ML17342B265
| ML17342B265 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/29/1988 |
| From: | Edison G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-63038, TAC-63039, NUDOCS 8804130011 | |
| Download: ML17342B265 (17) | |
Text
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Docket Nos.
50-250 and 50-251 t
UNITED STATES
, NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 29, 1988 LICENSEE:
FACILITY:
SUBJECT:
Florida Power and Light Company Turkey Point Units 3 and 4
SUMMARY
OF MEETING HELD WITH FLORIDA POWER AND LIGHT COIIPANY (FP&L) ON MARCH 15, 1988, REGARDING TECHNICAL SPECIFICATIONS AND OPERABILITY OF INTAKE COOLING WATER AND COMPONENT COOLING WATER SYSTEMS
REFERENCE:
TAC Numbers 63038 and 63039 A meeting was held, in Rockville, Maryland on March 15, 1988 with representatives of Florida Power and Light Company (FP&L) to discuss two matters related to Technical Specifications (TS) for the Intake Cooling Water
( ICM) and Component Cooling Mater (CCW) systems at Turkey Point Units 3 and 4.
The first matter concerned possible interpretations of "operability" of CCM heat exchangers.
The second matter related to a revision of the TS for both systems as part of the ongoing TS Revision Project.
1.
~0 erabilit of CCM Heat Exchan ers In a letter to the licensee (FP&L) dated December 3, 1987, the staff indicated that each CCW heat exchanger should be declared inoperable when it becomes known that it cannot remove its desiqn basis heat load (50~ of the required heat removal for the reactor unit).
The staff has now improved this interpretation to address the matter from a systems standpoint.
The staff agreed with FP&L that it is sufficient if two CCW heat exchangers operating together can remove the total design basis heat load of two CCW heat exchangers, provided that a monitoring proqram is in place to assur e this capability continues to exist.
The concern is that fouling of the heat exchanger surfaces could degrade the heat removal capability.
To paraphrase, the staff agreed that it is permissible for the plant to operate with one operating CCW heat exchanger which is not able to remove all of its design basis heat load, provided that a second operating CCW heat exchanger can fully compensate by removing more than its design basis heat loa'd, and provided that FP&L monitors the heat exchanger capability on. a frequent-.basis.
The licensee agreed to provide a letter to the staff by March 18, 1988 agreeing to these provisions.
The staff will then issue a letter clarifying Enclosure 2 of the December 3,
1987 letter.
2.
Revision of TS for CCW and ICM The staff indicated that it could not accept a relaxation of TSs which would entirely remove Allowable Outage Time (AOT) from the third ICM pump and the third CCW pump.
This position is based on the current knowledge 8804l30011 880329 PDR ADOCII', 05000250 P
Mr.
W. F.
Conway Florida Power and Light Company Turkey Point Plant CC:
Harold F. Reis, Esquire Newman and Holtzfnger, P.C.
1615 L Street, N.W.
Washington, DC 20036 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. J.
Odom, Vice President Turkey Point Nuclear Plant Florida Power and Liaht Companv P.O.
Box 029100 Miami, Florida 33102 Mr. Sergio Periera County Manager of Metropolitan Dade County Miami, Florida 33130 Resident Inspector U.S. Nuclear Regulatory Commission Turkey Point Nuclear Generating Station Post Office Box 57-1185 Miami, Florida 33257-1185 "acob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Servfces 1317 Winewood Blvd.
Tallahassee, Flor ida 32399-0700 Inter governmental Coordf nati on and Review Office of Planning 5 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting, Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Regional Administrator, Region II U.S.
Nuclea~ Regulatory Comfssfon Suite 2900 101 Marietta Street Atlanta, Georgia 30323 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 3~304 Joette Lorion 7269 SW, 54 Avenue Miami, Flor ida 33143 Yr. Chris J. Baker, Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102
March 29, 1988 of the importance of service water to core melt frequency as identified in the Byron PRA and is under generic review by the staff under Generic Issue 130.
The staff suggested that simply relaxing the current 24-hour AOT for the ICW pumps to perhaps 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> was a better approach.
The staff also suggested that the ICH strainers should be included in the TS with an,AOT.
The licensee agreed to consider possible AOTs for the ICW and CCH"pumps and the ICH strainers and propose these at a later date.
In addition, the staff agreed that no AOT is necessary for the third CCW heat exchanger because of the natural incentive for the licensee to maintain the heat exchanger in an operable condition, and because of the TS interpretation described in (I) above.
The meeting agenda and reference material discussed at the meeting are provided as Enclosure 1 to this letter.
The attendance list is Enclosure 2.
Enclosures:
As stated Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation cc w/enclosures:
See next page DISTRIBUTION NRC 8 Local PDRs PD22 Readng H. Berkow G. Edison OGC-HF E. Jordan J.
Par tlow NRC Participants ACRS (10)
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approach.
The staff also suggested that the ICW strainers should be included in the TS with an AOT.
The licensee agreed to consider possible AOTs for the ICW and CCW pumps and the ICW strainers and propose these at a later date.
In addition, the staff agreed that no AOT is necessary for the third CCW heat exchanger because of the natural incentive for the licensee to maintain the heat exchanger in an operable condition, and because of the TS interpretation described in (1) above.
The meeting agenda and reference material discussed at the meeting are provided as Enclosure 1 to this letter.
The attendance list is Enclosure 2.
Enclosures:
As stated Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation cc w/enclosures:
See next page DISTRIBUTION NRC 5 Local PDRs PD22 Readng H. Berkow G.
Edison OGC-WF E. Jordan J. Partlow NRC Participants ACRS (10) 0
-2 D 'er 3 +88 PM:PDII-2 GEdison:bg 3/+88 D: PDI I-2 HBerkow 3/
/88 SP JWermiel 3/M88
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ENCL'3SUQE 1
TURKEY POINT UNITS 3 8I 4 ICW/CCW HX OPERABILITY AND TECHNICAL SPECIFICATIONS FPL/NRC MEETING - MARCH 15, 1988 AGENDA LEAD OPENING REMARKS OVERVIEW OF ICW & CCW SYSTEMS HX OPERABILITY HX SURVEILLANCE PROGRAM
. CURRENT TECHNICAL SPECIFICATIONS REVISED TECHNICAL SPECIFICATIONS FPL/NRC FPL FPL/NRC FPL FPL FPL ATTACHMENTS 1)
ICW BLOCK DIAGRAM
'2)
CCW BLOCK DIAGRAM 3)
KEY DESIGN/OPERABILITY CONSIDERATIONS 4)
FPL'S PROPOSED POSITION ON ICW/CCW HX OPERABILITY 5)
CCW/ICW-HX OPERABILITY (MATRIX) 6)
NRC LETTER OF 12/1/87 WITH SAFETY EVALUATION 7)
CURRENT TECHNICAL SPECIFICATIONS 8)
REVISED TECHNICAL SPECIFICATIONS 9)
HX CURVES
3bi 334 BS 339 8
TPCW HXB 402 341 390 391 CV-2201 314 BS 319 A
310 311 312 TPCW HXA X
CJ 400 309 321 322 371 CCW HXA 340 361 307 331 332 301 406 SS A
324 329 Xo lK LL 411 CCW HXB 40%
CV 2202 BS 8
344 349 351 410 NOTE:
BLOCK D1AGRAM SHOWN FOR UNLT 4. UNIT 3 SUPPLY HEADERS TO T P C W HX ARE REVERSED.
412 CCW HXC RO RO TO LUBE WATER SYSTEM INTAKE COOLING WATER SYSTEM BLOCK DIAGRAM 310 360
CHKII tOI FOR UXSf IANX S ltVlit'A AHh tUHt'A' S tUHt'A hHh HX A CCC A
CHS tUNt'A CHC tUIlt CHS tUllt'tt HX Sf AL HX NON.he% HX C CC '0' CC
'C'ICi Wgh hCt NL COOL EXCESS L/0 N CC
~
DC.
~ t. SNIOLO C Lit C
tASS WAST SAS
'A'L5IE SAS
~ A SYAt C CW PVIits CL,W HX I tvii Nh HX hhh tUiit'0 CS tUII '
COHPONENT COOLING WATER SYSTEH BLOCK OIAGRAH
KEY DESIGN/OPERATIONAL CONSIDFRATIONS 0
2 HX'S, IN CONJUNCTION WITH 1
CCW PUMP AND 1 ICW PUMP, ARE CAPABLE OF REMOVING DESIGN BASIS HEAT LOADS.
0 DESIGN BASIS HEAT LOADS = 120 X 10E+6 BTU/HR 0
CCW AND ICW SYSTEMS ARE DESIGNED FOR SINGLE ACTIVE FAILURES, WHEN OPERATED IN CONJUNCTION WITH THE JCO.
JCO REQUIREMENTS INCLUDE:
0 MANUALLY ISOLATING ICW TO TPCW HX'S, AS NECESSARY 0
MAINTAININGMANUAL VALVE *-406 OPEN 0
A SURVEILLANCE PROGRAM MONITORS HX OPERABILITY CONSIDERING THE FOLLOWING;.
0 ICW INLET TEMPERATURE 0
HX TUBE RESISTANCE/FOULING RATE 0
ICW PUMP FLOW 0
PLUGGED HX TUBES
FPL'S PROPOSED POSITION ON ICW/CCW HX OPERABILITY THE COMBINED PERFORMANCE OF TWO HX'S, IN CONJUNCTION WITH 1
ICW PUMP AND 1
CCW PUMP, SHALL BE CAPABLE OF REMOVING DESIGN BASIS HEAT LOADS, REGARDLESS OF INDIVIDUALHX PERFORMANCE.
CCN ICW HX OPERABILITY EXAlvlPI E 1
HXA > 50%
HXB > 50%
HXC > 50%
CTION REQMT NRC FPL OPER OPER OPER OPER OPER OPER NA EXAMPLE 2 HXA = 60%
HXB = 40%
HXC > 60%
CTION REQMT NRC FPL OPER OPER INOP OPER OPER OPER NA EXAMPLE 3 HXA = 60%
HXB = 40%
HXC >
507m
< 60 CTION REQMT NRC FPL OPER OPER INOP INOP (3)
OPER OPER (3)
(1)
EXAMPLE 4 HXA = 60%
HXB = 40%
CTION REQMT NRC OPER INOP INOP FPL..
OPER INOP (3)
OPER (3)
ENMPLE 5 HXA = 60%
HXB < 40%
HXC < 40%
CTION REQMT NRC FPL OPER OPER INOP INOP INOP INOP (2)
NOTES; (1) ENTER 24 HR LCO CURRENT TECH SPECS (2) ENTER 3.0.1. CURRENT TECH SPECS (3) OEClARE MOST DEGRADEO HX INOPERABLE