ML20199E147
| ML20199E147 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 06/12/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| TAC-59320, TAC-59321, TAC-59322, TAC-59623, TAC-59624, TAC-60930, NUDOCS 8606230203 | |
| Download: ML20199E147 (11) | |
Text
_4 e
DUKE POWER GOMPANY P.O. Box 33180 OIIAMLOTTE, N.C. 28242 HALB. TUCKER TELEPHONE yygrea**==**
(704) 373-4538 June 12, 1986
. /
V Mr. Harold R. Denton, Director
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Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION:
B.J. Youngblood, Director PWR Project Directorate #4
Subject:
McGuire Nuclear Station Catawba Nuclear Station Docket Nos. 50-369 and 50-370; 50-413 and 50-414 Proposed Technical Specification Changes - Supplement Relaxation of RTS Allowed Outage Times i
Dear Mr. Denton:
My letter of July 22, 1985 submitted proposed license amendments (pursuant to 10CFR 50.90) to Facility Operating Licenses NPF-9 and NPF-17 for McGuire Nuclear Station Units 1 and 2, and NPF-35 for Catawba Nuclear Station Unit 1, respectively. The proposed amendments concern relaxation of Reactor Trip system allowable outage times based on an analysis performed by the Westing-house Owners Group (documented in WCAP-10271 and its Supplement 1) and approved by the NRC (reference NRC Safety Evaluation for WCAP-10271 dated February 21, 1985). This submittal was subsequently revised via Duke letter of September 11, 1985 in response to an NRC request. The " notices of consideration of issuance of amendments to facility operating licenses and l
proposed no significant hazards consideration determination and opportunity for hearing" related to the submittals for the McGuire and Catawba Nuclear Stations were published in the Federal Register on December 18, 1985. In addition, by letter dated March 7, 1986 Duke requested that these previously proposed changes (among others) for Catawba Unit 1 (License No. NPF-35) also apply to Catawba Unit 2 (License No. NPF subsequently superseded by No.
NPF-52).
I l
By letter dated April 7, 1986 (and subsequent correction letter of April 22, i
1986), the NRC issued amendment nos. 54 and 35 to Facility Operating Licenses NPF-9 and NPF-17 for McGuire Nuclear Station Units 1 and 2 respec-i tively in response to the above mentioned application (note that the Cacawba Units 1 and 2 aspects of the application are still under NRC review and have not yet been approved). As indicated in the April 7, 1986 letter, due to concerns raised by the NRC the McGuire amendments did not include that i
portion of the request which would change the Technical Specification Table 3.3-1 action statement (from action statement 11 to proposed action state-ment 6) and minimum channels operable'(from 1 to 4) for Item 16b " Turbine j
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Mr. Harold R. Denton, Director June 12, 1986 Page 2 Trip / Turbine Stop Valve Closure". This portion of the request was not concluded pending further consideration and potential alteration of the proposed change by Duke Power Company. Note also that.another portion of
.the request which would modify Technical Specification Table 3.3-1 action
+
statement 9 so as to increase (from 2 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) the time one channel may 1
be bypassed to allow testing was not included in the McGuire amendments as j
that portion of the request had been intended to be deleted from the sub-l mittal for the reasons outlined in the April 7, 1986 letter.
Duke has concluded its review of the McGuire Turbine Trip / Turbine Stop Valve Closure portion of the request and concluded that that portion is not appropriate. Consequently Duke rescinds the requested changes previously j
proposed for Item 16b (including deletion of action statement 11) of McGuire Technical Specification Table 3.3-1.
However, it is noted that the current-ly applicable action statement (i.e. No. 11) for Turbine Trip / Turbine Stop Valve Closure on McGuire Technical Specification Table 3.3-1 contains a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provision to accomplish the action. Therefore, in accordance with similar type changes (already approved on McGuire) contained in the July 22, 1985 submittal it is requested that the time allowed by action statement 11 be changed from I hour to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Attachment 1A provides the proposed McGuire Unit 1/2 Technical Specification changes (note that previously l
proposed changes issued by amendments 54/35 are already reflected in the current McGuire Unit 1/2 Technical Specification pages used in the attachment. Also, no further changes to the Technical Specification Bases pages are required for this change). Justification for this type change is i
provided in WCAP-10271 and further discussed in the July 22, 1985 submittal and April 7, 1986 SER. The previously provided technical bases and Significant Hazards Considerations remain valid.
i Duke considers the above proposed change resulting from resolution of the l
McGuire concern to be applicable to Catawba also. In addition, the portion of the previously proposed changes which would change Catawba Technical Specification Table 3.3-1 action statement 9 to increase from 2 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the time one channel may be bypassed to allow testing should be deleted for similar reasons as those indicated in the April 7, 1986 McGuire amendments 54/35 issuance letter. Accordingly, Attachment 1B contains suitably revised pages to the previously proposed Catawba Technical Specification changes i
reflecting these positions (note that current Catawba Unit 1/2 Technical Specification pages are used in the attachment as opposed to the outdated Unit 1 only pages used in the previous submittals. Again, no further changes to the Technical Specification Bases pages from those previously proposed are required). As noted above, the proposed changes previously provided had been pre-noticed for Catawba Unit 1 by the Federal Register j
notice of Jecember 18, 1985, and Duke had subsequently requested (via March 7,1986 letter) that these previously proposed changes for Catawba Unit 1 also apply to Unit 2.
This request also should be extended to the revision provided by Attachment IB.
The previously provided significant hazards I
considerations remain valid for this revision.
- -. ~.. - - --
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Mr. Harold R. Denton, Director June 12, 1986 Page 3 It is requested that this change be processed in a timely manner for McGuire, and that the NRC proceed in a timely manner with the issuance of i
the proposed RTS A0r relief changes (as revised by this letter) on both Catawba units.
This letter contains information which supplements that which was provided by my letter dated July 22, 1985 (portions of which are still currently under review) and is bounded by the analyses of that submittal. As such, no addition justification and safety analyses, significant hazards considera-tion, or amendment fees are necessary. Should there by any questions or if i
additional information is required, please advise.
Very truly yours, tY$.
lf Hal B. Tucker PBN/jgm L
Attachments xc:
Dr. J. Nelson Grace Mr. Heyward G. Shealy, Chief Regional Administrator Bureau of Radiological Health U.S. NRC S.C. Dept. of Health &
101 Marietta Street, NW, Suite 2900 Environmental Control Atlanta, Georgia 30323 2600 Bull Street Columbus, S.C.
29201 Mr. Darl Hood, Project Manager Division of Licensing Mr. Dayne Brown, Chief Office of Nuclear Reactor Regulation Radiation Protection Branch U.S. Nuclear Regulatory Coussission Division of Facility Services Washington, D.C.
20555 Dept. of Human Resources P.O. Box 12200 Mr. W.T. Orders Raleigh, N.C.
27605 Senior Resident Inspector McGuire Nuclear Station Dr. K.N. Jabbour, Project Mngr.
Office of Nuclear Reactor Reg.
Mr. P.H. Skinner U.S. Nuclear Regulatory Comm.
Senior Resident Inspector Washington, D.C.
20555 Catawba Nuclear Station s
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o ATTACHMENT 1A PROPOSED McGUIRE UNIT 1 AND 2 TECHNICAL SPECIFICATION C11ANGES
O 1
I TABLE 3.3-1 (Continued) 1 Es REACTOR TRIP SYSTEM INSTRUMENTATION c
E MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE OF CHANNELS 10 1 RIP OPERA 8LE N00ES ACTION s
l g
FUNCTIONAL UNIT i
- 14. Undervoltage-Reactor Coolant 6,
Pumps (above P-7) 4-1/ bus 2
3 1
l w
i S
j n
- 15. Underfrequency-Reactor Coolant 6,
Pumps (above P-7) 4-1/ bus 2
3 1
m l
16.
Turbine Trip 6,
l T
l a.
Low Fluid Oil Pressure 3
2 2
1 b.
Turbine Stop Valve Closure 4
4 1
1 11#
17 Safety Injection Input 2
1 2
1, 2 9
from ESF wk w
18.
Reactor Trip System Interlocks a.
Intermediate Range 2,,
8 Neutron Flux, P-6 2
1 2_
b.
Low Power Reactor l
Trips Block, P-7 P-10 Input 4
2 3
1 8
l or' j
j
[{
P-13 Input 2
1 2
1 8
D hh 4
2 3
1 8
I&
c.
Power Range Neutron l
yy Flux, P-8 t O N
1 f $i EE d.
Low Setpoint Power
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Range Neutron Flux, P-10 4
2 3
1, 2 8
r hj w
4 R i
w" Turbine Impulse Chamber Yh.
i EE Pressure, P-13
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2' 1
2 1
8 l
e.
^
in
.gl 5s/
ec g
.i
t'
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j TABLE 3.3-1 (Continued)
REACIOR TRIP SYSTEM INSTRUMENTATION sR MINIMUM TOTAL N0.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE M00ES ACTION e5d 19.
Reactor Trip Breakers 2
1 2
1 2 9
A 2
1 2
3, 4*,
5*
10 i
k
- 20. Automatic Trip and Interlock 2
1 2
I 2 9
Logic 2
1 2
3g, 4*, 5*
10 m
I R
y n
ya
- r n i
.h I }
Od e-10 (4
/
TA8LE 3.'3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 9 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERA 8LE.
ACTION 10 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
ACTION 11 - With the number of OPERA 8LE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within)6Y houci l
McGUIRE - UNITS 1 and 2 3/4 3-8 A 8 4~ese~ r uc.
(w~,r o A ~a~cm~ r no.
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9 ATTACHMENT 1B REVISED PROPOSED CATAWBA UNIT 1 (AND 2) TECHNICAL SPECIFICATION PAGES
l TABLE 3.3-1 (Continued) 4 1
REACTOR TRIP SYSTEM INSTRUMENTATION l
MINIMlM TOTAL NO.
CHANNELS CHANNELS APPLICA8LE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE N00ES ACTION m
10.
Pressurizer Pressure-High 4
2 3
1, 2 6# *
- l e*
11.
Pressurizer Water Level-High 3
2 2
1 6 /#
l 12.
Reactor Coolant Flow-Low a.
Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1
6 /#
I l
any oper-each oper-j ating loop ating loop j
i b.
Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1
6f#
l below P-8) two oper-each oper-ating loops ating loop w
i 5
ty 13.
Steam Generator Water 4/sta 2/sta gen 3/sta gen 1, 2 6#88 l
w Level--Low-Low gen in any each l
operating operating sta gen sta gen i
~
2 3
1 6# 8 "
l
- 14. Undervoltage-Reactor Coolant 4-1/ bus
)
Pumps (Above P-7)
- 15. Underfrequency-Reactor Coolant 4-1/ bus 2
3 1
6#
i Pumps (Above P-7) t h
- 16. Turbine Trip 3.1 a.1 Low Control Valve EH Pressure 4
2 3
1####
6 /#
I l
$1
- (Unit 1) i
?1 a.2 Stop Valve EH Pressure 4
2 3
1####
6<7#
l T&
- Low (Unit 2) b.
Turbine Stop Valve Closure 4
4 1
1####
11#
l g}
l 17.
Safety Injection Input f{
from ESF 2
1 2
1, 2 9
i CC
TABLE 3.3-1 (Continued)
O REACTOR TRIP SYSTEM INSTRUNENTATION
>b MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE MODES ACTION c-Ld 18.
Reactor Trip System Interlocks a.
Intermediate Range Neutron Flux, P-6 2
1 2
2##
8 e
e.
m b.
Low Power Reactor Trips Block, P-7 P-10 Input 4
2 3
1 8
or P-13 Input 2
1 2
1 8
j c.
Power Range Neutron l
Flux, P-8 4
2 3
1 8
w1 d.
Power Range Neutron 4
2 3
1 8
l w
i a
Flux, P-9 I
i e.
Power Range Neutron Flux, P-10 4
2 3
1 8
l f.
Power Range Neutron Flux, Not P-10 4
3 4
1, 2 8
g.
Turbine Impulse Chamber Pressure, P-13 2
1 2
1 8
A 19.
Reactor Trip Breakers 2
1 2
1, 2 9
2 1
2 3*, 4*, 5*
10 7 ?<
o 20.
Automatic Trip and Interlock 2
'1 2
1, 2 9
A nj Logic 2
1 2
3*, 4*, 5*
10 l i, f 5I t
0 l
O
^
TA8LE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 4 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERA 8LE requirement, suspend all operations involving positive reactivity changes.
ACTION 5 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers, suspend all operations involving positive reactivity changes and verify Valves NV-231, NV-237, NV-241, and NV-244 are closed and secured in position within the next hour.
ACTION'6 - With the number of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition i
within J houry, and l
6 j
b.
The Minimum Channels OPERA 8LE requirement is met; however, i
the inoperable channel may be bypassed for up to y't hours l
for surveillance testing of other channels per Specification 4.3.1.1.
6 ACTION 7 -humber of OPERA 8LE channels one less than.the Totat-l Number of Channew;,-STMTU and/or POWER OPERATION may proceed l
g,p until performance of the_next-red ANALOG CHANNEL OPERATIONAL TEST providad-the~ inoperable channel is piaced-titthe tripped j
p tiofwithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
I ACTION 8 - With less than the Minimus Number of Channels OPERA 8LE, within I hour determine by observation of the associated permissive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 9 - With the number of OPERA 8LE channels one less than the Minimum l
Channels OPERA 8LE requirement, be in at least HOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERA 8LE.
ACTION 10 -With the number of OPERA 8LE channels one less than the Minimum Channels OPERA 8LE requirement, restore the inoperable channel l
to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
ACTION 11 -With the number of OPERA 8LE channels less than the Total Number of Channels, operation may continue provided the inoperable channelsareplacedinthetrippedconditionwithin{hourf l
i CATAWBA - UNITS 1 & 2 3/4 3-6 n +,~<.,r -
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