ML18227C826
| ML18227C826 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/21/1974 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | O'Leary J US Atomic Energy Commission (AEC) |
| References | |
| Download: ML18227C826 (20) | |
Text
AEC DISTRIBUTION POR PART 50 DOCKET MATERIAL
(~PORARY FORM)
I CONTROL NO:
PRlM Ploricfa Power
& Light Company Miami, Pla.
33101 Mr. R.E. Uhrig TO:
J.P. O'eary DATE OF DOC
.6<<,21-74 ORIG 3 signed OTHER 6-28-74 CC OTHER SENT AEC PDR XXX SENT LOCAL PDR PILE:
DATE REC'D 'TR TWX CLASS UNCLASS XXX PROP INFO INPUT XXX NO S REC'D 40 DOCKET NO:
50-25 /251 DESCRIPTION:
Ltr notarized 6>>21-74...trans the following....
ENCLOSURES:
Proposed changes to tech specs for Turkey Point 3
& 4 ~ ~ ~ ~ ~ ~
PLANT NAME.
Turkey Point 3
& 4 ACKNOWLEBGEB DONOT REMQVh'OR ACTION/IhPOP~fATION 7-1-74 BUTLER (L)
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CYS CLARK (L)
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KNIEL (L)
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CYS SCHWENCER (L)
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CYS'TOLZ (L)
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CYS
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CYS PURPLE (L).
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CYS ZIEMANN (L)
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CYS DICKER (E)
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CYS YOUNGBLOOD (E)
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CYS REGAN (E)
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CYS INTERNAL DISTRIBUTION RE~bE
~MUNTZING/STAFF CASE GGQSUSSO BOYD MOORE (L)(LLK-2)
DEYOUNG (L)(LWR-1)
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~REG OPR FILE & REGION (3)
MORRIS STEELE TECH REVIEW HENDRIE SCHROEDER MACCARY KNIGHT PAWLICKI SHAO STELLO HOUSTON NOVAK ROSS IPPOLITO TEDESCO LONG LAINAS BENAROYA VOLLEYER DENTON GRIMES GAL%ILL KASTNER BALLARD SPANGLER ENVIRO MJLLER DICKER.
KNIGHTON YOUNGBLOOD REGAN PROJECT MGR Cleve1~<nd~
HARLESS LIC ASST DIGGS (L)
GEARIN (L)
GOULBOURNE (L)
KREUTZER (E)
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MAIGRET (L)
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SERVICE (L)
SHEPPARD (L)
SLATER (E)
SMITH (L)
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WILLIAMS (E)
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PE R. DAVIS if%6 - ACRS 4&b&%QQ Sent to Teets 7-1-,74 EXTERNAL DISTRIBUTION (1) (2) (10) -NATIONAL LABS 1-ASLBP(E/W Bldg, Rm 529) 1-W. PENNINGTON, Rm E-201 GT 1-B&M SWINEBROAD, Rm E-201 GT 1-CONSULTANTS
.,SE&JARK/BLUME/AGBABIAN 1-PDR-SAN/LA/NY 1-BROOKHAVEN NAT LAB 1-G ~ ULRIKSON, ORNL 1-AGMED (RUTH GUSSilAN)
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ulhto(y Filo py P.O. 8OX 3100 MIAMI,FLORIDA 33101 FLORIDA POWER 5 LIGHT COMPANY June 21, 1974 Mr. John F. O'eary, Director Directorate of Licensing Office of Regulation U.
S. Atomic Energy Commissio Washington, D.
C.
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Re:
Tuxkey Point Units. 3 Docket Nos 50-
& 50-251 Proposed Amen ment 'to Facility 0 er'atin Li'c'enses'PR-31
'& 'DPR-41 Ecpypg JUO 28 c
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(PC In accordance with 10 CFR 50.59, Florida Power
& Light Company submits herewith three signed originals and forty (40) conformed copies of a proposed amendment to Facility Operating Licenses DPR-31
& DPR-41.
The changes are as set forth in the revised Technical Specifications'ages (Appendix A to.DPR-31
& DPR-41) and are as described below:
3'.'2.'3 In specification
- 3. 2. 6, Section (a), the hot channel factor limits have been broadened to include any range in the flux difference.
~3-:2-.4 In specification, 3.2.6, a new Section (f) has been added to provide corrective action requixed in case the indicated axial flux difference exceeds the permissible range.'~P'3; 2'-3 Previous paragraph (f) has been redesignated (g).
Subparagxaph (1) has been changed and subparagraph (4) has been added to clarify the requirement fox taking movable incore detector maps.
HELPING BUILD FLORIDA
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Mr. John F. O'L ry June 21, 1974 Previous paragraph (h) has been redesignated (i).
~3. 2-6 Paragraph (i) (previously on Page 3.2-5) has been redesignated (j).
3; 2-7 Specification 3.2-7, Paragraph (b) (previously on Page 3.2-6) was relocated to a new" page.
No changes have been made to the text.
'3; 2'-5 The bases have been made consistent with 'the 'proposed
.Technical Specifications.
These changes have been review'ed by the Plant Nuclear Safety Committee and the Company Nuclear Review Board.
These groups have independently det'ermined that the changes do not degrade but, in fact, improve the 'safety of the facility.
Very t ly yours, Robert E. Uhrig Vice President REU:nch Attach.
cc:
Mr. Jack R.
Newman
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STATE OF FLORTDA )
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COUNTY OF DADE
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Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power e Light Company, the Licensee herein; That he has executed the foregoing instrument; that the statements made in this said instrument are true and correct to the best of his knowledge, information and belief; and that he is autho'rized to execute the instrument of said Licensee.
o ert crag Subscribed and sworn to before me this'ay of 1974.
-Notary u
.xc zn an or t e
- of Dade, State of Florida
,~w, gY COMMISSION EXPIRES APRIL 2, 1976 aIoBDRII INRQ klhmARR JlQNDJNQ hoxN<>
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reactivity insertion upon ejection greater than 0.3%
A k/k at rated power.
Inoperable rod worth shall be determined within 4 weeks.
b.
A control rod shall be considered inoperable if (a) the rod cannot be moved by the CRDM, or (b) the rod is misaligned from its bank by more than 15 inches, or (c) the rod drop time is not met.
- c. If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.
5.
CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable rod positions shall be logged once per shift and after a load change greater than 10% of rated power.
If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93% of interim power.
6.
POWER DISTRIBUTION LIMITS a.
At all times the hot channel factors defined in the basis must meet the following limits:
FN< 2.50
[1 + 0.2 (1-P)] in the'flux difference range
+10 to -14 percent FN~H
< 1 55
[1 + 0.2 (1-P)]
where P is the fraction of interim power at wh8.ch the core is operating (P
< 1.0)
. For every percent outside of the indicated flux difference of +10 percent, the allowed F may be N
q increased above 2.50 by 3.5 percent.
For every percent outside of the indicated flux difference N
of -1'4 percent, the'llowed F
may be increased q
above 2.50 by 2 percent.
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6/21/74
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- b. If peaking factors exceed the limits of Section 6a, the reactor power and high neutron flux trip set-point shall be reduced by 1 percent for every percent excess over F or F
, whichever is limiting. If the N
N peaking factors cannot be corrected within 1 day, the overpower AT and overtemperature AT trip setpoints shall be similarly reduced.
c.
The permissible fraction of rated power, N, not to exceed the power levels given in Figure 3.2-3, at which the reactor can be operated shall be determined by N=
5.56 X 1.02 X 1.019 X 1.007'X M where M = 2.58 X F
[1 + 2 (T/100 0.02)]
~x 1.435 Q = limiting local power from Figure 3.2-4; F
is 1.435, or the value of the unrodded hori-xy zontal plane peaking factor appropriate to F
,as q'etermined by a movable in-core detector map taken on at least a monthly basis; and T is the percentage operating quadrant tilt limit, C
having a value of 2% if F is 1.435 or a value up to 10% as selected by the operator if a measured F
value is used.
xy d.
At interim power the indicated axial flux difference must be maintained within the range +10 percent to
-14 percent.
e.
For every 3.5 percent below interim power the per-missible positive flux difference range is extended by +1 percent.
For every 2 percent b'elow interim power the permissible negative flux difference is extended by 1 percent.
- f. If the indicated axial flux difference exceeds the permissible range defined in (d) and (e) above for a period of more than eight hours, the situation shall 3.2-4 6/21/74
be corrected or the reactor power shall be reduced 3.5 percent for each percent the positive flux dif-ference exceeds the permissible range or 2 percent for each percent the negative flux difference ex-ceeds the permissible range.
Following initial loading and each subsequent re-
- loading, a power distribution map, using the movable'n-core detectors, shall be made to confirm that power distribution limits are met, in the full power con-figuration, before the reactor is operated above 75 percent of rated power.
For sustained operation of the reactor above 75% of rated power; (1) a full movable incore detector map shall be taken within one month (not to exceed 38 days) after exceeding 75% power.
A full map is de-fined as surveillance of a minimum of 40 fuel assembly detector thimbles with at least 8 per quadrant.
(2)
A,partial movable incore detector map must be taken 10 to 17 days after the full map.
A partial map is defined as surveillance of a minimum of 20 fuel assembly detector thimbles with at least 4'er quadrant.
(3)
Two traverses with the movable incore detectors (4) in appropriate alternate thimbles shall be taken during each calendar week.
If the reactor is operated belo~
75% of rated
- power, the intervals in (1),
(2) and (3) above may be extended by the length of time the reactor was below 75% of rated power.
If the quadrant to average power tilt exceeds a
value T% as selected in specification 6.c, except for physics and rod exercise testing, then:
1)
The hot channel factors shall be determined within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the power level and trips J
adjusted to meet the requirements of Section 6a and b, or 302-5 6/21/74
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2)
If the hot channel factors are not determined within two hours, the power shall be reduced from interim power 2X for each percent of quad-rant tilt.
3)
If the quadrant to average power tilt exceeds
+10%, except for physics tests, the power level and.high neutron flux trip setpoint will be re-duced from interim power, 2% for each percent of quadrant tilt.
If after a further period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the power tilt in 2) above is not corrected to less than
+T%, and 1)
If design hot channel factors for interim power are not exceeded, an evaluation as to the cause of the discrepancy shall be made and reported as an abnormal occurrence to the Atomic Energy Com-mission.
2)
If the design hot channel factors for interim power are exceeded and the power is greater than 10% the Atomic Energy Commission shall be notified and the nuclear overpower, over-power AT and overtemperature AT trips shall be reduced one percent for each percent the hot channel factor exceeds the rated power design values.
3)
If the hot channel factors are not determined, the Atomic Energy Commission shall be notified and the overpower AT and overtemperature AT trip settings shall be reduced by the equivalent of 2% power for every.lX quadrant to average power tilt.
7.
IN-CORE INSTRUMENTATION a.
A minimum of 16 thimbles, at least 2 per quadrant, and the necessary associated detectors shall be operable during the check and calibration of nuclear instrumentation ion chambers.
3.2-6 6/21/74
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b.
Power shall be limited to 90% of interim power for 3 loop or 50X of interim power for 2 loop operation if the requirements in Section 7.a are not met.
302-7 6/21/74
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For operation at a fraction, P, of 'interim power the design limits are met,
- provided, N < 2.50
[1 + 0.2 (1-P)] in the indicated flux difference range q-of +10 to -14 percent, and F>
< 1.55
[1 + 0.2 (1-P)]
For every percent outside of the indicated flux difference of +10 percent the allowed F may be increased above 2.50 by 3.5 percent.
N q,,
For every percent outside of the indicated flux difference of -14 percent the allowed F may be increased above 2.50 by 2 percent.
N q
The permited relaxation allows radial power shape changes with rod N
insertion to the insertion limits.
The allowed increase in F for large flux differences is consistent with power shapes assumed in setting the overpower and overtemperature hT setpoints.
It has been deter-mined that provided the above conditions 1 through 5 are observed, these hot channel factor limits are met.
For normal, operation and anticipated transients the core is protected from excdeding 18.0 KW/ft locally, and from going below a minimum DNBR of 1.30, by automatic protection on power,,flux difference, pressure and temperature.
Only conditions 1 through 4, above, are mandatory since the flux difference is an explicit input to the protection system.
Measurements of the hot channel factors are~reqOired ys part of'startup physics tests and whenever abnormal power distribution conditions require a reduction of core power to a level based on measured hot channel factors.
In the specified limit to, F there is a 5 percent allowance for uncertain-N
[11 q
ties which means that normal operation of the core within the defined N
conditions and procedures is expected to result in F
< 2.50/1.05 even on a worst case basis.
When a measurement is taken experimental error must be allowed for and 5 percent is the appropriate allowance for a full core map taken with the moveable incore detector flux mapping system, B3; 2-5 6/21/74
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