ML20236L611
| ML20236L611 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/05/1987 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236L614 | List: |
| References | |
| NUDOCS 8711100465 | |
| Download: ML20236L611 (10) | |
Text
.
p aro og'o, UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
e$
WASHINGTON, D. C,20555 4,***.
g/
DUKE POWER COMPANY DOCKET NO. 50-369 I
McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY.0PERATING LICENSE i
R 1
Amendment No. 77 License No. NPF-9 1.
The Nuclear Regulatory Corn (ission~ (the Commission) has found that:
A.
The application for amendment to-the McGuire Nuclear Station,.
)
Unit 1 (the facility) Facility Operating License No..NPF-9 filed by the Duke Power. Company (the licensee) dated-June.3,1987, I
complies with the standards and requirements'of the Atomic Energy.
l Act of 1954, as amended-(the Act) and the Commission's rules and l
regulations as set forth in 10 CFR Chapter:I; B.
The facility will operate in conformity with the application, as j
l amended, the provisions of the Act, and the rules and regulations of the Commission;
.I i
C.
There is reasonable assurance (1) that the activities authorized by l
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 Commission's regulations' set forth in 10 CFR-1 Chapter I; D.
The issuance of this amendment will not be inimical to the common
.j defense and security or to the health and safety of the public; and E.
The issuance of this amendaent is in.accordance with 10 CFR' Part 51 of the Commission's-regulations and all applicable requirements have been satisfied.
4 i
i 871110046S 871105 PDR ADOCK 05000369 P
. 2.
Accordingly, the license is hereby amended by page changes to the Technical l
Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.77, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION L61 i
Lawrence P. Crocker, Acting Director Project Directorate II-3 Division of Reactor Projects I/II j
Attachment:
Technical Specification Changes
{
j Date of Issuance:
November 5, 1987 fhk/
)
be PDI&-h/DRPI/II PDII-3/DRPI/II BE1} f PDII-3/DRPI/II MDdhcan/ rad DHood
%b Acting PD i
10ffj/87 10/q$/87 1
W87 IF/2/87 l
1 L-
-(
p arroq'o -
UNITED STATES '
8 NUCLEAR REGULATORY COMMISSION o
g j
WASHINGTON, D, C. 20555 4
S
,p 0
- ..'.+9 DUKEP0WER COMPANY DOCKET NO. 50-370 Mc'GUIRE NUCLEAR FATION', UNIT 2 s
AMENDMENTiTO FACILITY OPERATING LICENSE
/
Amendment 30. 58 1.icense No. HPF-17 1.
The Nuclear Regulatory Com,ission (the Commission) has found.that:
A.
The application for; amendment to the.McGuire Nuclear Station, J
Unit 2 (the facility) Facility Doeratfng License No. NPF-17 filed by the Duke Power Company (the, licensee)>datri June 3 1987..
Act of 1954, as amerJed (the Act) quirements of the Atomic Energy complies with the standards and re and the Comission's rules and-regulations as set forth in 10 CFR Chapter I;.
B.
The facility will op'erate in confoncity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission;'
l C.
There is reasonable assurance Bi that the activities authorized.by
]
this amendment can be conducted without er;dangering the health.-and i
safety of the public, and (ii) that such activities will:.be' conducted 1
in complianco with the Comission's regulations set forth in'10 CFR l
Chapter I; j
D.
The issuance of this omendment will not be inimical to the connon defense and security or to the health and safety of Qhe 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 1
satisfied.
j 1
.t.
I a--
g.
.- =
l i
j 2.
Accordingly, the license is hereby amended by page changes to the lechnical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. hPF-17 is hereby
)
amended to read as follows:
I
'(2) Technical Specifications
)
The Technical Specifications contained in Appendix A, as.rnvised.
through Amendment No.58; are hereby incorp9 rated into the license.
The licensee shall operate the facility in accordance with the-Technical Specifications and the Environmental Protection Plan.
]
3.
This if cense amendment is effective 'as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
h Lawrence P. Crocker, Acting Director Project Directorate 11-3
)
Division of Reactor Projects 1/II
Attachment:
Technical Specification Changes
}
Date of Issuance: November 5, 1987 i
'l
{
j
(
l f,~,
Mdub)(DRPI/II
),/ DHood W)wn4 Actirg Director PDII 3 PDII-3/DRPI/II OGC-Betheyda
.PDII-3/DRPI/II h/ rad 10/jj/87 10/d/87 10/p87
//10/ 2 /87 L
1 j
L a.
{
~
J.T,
]
o u.
1,.
4 l
i i
ATTACHMENT TO I TCENSE AMENDMENT N0. 77-cl g..
6,a -
FACH.ITY OPERATING LICENSE'NO. NPF-9.
1
,s DOCET NO. 50-369 l
~
'AND T0' LICENSE AMENDMENT'NO.58'
'i FACILITY OPERATING LICENSE NO.~NPF-17.,
4
'l DOCKET NO. 50-370' a
'Replacethefollowingpagesofthe'. Appendix"A"l.TechnicalSpec'if'icati$nswith the enclosed pages. The revised pages a 3 identified by-Amendment number and contain vertical. lines indicating the 3 2as of. change. ? The corresponding over-s leaf pages are also provided to maintain document completeness.
Amended Overleaf fage y,, age I a
3/4 1-14.
- 3/4 1-13'
-l O/4 1-15 3/4'l-16 B 3/4 1-3c (new) i i
I
.j i
I i
0 0
'i
-(
^
-y 5
i d )." X
' s..
-:V l
ig:
' J: Of,
o s,,
,, a H
(-
'gpq
.p
- p
,j L
f
- ]
e,
'c s
J. REACTIVITY' CONTROL' SYSTEMS-T
.[
SURVEILLANCE REQUIREMENTS
~~
~
9; a
l 4.1.2.6. Each borat5d wat.er: source shall.be demonstrat' d OPERABLE:
e 4:
.(
a,
.At '1least once per 7, days byt
- E
'f" J
. 1)..
'a L Veri fyi r,g.' t'he! boron concentration : int the ' water,,
'3
- 2)
Ver'ifying the contained borate'd water volume' of;the.wat'ep
- 3 source', and.
t I.
,, i 3)
Verifying the Boric Acid ~. Storage lSystemJsolution temperature
~
R}
i
~
?when it:is-the bource of borated water, 3:
-b.
' At least icnce' per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' by Jverifying the RWST temperature when:
the outside' air temperature.is either less than 70*F or'.preater:than
. 100 F.
1 d'
r 4r
,}
I I'
o
\\
)
,1 i
,y i
l 1
1
. +,.
McGUIRE - UNITS 1 and 2
'3/4.1-13' i-
?.
i
___---L5--------
f.
REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1. 3.1 All full-length shutdown and control rods shall be OPERA 9'.E and positioned within 12 steps (indicated position) of their group step counLar demand position.
APPLICABILITY: MODES 1* and 2*.
ACTION:
a.
With one or more full-length rods inoperable due to being immovable as a result of excessive friction or mechanical ir,terference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in tiOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With more tnan one full-length rod mic> aligned from the group step j
counter demand position by more than 2 12 steps (indicated position),
be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With one full-length rod trippble but ir>cperable due to carses other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more then i 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:
1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The rod is declared inoperable and the remainder of the rods in the group wIth the inoperable rod are aligned to within i 12 steps of the inoperable rod while mairitaining the red sequence and insertion limits of Figure 3.1-1.
The DIERMAL POWER level l
shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, of 3.
The rod is declared inoperable and the SHUTDOWh MARGIN requirement of Specification 3.1.1.1 is satisfiad.
POWER OPERATION may then continue provided that:
a)
A reevaluation of eacn accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents reSain valid for the duration of operation under these conditions; b)
The SHUTDOWN MAF'CIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;
^$ee Special Test Exceptions 3.10.2 and 3.10.3.
l McGUIRE - UNITS 1 and 2 3/4 1-14 Amendment No.77 (Unit 1)
Amendment No.58 (Unit 2) o
h.
)
I 1
REACTIVITY CONTPOL SYSTEMS i
ACTION (Continued) l
'b c)
A power distribution map is obtained from the movable f
incoredetectorsandFpZ)andF are verified to be H
within their ?imits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and J
d)
The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next. hour and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron Flux j
Trip Setpoint is reduced to less than or equal to 85%
l of RATED THERMA! POWER.
l d.
With more than one full-length rod trippable but inoperable due to causes other than addressed by ACTION a above, POWER OPERATION may continue provided that:
j q
1.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the remainder of.the rods in the bank (s) with j
the inoperable rods are aligned to within i 12 steps of %e j
inoperable rods while maintaining the rod sequence and j
insertion limits of Figure 3.1-1.
The THERMAL POWER level i
shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.
The inoperable rods are restored to OPERABLE status within 72' l
hours.
4 i
SURVEILLANCE REQUIREMENTS l
1 l
4.1.3.1.1 The position of each full-length rod shall.be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once i
per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
i 4,1.3.1.2 Each full-length rod not fully inserted in the core shall be j
determined to be OPERABLE by movement of at least 10 steps in any one j
~
direction at least once per 31 days.
i 1
l McGUIRE - UNITS 1 anC 2 3/4 1-15 Amendment No. 77 (Unit 1)-
I Amendment No. 58 (Unit 2) l 1
TABLE 3.~1-1
~
\\
/
ACCIDENT' ANALYSES REQUIRING REEVALUATION IN THE EVENT Of AN INOPERABLE FULL-LENGTH R00 Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misalignment Loss of Reactor Coolant from Small Ruptured Pipes or'from Cracks in Large Pipes Which Actuates the Emergency. Core Cooling System Single Rod Cluster Control Assembly Withdrawal at Full Power Major Reactor Coolant System Pipe Ruptures.(Loss of Coolant Accident)
Major Secondary System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)
I i
i t.
I i
l McGUIRE - UNITS 1 and 2 3/4 1-16 l
4 1
REACTIVITY CONTROL SYSTEMS
]
BASES MOVABLE CONTROL ASSEMBLIES (Continued)
For Specification 2.1.3.1 ACTIONS c. and d., it is incumbent upon the plant personnel to verify.the trippability of the inoperable control rod (s).
This may be by verification of a control system failure, usually electrical in nature, or 'that the failure is associated with the control rod stepping' mechanism.
1 During performance of the Control' Rod Movement periodic test'(Specifica-tion 4.1.3.1.2), there have been some " Control Malfunctions".that prohibited.a control rod bank or group irom mdving when selected, as evidenced by the demand counters and DRPI*. In all cases, when the control malfunctions were corrected, the rods moved freely (no excessive friction or' mechanical interference) and-were trippable.
This surveillance test is an indirect method of verifying the control rods are not immovable or untrippable.
It is highly uniikely that a complete con-trol rod bank or bank group is immovable or untrippable.
Past surveillance and operating history provide evidence of "trippability."
Based on the above information, during performance of the rod movement test, if a complete control rod bank or group fails to move when selected and can be attributed.to a " Control Malfunction,"'the control rods can be considered
" Operable" and plant operation may continue while ACTIONS c. and d. are taken.
If one or more control rods fail to move during testing (not a complete bank or group and cannot be contributed to' a " Control Malfunction"),' the affected control rod (s) shall be declared " Inoperable" and ACTION a. taken.
(
Reference:
W letter dated December 21, 1984, NS-NRC-84-2990, E. P. Rahe to Ur. C. O. Thomas)
- Digital Rod Position Indicators
(
' McGUIRE - UNITS 1 and 2 B 3/4 1-3a
- mendment No. 77 (Unit 1)
Amendmentt No..58 (Ur.it 2)
_ -