ML20093J808
| ML20093J808 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/18/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20093J811 | List: |
| References | |
| NUDOCS 9510230406 | |
| Download: ML20093J808 (12) | |
Text
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-t UNITED STATES y*
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001 i
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9 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. NPF-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
j A.
The application for amendment by Northeast Nuclear Energy i
Company, et al. (the licensee), dated March 29, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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9510230406 951018 PDR ADOCK 05000423 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby J
amended to read as follows:
1
]
(2)
Technical Soecifications
)
The Technical Specifications contained in Appendix A, as revised through Amendment No. 120, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
The licensee shall i
operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
j i
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
j
'FOR THE NUCLEAR REGULATORY COMMISSION i
f
"^I i
i Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance:
October 18, 1995 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 120 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and l
contain vertical lines indicating the areas of change.
1 Remove Insert 1
3/4 2-5 3/4 2-5 3/4 2-6 3/4 2-6 3/4 2-8 3/4 2-8 3/4 2-11 3/4 2-11 i
3/4 2-12 3/4 2-12 3/4 2-13 3/4 2-13 3/4 2-15 3/4 2-15 3/4 2-17 3/4 2-17 6-20 6-20 i
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i POWER DISTRIBUTION LIMITS 3/4.2.2 NEAT FLUX H0T CHAMEL FACTOR - Fo_(Z)
FOUR LOOPS OPERATIM LIMITIM COMITION FOR OPERATION 1
s 3.2.2.1 Fa(Z) shall be limited by the following relationships:
F(Z)$ F*" K(Z) for P > 0.5 o
P J
p*m i
F(Z)s K(Z) for P $ 0.5 a
0.5 i
Fo" = the Fo limit at RATED THERMAL POWER (RTP) provided in the core operating limits report (COLR).
4 THWAL MR RATED THERMAL POWER,,,g Where: P, I
K(Z) - the normalized Fo(Z) as a function of core height specified in the COLR.
APPLICABILITY: MODE 1.
ACTION:
With Fa(Z) exceeding its limit:
a.
For RAOC operation with Fo(Z) outside the applicable limit specified in the COLR:
l (1) Within 15 minutes, control the AFD to within new AFD limits i
which are determined by reducing the applicable AFD limits by 1% AFD for each percent Fo(Z) exceeds its limits.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits, or l
l 4
MILL 5 TONE - UNIT 3 3/4 2-5 Amendment No. pp, pp, 77,120 um
POWER DISTRIBUTION LIMITS LIMITING C0lWITION FOR OPERATION (Continued)
(2) Reduce THERMAL POWER at least 1% for each 1% Fo(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range i
Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER i
OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% Fo(Z) exceeds the limit, or l
j (3) Verify that the requirements of Specification 4.2.2.1.3 for j
base load operation are satisfied and enter base load j
operation.
i, Where it is necessary to calculate the percent that Fa(Z) exceeds the limits for items (1) and (2) above, it shall be calculated as the maximum percent over the core height (Z) that Fa(Z) exceeds its 2
limit by the following expression:
1
-1 x 100 for P :t 0. 5 x K(Z) p 4
1 i
'* f)
- u
-1 x 100 for P < 0. 5 l
x x(z)
,3 b.
For base load operation outside the applicable limit specified in the COLR, perform either of the following actions:
(1)
Place the core in an equilibrium condition where the limit in 4.2.2.1.2.C is satisfied, and remeasure F#(Z), or i
6 NIL.LSTONE - UNIT 3 3/4 2-6 Amendment No. 77, 120 on
POWER DISTRIBUTION LIMITS SURVEILLANCEREQUIREMENTS(Continued) c.
Satisfying the following relationship:
i k
Ff(Z) s F*"" x K(Z) for P > 0.5 PxW(Z)
Fl{Z) $ F*"" x K(Z) for P s 0.5 W(Z) x 0.5 I
where Fy(Z) is the measured Fa(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, F$" is the Fa limit, K(Z) is the normalized Fo(Z) as a function of core height, P is the relative THERMAL POWER, and W(Z) is the cycle-dependent.
function that accounts for power distribution transients encountered' during normal operation.
FSTP, K(Z), and W(Z) are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.6.
d.
Measuring F"a(Z) according to the following schedule:
4 (1) Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which Fo(Z) was last determined,* or (2) At least once per 31 Effective Full Power Days, whichever occurs first.
e.
With the maximum value of i
j Ff(Z)
K(Z) i over the core height (Z) increasing since the previous determination j
of F#(Z), either of the following actions shall be taken:
(1) Fy(Z) shall be increased over that specified in Specification 4.2.2.1.2c by an appropriate factor specified in the COLR, or l
. During power escalation at the beginning of each cycle, oower level may be increased until a power level for extended operation has been achieved and power distribution map outlined.
MILLSTONE - UNIT 3 3/4 2-8 Amendment No. pp, pp, 77,120 nae
l 3
4 j.
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) e.
With the maximum value of.
f5(Z)
{
K(2) 1
]
l over the core height (Z) increasing since the previous determination of F#(Z), either of the following actions shall be taken:
(1) Fy(Z) shall be increased over that specified in 4.2.2.1.4.c by an appropriate factor specified in the COLR, or (2) Fy(Z) shall be measured at least once per 7 Effective Full Power Days until 2 successive maps indicate that the maximum value of i
Eg(Z)
K(2) j overthecoreheight(Z)isnotincreasing.
1 f.
The limits specified in 4.2.2.1.4.c and 4.2.2.1.4.e are not l
applicable in the following core plane regions:
(1) Lower core region 0% to 15%, inclusive.
(2) Upper core region 85% to 100%, inclusive.
l 4.2.2.1.5 When Fo(Z) is measured for reasons other than meeting the require-ments of Specifications 4.2.2.1.2 or 4.2.2.1.4, an overall measured Fo(Z) shall be obtained from a power distribution map and increased by 3% to i
i account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
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MILL 5 TONE - UNIT 3 3/42-11 Amendment No. pp pp. 77 120 me a
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POWER DISTRIBUTION LIMITS HEAT Filly HOT CHAlelEL FACTOR - F (Z) f TINtEE LOOPS OPERATING LIMITING COW ITION FOR OPERATION 3.2.2.2 Fa(Z) shall be limited by the following relationships:
pm i
f(Z)s (K(2)] for P > 0.375 o
P l
ge 8
F(2)s
[K(2)] for P s 0.375 o
0.375 i
i I.
Fo" - The Fo limit at RATED THERNAL POWER (RTP) specified in the CORE OPERATING LIMITS REPORT (COLR).
k N*
I Wheres P=
RATED THERMAL POWER, and i
K(Z) - the normalized Fo(Z) as a function of core height speci-fled in the COLR.
]
APPLICABILITY: N0DE 1.
ACTION:
,4 With Fo(Z) exceeding its limit:
a.
For RAOC operation with Fo(Z) outside the applicable limit specified in the COLR:
l 4
1 (1) Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the applicable AFD limits by 4
1% AFD ' for each percent Fo(Z) exceeds its limits.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits, or i
L (2) Reduce THERNAL POWER at least 1% for each 1% Fo(Z) exceeds the i
limit within 15 minutes and similarly reduce the Power Range j
Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent i
i MILLSTONE - UNIT 3 3/4 2-12 Amendment No. JP. JP. 77.120 4
esas
i PCWER DISTRIBUTION LIMITS LIMITING C0fGITION FOR OPERATION (Continued)
POWER OPERATION may proceed provided the Overpower AT Trip i
Setpoints have been reduced at least 1% for each 1% Fa(Z) exceeds the limit.
The Overpower AT Trip Setpoint reduction shall be performed with the reactor in at least HOT STANOBY, or l
j (3) Verify that the requirements of Specification 4.2.2.1.3 for base load operation are satisfied and enter base load operation.
Where it is necessary to calculate the percent that Fo(Z) exceeds the limits for items (1) and (2) above, it shall be calculated as the maximum percent over the core height (Z) that Fa(Z)~ exceeds its limit by the following expression:
0
-1 x 100 for P2 0. 375 x x (Z)
\\
-1 x 100 for P< 0. 37 5
, 0.375
- I b.
For base load operation outside the applicable limit specified in the COLR, perform either of the following actions:
(1) Place the core in an equilibrium condition where the limit in l
4.2.2.2.2.C is satisfied, and remeasure Ff(Z), or (2) Reduce THERMAL POWER at least 1% for each 1% Fo(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% Fa(Z) exceeds the limit.
The Overpower AT Trip Setpoint reduction shall be performed with the reactor in at least HOT STANDBY.
4 The percent that Fo exceeds the limit shall be calculated as the maximum percent over the core height (Z) that Fa(Z) exceeds the 3
limit using the following expression:
MjLSTONE-UNIT 3 3/4 2-13 Amendment No. pp.120
1 POWER DISTRIBUTION LIMITS 1
SURVEILLANCE REQUIREMENTS (Continued) d.
Measuring FT(Z) according to the following schedule:
(1) Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which Fo(Z) was last determined,* or (2) At least once per 31 Effective Full Power Days, whichever occurs 2
first.
e e.
With the maximum value of i
Ff(Z)
K(Z) over the core height (Z) increasing since the previous determinationi of F5(Z), either of the following actions shall be taken:
(1) FT(Z) shall be increased over that specified in Specification 4.2.2.2.2c by an appropriate factor specified in the COLR, or i
(2) F5(Z) shall be measured at least once per 7 Effective Full Power Days untti two successive maps indicate that the maximum value of i
Ff(Z)
K(Z) i overthecoreheight(Z)isnotincreasing, f.
The limits specified in Specifications 4.2.2.2.2c and 4.2.2.2.2e are not applicable in the following core plane regions:
i (1) Lower core region from 0% to 15%, inclusive.
1 (2) Upper core region from 85% to 100%, inclusive, 1
i i
- During power escalation at the beginning of each cycle, the power level may be increased until a power level for extended operation has been achieved and power distribution map obtained.
MILLSTONE - UNIT 3 3/42-15 Amendment No. #, pp, pp, pp.120 onze i
l POWER DISTRIBUTION LIM 1I,1 SURVEILLANCEREQUIRENENTS(Continued) i f
c.
Satisfying the following relationship:
i Ff(Z) $ F*"" x K(Z) for P > APL*
i P x W(Z),
t 5
l where:
FY(Z) is the measured Fa(Z).
The Fa"* is the Fo limit, the normalized Fo(Z) as a function of core height.
P is the relative l
THERNAL POWER.
W(Z)a is the cycle-dependent function that accounts forlimitedpogrdistributiontransientsencounteredduringbaseload i
j operation.
Fa, K(Z), and W(Z) are specified in the COLR as per l
Specification 6.9.1.6.
j i
d.
Neasuring F%(Z) in conjunction with target flux difference determina-i tion according to the following schedule:
l (1) Prior to antering. base load operation after satisfying Sec-tion 4.2.2.2.3, unless a full core flux map has been taken in the previous 31 Effective Full Power Days with the relative THERNAL 1
j POWER having been maintained above APL"* for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior j
to mapping, and (2) At least once per 31 Effective Full Power Days.
I e.
With the maximum value of l
l Ff(z)
K(z) l i
over the core height (Z) increasing since the previous determination j
of FT(Z), either of the following actions shall be taken-l (1) F5(Z) shall be increased over that specified in 4.2.2.2.4.c by an appropriate factor specified in the COLR, or I
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MILLSTONE - UNIT 3 3/42-17 Amendment No. M. pp, pp, pp 120 omae
ADMINISTRATIVE CONTROLS i
CORE OPERATING LIMITS REPORT (Cont.)
1 2.
Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, 3.
Control Rod Insertion Limits for Specification 3/4.1.3.6, 4.
Axial Flux Difference Limits, target band, and APL"" for Specifica-tions 3/4.2.1.1 and 3/4.2.1.2, 5.
Heat Flux Hot Channel Factor, K(z), W(z), APL"", and W(z)a for Specifications 3/4.2.2.1 and 3/4.2.2.2.
6.
Nuclear Enthalpy Rise Hot Channel Factor, Power Factor Multiplier for Specification 3/4.2.3.
6.9.1.6.b The analytical methods used to determine the core ' operating limits 3
shall be those previously reviewed and approved by the NRC in:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (W Proprietary). (Methodology for Specifications 3.1.1.3--
Moderator Temperature Coefficient, 3.1.3.5--Shutdown Bank Insertion Limit, 3.1.3.6--Control' Bank Insertion Limits, 3.2.1--Axial Flux,
i Difference, 3.2.2--Heat Flux Hot Channel Factor, 3.2.3--Nuclear Enthalpy Rise Hot Channel Factor.)
2.
WCAP-8385, " Power Distribution Control and Load Following i
Procedures - Topical Report," September 1981 (W Proprietary).
J 3.
T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC),
January 31, 1980--
Attachment:
Operation and Safety-Analysis Aspects l
of an Improved Load Follow Package.
<[
4.
NUREG-800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981 Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),
Revision 2, July 1981.
l 5.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ j
SURVEILLANCE TECHNICAL SPECIFICATION," Rev. 1, October 1993 (W Proprietary).
(Methodology for Specifications 3.2.1--Axial Flux Difference [ Relaxed Axial Offset Control] and 3.2.2--Heat Flux Hot Channel Factor [W(z) surveillance requirements for Fo Methodology].)
4 6.
WCAP-9561-P-A, ADD. 3 Rev. 1, "BART A-1: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS--SPECIAL REPORT:
THIMBLE MODELING H ECCS EVALUATION MODEL," July 1986 (W Proprie-I tary).
(Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)
I 7.
WCAP-10266-P-A, Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," March 1987 (W Proprietary).
(Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)
}
MILLSTONE - UNIT 3 6-20 Amendment No. JJ. 77, pp, pp, pf,120