ML20064F155
| ML20064F155 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/16/1978 |
| From: | Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| JNRC-78-59, NUDOCS 7811280291 | |
| Download: ML20064F155 (6) | |
Text
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMBUS CIRcLI:
NEW YORK, N. Y.10019 (212) 397 6200 osoRomr.esRRy gs;^g,"ggs,",,
rasosmicx R. cLARx s'a"*I vics e a an a
,a fi.ICHARo M. FLYNN WILSUR L. oRONSERG ROBERT L MILLONZI Mama
.sN INEER NS wituAM r. Lunov November 16, 1978 JoH",i;,W'Jo,'
JNRC-78-59
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- THO M A
.M R ANN. JR.
Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.
C.
20555 Attention:
Mr. Thomas A.
Ippolito Operating Reactors Branch No. 3
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Division of Operating Reactors
Subject:
James A. FitzPatrick Nuclear Power Plan ~tI-Rotated Bundle Loading Error Event Analysis _,
Docket No. 50-333 ()
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Dear Sir:
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General Electric Company has performed an analysis of the rotated bundle loading error event for James A.
FitzPatrick Nuclear Power Plant (JAFNPP).
This letter forwards the results of the analysis which we received from General Electric Company on November 15, 1978.
As was indicated in a telephone conversation with Philip Polk and Marvin Mendonca of the Commission, a final report con-cerning the subject matter, which we expect to receive from General Electric Company on November 22, 1978, will be transmitted to you later.
The analysis was performed for Reload 2, Cycle 3 operation of the James A. FitzPatrick Nuclear Power Plant using the variable water gap method.
The method was approved by the Commission in a letter to R. E. Engel (GE) from D.
G. Eisenhut (NRC) dated May 8, 1978.
As a result of the analysis, Section 15 in the Reload 2 licensing supplement (NEDO-24129 June 1978) should be replaced with the following:
- 09\\ \\4 n uusoam
4 15.
LOADING ERROR RESULTS (5.5.4)
Limiting Event:
Rotated Bundle
- Fuel Type Initial CPR**
Minimum CPR 80RB283 1.22 1.07 80RB265L 1.22 1.07 Variable water gap method of analysis Includes 9.02 Critical Power Ratio (CPR) penalty for uncertainties in GEXL CPR predictions using axially varying R-factors.
The rotated bundle event therefore remains the limiting event for 8x8R fuel from BOC3 to EOC3-2GWd/t.
From EOC3-2GWd/t to EOC3 the load rejection without bypass event remains the limiting event for 8x8R fuel.
The FitzPatrick Cycle 3 Operating Limits are therefore as follows:
bdnimum Critical Power Ratio Exposure Range (MCPR) Operating Limit **
7x7 8x8 8 x 8R From BOC3 to EOC3-2GWd/t 1.21 1.22 1.22 From EOC3-2GWd/t to EOC3-lGWd/t 1.25 1.33 1.33 From EOC3-lGWd/t to EOC3 1.30 1.37 1.37 Attachment A to this letter shows revised Technical Specification page to reflect the new Minimum Critical Power Ratio (MCPR) Operating Limit for 8x8R fuel in the exposure range of "BOC3 to 2GWd/t before EOC3".
l l
As indicated to Marvin Mendonca of the Commission in the aforementioned telephone conversation, the analysis will allow the setpoint for the off-gas radiation monitor to be returned to the value used during Cycle 1 operation of the l
James A. FitzPatrick Nuclear Power Plant following approval of the analysis by the Commission.
Attachment B transmits the original Technical Specification page used for Cycle 1 regarding the off gas radiation monitor.
Very trh1
- yours, buOf
/
Paul
. Early Assi tant Chi f Engineer-Projects l
Att.
l
ATTACHMENT A DOCKET NO. 50-333 JAMES A.
FITZPATRICK NUCLEAR POWZP PLANT
JAFNPP 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILIANCE REQUIRENEKrS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Applicability:
Applicability:
Applies to the instrumentation and associated Applies to the surveillance of the instru-I devices which initiate the reactor scram.
mentation and associated devices which initiate reactor scram.
Objective:
l Objective:
To assure the operability of the Reactor Protection System.
To specify the type of frequency of surveillance to be applied to the protection Speci fication:
instrumentation.
s A.
The setpoints, minimum number of trip Specification:
systems, minimum number of instrument channels that must be operable for each A.
Instrumentation systems shall bc position of the reactor mode switch shall be functionally tested and calibrated as
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as shown on Table 3.1-1.
The design system indicated in Tables 4.1-1 and 4.1-2 response time from the opening of the sensor respectively.
contact to and including the opening of.the trip actuator contacts shall not exceed 100 5
msec.
B.
Minimum Critical Power Ratio (MCPR)
B.
Maximum Fraction of LLmiting Power-i Density (HFLPD) l During reactor power operation at l
rated power and flow, the MCPR operating The MFLPD shall be determined daily during 10mits shall not be less than those shown below:
reactor power operation at 2 251 rated thermal power and the APRM high flux scram
' FU EL MCPR OPERATING LIMIT FOR INCROMENTAL and Rod Block trip settings adjusted if TYPE CYCLE 3 CORE AVERAGE EXPOSURE necessary as required by Specifications 2.1.A.I.c and 2.1.A.I.d, respectively.
BOC3 to 2CWd/t EOC3-2CWd/t EOC3-1GWd/t before EOC3 to EOC3-1GWd/t to EOC3 i
7x7 1.21 1.25 1.30 i-8x8 1.22 1.33 1.37 8x8R 1 92 1.33 1.37 l
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30 d
8 Amendment No.
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ATTACHMENT B DOCKET NO. 50-333 JAMES A.
FITZPATRICK NUCLEAR POWER PLANT i
.l JAFNPP
-x s
Table 3.2-4 RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS
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Minimum 130.
Total Number of Of Operable Instrument Channels Instrument Provided By Design Action Chrnnels (1)
Trip Function Trip Level Setting For Both Channels (2) 5 1
Refuel Area Exhaust Monitor 42.7 x 10 cpm (5) 2 Inst. Channels A or B 1
Reactor Building Area Exhaust 12.7 x 105 epm (5) 2 Inst. Channels B
Monitors 4
1 Off-Gas Radiation Monitors A7 x 10 mR/hr(3) 2 Inst. Channels C
5 1
Turbine Bldg. Exhaust Monitors 41.8 x 10 cpm (5) 2 Inst. Channels C
l 5
1 Radwaste Bldg. Exhaust Monitor 66.7 x 10 cpm (5) 2 Inst. Channels C
3 1
Main Control Room Ventilation 44 x 10 cpm (6) 1 Inst. Channel D
Monitor i
2 Mechanical vacuum Pump Isolation 43 times normal full 4 Inst. Channels E
power background 1
Liquid Radwaste Discharge Monitor (4) 1 Inst. Channel F
NOTES FOR TABLE 3.2-4 1.
Whenever the systems are required to be operable, there shall be two operable or tripped instrument channels per trip system. From and af ter the time it is found that this cannot be met, the indicated action shall be taken.
2.
Action I'
A.
'Censr. operation of the refueling equipment.
B.
Isolate secondary containment and start the standby Gas Treatment System.
C.
Refer to Section 2.3.B.4 of Environmental Technical Specification.
D.
Control Room Isolation is manually initiated.
E.
Utes same sensors as Primary Containment Isolation on high main steam line radiation. Table 3.2-1.
F.
Rsfer to Environmental Technical Specification 2.3.A.3.
3.
Refer to Specification 2.3.B of the Environmental Specifications.
4.
Trip setting to correspond to Specification 2.3. A of the Environmental Technical Specifications.
7 5.
Conversion factor is 9.0 x 10 cpm - 1 uci/cc.
7 6.
Conversion factor is 8.15 x 10 cpm - 1 uci/cc.
. Amendment No.,)d 74