPM indication T -

would provide information for an individual pump operating abnormally.

Status:

RPM indication is required.

Priority:

If ~ required - Second Priority.

l 11 AFW - Electrical Conduit Reroute Old Reference Number TD-333 Problem

Description:

Recurring failure of the solenoid valves (SV l

2919, 2917, 2915) on flow control valves CV-2831, 2832, 2833, due to water damage.

Review:

JPE should review and provide solution.

Possible considerations are to reroute the conduit lines into these solenoid valves.

Status:

No work done or scheduled.

Priority:

Second - Third Priority.

=

l-1 AFW REA ATTACKNT Page 7 12.

AFW - Removal of Obsolete Equipment Old Reference Number TD-330 Problem

Description:

Out-of-service equipment in the AFW system effects overall cleanliness and to some extent accessibility for the AFW.

t Review:

This is not an AFW operability concern, however, a cost estimate to remove the following should be provided:

a.

Pressure switch on front of turbine.

b.

Old AFW flow indicators on Unit 3 feedwater platform.

c.

3/8" tubing north of A AFW turbine, d.

The junction box for the old Units 3 4 4 AFW flow indicators.

Status:

No work done.

Priority:

If cost effective - Third Priority.

13. Single Failure Analysis Problem

Description:

A single failure analysis of the current AFW h,\\

configuration should be performed and

~

incorporated into the AFW design basis document.

v' Review:

JPE should provide the above.

Ok Status:

JPE is almost finished (3/15/85).

Priority:

Third Priority (work almost conplete).

14 Misa11onment of AFW Problem

Description:

Can a single operator action disable the AFW cospletely?

Review:

Impell is determining the minimum required equipment to allow the AFW to function.

This analysis must be reviewed by JPE.

When complete, it should be incorporated into the AFW design basis document.

f

-.m

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AFW REA ATTACmENT Page 8 Status:

Impell is currently working on this, should complete first rev. on 4/1/85.

Priority:

Third Priority.

15. AFW - Auxiliary 011 Puno Problem

Description:

Is the auxiliary oil pump required for AFW pump operability?

What are the aux. oil pump's functions?

Reviaw:

JPE should provide the design basis for the aux.

oil pug.

This information will be incorporated into the AFW design basis document.

Status:

JPE to provide this information as well as cost estimate to meet design basis (if it doesn't) by 6/28/85.

Priority:

Third Priority.

16 Auxiliary Feedwater Supply from the DWST Problem

Description:

Determine the limitations on use of DWST water as a backup for the AFW water supply.

Review:

JPE should determine the limitations on using DWST water.

A path for DWST water to the AFW has been done. This work is required.

i J

Status:

JPE is currently scheduled to complete this work by 6/28/85.

Priority:

Third Priority - may be closed out.

j i

l m.-

AFW REA ATTACM4ENT Page 9 ITEMS OMITTED FROM THE AFW REA 1)

AFW Trouble Annunciator Cmitted because there is currently an operator solely dedicated to monitoring the ATW after initiation (Operator can spot any problems).

Long term AFW problems can be diagnosed via S/G level and TAVG alarms.

The annunciator is not useful in either the short-term or the long term.

2)

AFW Control Valve Position Monitoring Omitted because secondary. flow indication (via HICs) is adequate to determine whether the FCVs are open or closed.

This instrumentation i

would unnecessarily complicate the AFW and add another failure mode.

3)

AFW - Ng Backup Relief Valve and Crosstie Omitted because; a) regulators have internal relief and relief valve is not required, b) crosstie is not needed.

4)

AFW - Lube Oil Monitoring IST is sufficient to detect bearing problems.

5)

Neutral Position for Flow Control Valves item is already closed out.

6)

AFV Lighting Covered under security lighting.

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INTER 4FFICE CORREFONDENCE JPE-PTPO-85-534 LocATsom Juno Beach, Fla.

To K.L. Jones - PTP Technical Dept.

DATE May 22,1985 PROM S.G. Brain - Power Plant Engineering copits to h

C.J. Baker susacTs TURKEY POINT UNITS 3 & 4 C.M. Wethy.

AUXILIARY FEEDWATER SYSTEM L.C. Buenninger TURBINE GOVERNOR MANUAL BLEED DOWN J.M. Donis (w/ enc)

REA's TPN 84-009 & TPN 85-30 J.D. Evans

'J.A. Labarraque W.H. Rogers, Jr.

H.T. Young T. Raed (w/ enc)

Reference:

JPE-PTPO-85-470 dated May 8, 1985 In accordance with the letter referenced above Power Plant Engineerirg has completed an RPA for the purchase of pressure actuated shutdown devices to be installed on the three AFW turbine Governors in service and the three recently acquired spares.

The attached RPA provides specifications for Governor operating j

requirements with the shutdown device installed.

We recommend the plant ship two or three Governors at a time to Woodward Governor Co. for the modification and then sequentially install the refurbished Governors on the turbines to avoid adversely affecting normal operation of the system or spare part availability.

Woodward can modify the Governors and return them within four weeks of receipt.

Per the referenced letter, JPE will provide a PC/M for this modification by August 23, 1985.

The PC/M is provided primarily to document the vendors modifications and will not provide implementation details.

The RPA requires Nuclear Energy's incorporation of account numbers, delivery date, and signature authorization.

Details for Governor shipping and order of refurbishment should be coordinated between the plant, purchasing department and Woodward Governor Co.

If you have any questions or concerns, plese contact me or Steve Cornell at 863-3132.

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Enclosure PEOPLE... SERVING PEOPLE

PLO#iOA P0wtit & UGMT COMPA88Y INTER 4FFICE CORRESPONDENCE JPE-PTPO-65-544 i.occio,e Juno Beach, FL K.L. Jones - PTP Technical Dept yo cars g,y 30, 1985 S.G. Brain - Power Plant Engineering comes to E.J. Acosta C.J. Baker su m cT.

TURKEY POINT UNIT 3&4 C.M Wethy AUXILIARY FEEDWATER SYSTEM L.C. Huenniger UPDATE AND SCHEDULE J.M. Donis REA-TPN-65-30 J.D. Evans J. A. Labarraque W.H. Rogers, Jr.

H.T. Young T. Reed

Reference:

1)

JPE-PTPO45-102 Dated January 29,1985 2)

JPE-PTPO44-1900 Dated January 11,1985 3)

JPE-PTPO45-231 Dated March 1,1985 4)

JPE-PTPO45-470 Dated May 8,1985 5)

JPE-PTPO-84-1861 Dated December 18,1984 6)

JPE-PTPO45-98 Dated January 30,1985 7)

JPE-PTPM44-209 Dated February 24,1984 8)

JPE-PTPM44438 Dated April 18,1984 Power Plant Engineering has received and reviewed the subject REA. This project is currently being worked in accordance with the schedule provided per reference

1. A current status and schedule is provided below:

1. Minimize APW Flow ControlOscillation Reference 2 requested Bechtel to provide a schedule and cost estimate to modify the system to eliminate flow oscillation. A DWA has been prepared to initiate this work, however, this project is on hold pending bu%et approval.

2. AFW TechnicalSpecification Revision A preliminary copy of the Standard Technical Specification for the Auxiliary Feedwater System was reviewed by JPE and comments were provided to the plant.

JPE will support any further review of these documents as required.

3. AFW Governor Performance Item in JPE has provided recommendations for testing the t..rbine governors to determine their present operability (Reference 4).

Test results will be reviewed when available to determine necessary modifications.

A0003/JPE-PTP045-5444585/G ptOPLE.. 5ERVING PEOPLE

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Item 3:

Per reference 4, JPE will provide the necessary technical information on an RPA for the purchase of the automatic shutdown devices by May 31,1985. A PC/M for their installation will be provided by August 30,1985.

4. Upgrade of AFW Flow ControlValve Nitrogen Supply Lines Bechtel is currently evaluating the supports for the nitrogen apply Enes, A summary of this evaluation and a schedule for additional work if necessary will be provided by July 19,1985.

5. APW T&T Valve Switches and LocalIndicati:q Lights JPE completed a east estimate (REE44-E-14) to inlement a solution to the problem (Reference 5).

A PC/M will be scheduled won bu%et approval for this project.

6. Design Basis Document A design basis document was issued per reference 6. 'Ihis document willbe updated as the system is modified or as otherwise necessary.

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7. APW - Nitrogen Backup System.

Item 1: Per reference 1, this project is currently scheduled for completion by January 31,1986.

Item 2: The design basis for the nitrogen supply system and survelliance requirements willbe provided by August 30,1985.

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8. AFW System Accessibility i

Item 1: A cost estimate for shortening the AFW turbine inlet piping willbe provided by August 30,1985.

Item 2: A scope and schedule ~ for this item will be provided by June 28,1985.

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Item 3: 'An RPA (400179) was provided for nine chain operators per reference 7.

Purchase Order 8538049800P was prepared for their purchase. JPE will provide a PC/M to document this modification by July 26,1985.

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1 A0003/JPE-PTP0154444585/O i

The remaining three valves (440-141,341,341) are located above a horizontal.. section of security fencing.

1herefore a platform is recommended ^for their accesa, To support this effort, JPE provided PC/M 8447 per reference 8.

9. AFW System Steam Leakoffs l

Per reference 1, these items willbe completed by November 29,1985

10. AFW-AFP RPM Monitoring A DWA has been prepared for Bechtel to provide a PC/M for installing AFP RPM indicators in the Control Room. However this project is presently on hold pending bu4et approval

11. AFW - Electrical Conduit Heroute A scope and schedule willbe provided by June 28,1985.

12. AFW - Removal of Obsolete Equipment A cost estimate for this task willbe provided by December 27,1985.

13. Single Failure Analysis JPE is presently performing a single failure analysis. the current AFW configuration. This analysis should be completed by September 27,1985.

14. Misalignment of AFW JPE is presently reviewing a draft of a report prepared by Impell We expect to provide our comments by June 28,1985. A finalsummary of the project is expected to be complete by October 25,1985.

15. AFW - Auxiliary OilPump Per reference 1, this project should be completed by June 28,1985.

18. Auxiliary Feedwater Sgply from the DWST i

Per reference 1, this project should be completed by June 28,1985.

If you have any questions or concerns about the current status or schedule for these projects, please contact me or Steve Cornell at 863-3132.

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ptoneoa powen a uswt co*8Phav INTEROFFICE CORREWONDENCE JPE-PTPO-85-579

1. ^T '"

Juno Beach, FL to K.L. Jones - Technical Department oave June 4, 1985 p ao.,

S.C. Brain - Power Plant Engineerin copias v R.J. Acosta C.J. Baker susact, TURKEY POINT UNITS 3 & 4 C.M. We hy AUXILIARY FEEDWATER SYSTEM EMERCENCY WATER SUPPLY FROM THE DWST L.C. Buenninger

)

J.M. Donis REA TPN 85-30 J.D. Evans J.A. Labarraque W.H. Rogers, Jr.

H.T. Young D.W. Haase T. Reed

Reference:

Inter-office memo from C.J. Baker to Distribution dated May 15, 1984.

Per the letter referenced above, Power Plant Engineering was tasked with reviewing the availability and limitations of using water from the demineralized water storage tank (DWST) for an emergency

' backup supply to the condensate storagt tanks to supply the auxiliary feedvater system.

As part of our review, we studied the present procedure used for l

this operation (ONOP 7308.1 '4k1 function of the Auxiliary Feedwater System" dated 1/18/85 steps 5.3.15, 1-9).

This procedure provides a valve lineup and restrictions for supplying emergency makeup from the DWST to the condensate storage tank via the condensate transfer pump.

The restriction for this procedure states that the operation should not be performed unless the, CST level is critically low and the DWST level is above 12 feet.

The DWST level restriction is based on an elevation difference in a section of piping between the DWST and the Unit 4 condensate transfer pumps (The same section of piping on Unit 3 does not reach the same elevation).

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PTP 3 & 4 Auxiliary Fosdvstor Systen Based on our review and walkdown of the system, JPE concludes that ONOP 7308.1 is acceptable for this operation with the restrictions provided.

The water stored in the DWST is acceptable l

for use in the feedwater system and the pump succion will remain l

flooded if the DWST level is above 12 feet.

Also, the. nitrogen i

blanket system on the DWST is capable of making up the full volume displacement rate of water removal by the condensate transfer pumps without breaking the vent tank seal.

Closure of isolation valves on the branch connections to the pump suction piping (ie. CV-1519) may allow continued pumping below the 12 foot level by maintaining a siphon.

If the tank is to i

be pumped below 12 feet, to avoid possible equipment damage, the l

operation should be monitored to shut down the pump if flow is lost.

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This letter completes our efforts on the Item 16 of the subject

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REA.

If you have any questions or concerns about this review, please i

contact me or Steve Cornell at 863-3132.

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