ML20065F528
| ML20065F528 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/31/1994 |
| From: | DUKE POWER CO. |
| To: | |
| References | |
| PROC-940131, NUDOCS 9404110369 | |
| Download: ML20065F528 (29) | |
Text
-. _ _ _ _ -. - _ _ _ _ _. _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _. _ _ _ _ _
DISPOSITION OF THE ORIGINAL PRIORITY NORMAL Q,ME WILL
,L S8GNATU LEED RECIP9ENT IS OTHERWISE DUKE POWER COMPANY 03/17/94
,11) 0085 G A COPP EC050 DATE:
12'997
!?) 2702 U N MATTHEWS MG03EE DOCUMENTTRANSMITTALFORM DOCUMENT TRANSMITTAL *
- 0)1236 0 V ETHINGTON EC13G a4)4409 S A GEWEHR EC050 "M
- !51 1437 P F GUILL COMPLIANCE MG01RC
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!s)3718 MCG CHEM SHIFT GEN SUPV MG01CH OA COhDmON YES hNO
.f7)3133 M E PACETTI MG02ME
REFERENCE:
&O hYES py i8) 1896 J S MURANSKY EC08H OmER ACKNOWLEDGEMENTREQUIRED i9) 0777 T A REED, ONRR WASH DC MCGUIRE NUCLEAR STATION W QA OR OTHER ACKNOWLEDGEMENT REQUIRED. PLEASE F
@ o*MRECEIPT BY RETURNING THIS FORM OR DPC
^
1 10)3609 L K CRIMINGER RP SUPV MG01RP SELECTED LICENSE COMMITHENTS
- 11: 3744 MCG DIR SIM (MCGINNIS) MG030T MANUAL McGuere Nuclear Station W
'12)3044 MCG DOC CNTRL MISC MAN MG02DM PO. Box 12700
'"'"*"',",*",*f","y*n"'>ad Q
1310422 MCG SAFETY REVIEW GROUP MG01SR
- 4)5879 G C DOVER CNOIRC Huntersvdle. North Carolina 28078
'15)0322 M D LANE MG03A2 16)1468 R R WEIDLER MG02ME Reca sy Date
- f437!5D[S$ NUCLEARTREGiWASH,T! DCL;l~lY
'1810297 REGION ADMINISTRATIOR REG II PAGE 1 0F 4
j DOCUMENT NO.-
cst O
C ND D
C
- MCGUIRE NUCLEAR STATION NA 03/17/94 MADM-03 V1 V1 V1 U1 V1 V1 V1 V1 V1 V1 V2 V7 V2 V1 V1 V1 V7 V1 71 SELECTED LICENSE COMMITMENTS NA MANUAL NA I
LOEP 1,2 NA PAGES 16.5-1 NA PAGES 16.5-2 NA STAMF DO :UMENTS/ MANUALS
% 0REING COPY CONTROLLED REMARKS:
REPLACE PAGES 1, 2 0F LOEP & PAGES 16.5-1 & 16.5-2
[b T C MCMEEKIN
/ jl VICE PRESIDENT d
MCGUIRE NUCLEAR STATION 050010 BY L J KUNKA LJK/CDC MG01RC
1 O
McGuire Nuclear Station
'l Selected Licensee Commitments List of Effective Pages Py Revision Date L0EP Tab L0EP 1:
01/94-
.L0EP 2 01/94 i
L0EP 3 10/90.
^
L0EP 4 1/92.
L0EP 5 1/92 LOEP 6 2/91 L0EP'7-9/93' f
L0EP 8.
.12/93 L0EP 9 12/93 L0EP 10 9/93 Tab'16.0 16.0-1 16.0-2 Tab 16.1 16.1-1 1
Tab 16.2 16.2-1 3/91 16.2-2 5/91 16.2-3.
16.2-4 Tab 16.3
'01/94 Page 1
-.,n.
(
4 hP
[
Revision Date b
_ age o
(16.3-1 1
Tab 16.4 Tab-16.5 16.5-1 01/94 i-i-
16.5-2 01/94 t
4 r
- i
'16.5-3 3/93 l
16.5-4 3/93 i
16.5-5 3/93 16.5-6 3/93 i
16.5-7 3/93.
j 16.5-8 3/93 16.5-9 3/93
.16.5-10 3/93 1
i I
Tab 16.6 t
Tab 16.7 l
16.7-1 Tab 16.8 i
16.8-1 10/90 i
Table 16.8-la 1 of 39 10/90-Table 16.8-la 2 of.39 10/90 Table 16.8-la 3 of 39 10/90 Table 16.8-la-4 of 39-10/90 Table 16.8-la 5 of 39 10/90 Table 16.8-la 6 of 39 10/90 t
01/94 Page 2
16.5 REACTOR COOLANT SYSTEM REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less than 60" Wide Range NC system level, the following conditions shall be met:
a.
If steam generator (S/G) nozzle dams are in use, at least one hot leg vent path shall remain open whenever the reactor vessel head is in place.
The vent path may be satisfied by no hot leg nozzle dam installed and removal of either:
- 1. hot leg diaphram and manway or
- 2. cold leg diaphram and manway in the vented loop.
b.
If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
hot leg S/G manway and diaphragm (no hot leg nozzle dam) or 2. no hot leg nozzle dam and cold leg manway and diaphragm in the same steam generator or by the
/~sT removal of the reactor vessel head.
A detailed review of each outage schedule which c.
involves operation at reduced inventory shall be conducted, looking in particular at evolutions which could perturb the NCS.
d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor, The reactor has been subcritical for at least 7 days; e.
or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218.
REMEDIAL ACTIONS:
a.
With the vent paths of 16.5-la and b not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.
O O
16.5-1 01/94
A
\\
b.
If the vent path of 16.5-1b cannot be provided, ensure
(\\__)
containment closure can be achieved prior to the onset of core boiling and suspend any activities that may reduce NCS inventory.
TESTING REQUIREMENTS:
None
REFERENCES:
1)
Generic Letter 88-17, Loss of Decay. Heat Removal 2)
NUREG 1410, Loss of Vital AC Power and Residual Heat Removal During Mid-Loop Operation at Vogtle 3)
Integrated Scheduling Management Procedure 3.1, Outage Planning and Execution Responsibilities 4)
McGuire Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5)
McGuire Station Directive 3.1.3 (MSD403) Shutdown Risk g-~s Management Guidelines k
) 6)
N/
Design Study:
CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By Decay Heat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services 7)
Design Study:
MGDS-0228/CNDS-0218, McGuire/ Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department BASIS:
Generic Letter 88-17 and NUREG 1410 involve concerns associated with a loss of Residual Heat Removal during NC system reduced inventory.
Numerous events have occurred in the industry that resulted in a loss of residual heat removal during reduced inventory operation.
This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.
This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.
j'}
16.5-2 01/94 i
i
i l
McGuire Nuclear Station O
Selected Licensee Comitments List of Effective Pages P_ age Revision Date L0EP Tab L0EP 1 01/94 L0EP'2 01/94 LOEP 3 10/90 L0EP 4 1/92 L0EP.5 1/92 L0EP 6 2/91 L0EP 7 9/93 LOEP 8 12/93 L0EP 9 12/93 L0EP 10 9/93 Tab 16.0 16.0-1 16.0-2 Tab 16.1 16.1-1 Tab 16'.2 16.2-1 3/91 16.2-2 5/91
~16.2-3 j
16.2-4 Tab 16.3 01/94 Page 1
7.....-
~.
~ ~
l:
i
'i P_ag.e Revision Date
.16.3 Tab'16.4 Tab 16.5 16.5-1 01/94 16.5 01/94 16.5-3 3/93 16.5-4~
3/93 l
~
l
-16.5-5
.3/93 l
.16.5-6 3/93 16.5-7.
3/93
(
16.5-8
'3/93 l
16.5-9 3/93 L
16.5-10 3/93 Tab 16.6 Tab 16.7 16.7-1 Tab 16.8 16.8-1 10/90 Table 16.8-la 1 of 39 10/90 Table 16.8-la 2 of 39 10/90 Table 16.8-la 3 of 39 10/90 i
Table 16.8-la 4 of 39 10/90 Table 16.8-la 5 of 39-10/90 Table 16.8-la 6 of 39 10/90 01/94 1
Page 2
.- -... ~.. -....
[
16.5 REACTOR COOLANT SYSTEM REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less than 60" Wide Range NC system level, the following conditions shall be met:
a.
If steam generator (S/G) nozzle dams are in use, at least one hot leg vent path shall remain open whenever the reactor vessel head is in place.
The vent path may be satisfied by no hot leg nozzle dam installed and removal of either:
1.
hot leg diaphram and manway or 2.
cold leg diaphram and manway in the vented loop.
b.
If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
hot leg S/G manway and diaphragm (no hot leg nozzle dam) or 2.
no hot log nozzle dam and cold leg manway p ~x and diaphragm in the same steam generator or by the
}
removal of the reactor vessel head, c.
A detailed review of each outage schedule which involves operation at reduced inventory shall be conducted, looking in particular at evolutions which l
could perturb the NCS.
d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor.
The reactor has been subcritical for at least 7 days; e.
or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218.
REMEDIAL ACTIONS:
a.
With the vent paths of 16.5-la and b not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.
C\\
\\\\ ')
16.5-1 01/94
l l
l l
)
b.
If the vent path of 16.5-1b cannot be provided, ensure l
(_,/
containment closure can be achieved prior to the onset of core boiling and suspend any activities that may reduce NCS inventory, i
TESTING REQUIREMENTS:
None l
REFERENCES:
1)
Generic Letter 88-17, Loss of Decay Heat Removal 2)
NUREG 1410, Loss of Vital AC Power and Residual Heat Removal During Mid-Loop Operation at Vogtle 3)
Integrated Scheduling Management Procedure s.1, Outage l
Planning and Execution Responsibilities l
l 4)
McGuire Ruclear Station responses to Generic Letter 88-17 dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5)
McGuire Station Directive 3.1.3 (MSD403) Shutdown Risk gs Management Guidelines
(
4
\\m /
6)
Design Study:
CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By Decay Heat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services 7)
Design Study:
MGDS-0228/CNDS-0218, McGuire/ Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department BASIS:
Generic Letter 88-17 and NUREG 1410 involve concerns associated with a loss of Residual Heat Removal during NC system reduced inventory.
Numerous events have occurred in the industry that resulted in a loss of residual heat removal during reduced inventory operation.
This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.
This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.
/N
\\\\>')
16.5-2 01/94
o
.McGuire Nuclear Station Selected Licensee Connitments List of Effective Pages
. Pag.e Revision Date L0EP Tab L0EP 1 01/94' LOEP 2 01/94 L0EP 3
.10/90 L0EP 4 1/92 LOEP 5
- 1/92 L0EP 6 2/91 L0EP 7 9/93-L0EP 8 12/93 L0EP 9
'12/93 L0EP 10 9/93..
Tab 16.0 i
l 16.0-1 16.0-2 i
Tab 16.1 l
16.1-1 Tab-16~.2 16.2-1 3/91 16.2-2 5/91 16.2-3 16.2-4 l
()
' Tab 16.3 l-01/94 l
l Page 1 l-
i-l.
P_ag_e Revision Date-1
-16.3-1 1-
}
-Tab 16.4 1:
l
. Tab 16.5 a,
i 16.5-1 01/94 l
i 16.5 '01/94; l
16.5-3
.3/93 l
16.5-4 3/93 1-j 16.5-5 3/93 l
1-16.5-6 3/93.
- j.,
l 16.5-7
-3/93 v -.
l 16.5 -3/93 l
1
-16.5-9 3/93 L
16.5-10 3/93 l
l Tab 16.6 E
4 Tab-16.7 i
16.7-1 i
l l
Tab 16.8
..+
1
~
16.8-1 10/90-
{-
1 i
j..
Table 16.8-la 1 of'39 10/90 i
t' Table 16.8-la 2 of 39 10/90 f
l j
Table 16.8-la 3 of 39 10/90 i
Table 16.8-la 4 of 39 10/90-1 Table 16.8-la 5 of 39-10/90 j
a 1
Table 16.8-la 6 of 39 10/90 l
01/94
[
ll Page 2 1
.... L....
8 O
5 16.5 REACTOR COOLANT SYSTEM REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE l
l 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less 4
than 60" Wide Range NC system level, the following conditions shall be met:
e a.
If steam generator (S/G) nozzle dams are in use, at l
least one hot leg vent path shall remain open whenever
}
the reactor vessel head is in place.
The vent path may i
be satisfied by no hot leg nozzle dam installed and j
removal of either:
- 1. hot leg diaphram and manway or
- 2. cold log diaphram and manway in the vented loop.
b.
If the reactor coolant system cold leg side.is to be opened with total openings of one square inch or j
greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
j hot leg S/G manway and diaphragm (no hot leg nozzle dam) or 2.
no hot leg nozzle dam and cold leg manway l
and diaphragm in the same steam generator or by the removal of the reactor vessel head.
c.
A detailed review of each. outage schedule which involves operation at reduced inventory shall be j
conducted, looking in particular at evolutions which could perturb the NCS.
d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor.
The reactor has been subcritical for at least 7 days; e.
j or as specified in Design Study CNDS-G;,2 based on unit
~
rated power operation time; or as specified in Design i
Study MGDS-0228/CNDS-0218.
i j
REMEDIAL ACTIONS:
i a.
With the vent paths of 16.5-la and b not available immediately initiate action to provide the required hot j
leg vent path and suspend all activities which may perturb NCS level or which may reduce the-reliability of the operating ND Loop.
i-
['
f s-16.5-1 01/94 i
e i
i
-O' b.
If the vent path of'16.5-lb cannot be provided, ensure containment closure.can be achievod prior to the onset-of core boiling and:' suspend any activities-tnat may reduce NCS inventory.
TESTING REQUIREMENTS:
None
REFERENCES:
1)'
Generic Letter 88-17, Loss of Decay Heat Removal 2)
NUREG 1410, Loss of Vital AC Power and: Residual-Heat: Removal During Mid-Loop Operation at Vogtle 3)
Integrated Scheduling Management Procedure 3.1,' Outage Planning-and' Execution Responsibilities-4)
McGuire Nuclear Station responses to Generic Letter 88-17' dated January 3, 1989, February 2, 1989, March-10, 1989 and February 24,.1993.
5)
McGuire Station Directive 3.1.~3-(MSD403) Shutdown Risk Management Guidelines O
6)
Design Study:
CNDS-0242, Catawba and McGuire: Nuclear" Stations, Shutdown By Decay Heat? Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services
'7 )
Design Study:
MGDS-0228/CNDS-0218,'McGuire/ Catawba Nuclear Stations, Loss of Decay Heat RemovalLWith Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department
]
BASIS:
Generic Letter 88-17 and NUREG 1410 involve concerns associated with.a: loss of' Residual Heat Removal during NC system reduced' inventory.
Numerous events have occurred in the industry that resulted in a loss of. residual heat removal.during reduced-
)
inventory operation.
This-is of' great concern due to the.
potential for substantial core damage occurring in a relatively; short time period.
This Selected Licensee Commitment depicts-those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.
16.5-2 01/14
=.
i.
McGuire Nuclear Station i
Selected Licensee Comitments i
i List of Effective Pages l
.PR Revision Date l
L0EP Tab LOEP 1 01/94 i
L0EP 2 01/94 i
f j
L0EP 3 10/90 j
L0EP 4 1/92 1
j, L0EP 5 1/92 LOEP 6 2/91 i
LOEP 7 9/93 j
L0EP 8 12/93 i
LOEP 9 12/93 L0EP 10 9/93 i
Tab 16.0 16.0-1 16.0-2 i
L Tab 16.1 16.1-1 Tab 16.2-16.2-1 3/91 16.2-2 5/91-
- l 16.2-3 16.2-4 Tab 16.3 01/94:
Page 1 eWb T
4
-.*-e w
rm
-e
- - ~.. - -
=
1 i
j j
i i
Page Revision Date
. 16.3-1 j
Tab 16.4 i
Tab 16.5 16.5-1 01/94
[
16.5-2 01/94-.
i j
16.5-3 3/93' 1
t 16.5-4 3/93 l
16.5-5 3/93 i
i 16.5-6 3/93 1
l 16.5-7 3/93 t
i 16.5-8 3/93 16.5-9 3/93 1
)
16.5-10 3/93 Tab 16.6 Tab 16.7 16.7-1 Tab 16.8 l
1-16.8-1 10/90 Table 16.8-la 1 of 39 10/90 l
Table 16.8-la 2 of 39 10/90 4
i Table 16.8-la 3 of 39 10/90 Table 16.8-la 4 of 39 10/90 Table 16.8-la 5 of 39 10/90 r
Table 16.8-la 6 of 39 10/90 01/94-l Page 2 i
-e n
,-,-.,-,..e.+
16.5 REACTOR COOLANT SYSTEM REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less than 60" Wide Range NC system level, the following conditions shall be met:
a.
If steam generator (S/G) nozzle dams are in use, at least one hot leg vent path shall remain open whenever the reactor vessel head is in place.
The vent path may be satisfied by no hot leg nozzle dam installed and removal of either:
- 1. hot leg diaphram and manway or 2.
cold leg diaphram and manway in the vented loop.
b.
If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
hot leg S/G manway and diaphragm (no hot leg nozzle dam) or 2.
no hot leg nozzle dam and cold leg manway f-~s and diaphragm in the same steam generator or by the
)
removal of the reactor vessel head.
(V c.
A detailed review of each outage schedule which involves operation at reduced inventory shall be conducted, looking in particular at evolutions which could perturb the NCS.
d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor, e.
The reactor has been subcritical for at least 7 days; or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218.
REMEDIAL ACTIONS:
a.
With the vent paths of 16.5-la and b not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.
O N
16.5-1 01/94
,~[
T b.
If the vent path of 16.5-1b cannot be provided, ensure
\\_-)
containment closure can be achieved prior to the onset of core boiling and suspend any activities that may reduce NCS inventory.
TESTING REQUIREMENTS:
None
REFERENCES:
1)
Generic Letter 88-17, Loss of Decay Heat Removal 2)
NUREG 1410, Loss of Vital AC Power and Residual Heat Removal During Mid-Loop Operation at Vogtle 3)
Integrated Scheduling Management Procedure 3.1, Outage Planning and Execution Responsibilities 4)
McGuire Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5)
McGuire Station Directive 3.1.3 (MSD403) Shutdown Risk y'"
Management Guidelines 6)
Design Study:
CNDS-0242, Catawba and McGuire Nuclear
-s Stations, Shutdown By Decay Hoat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services 7)
Design Study:
MGDS-0228/CNDS-0218, McGuire/ Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department BASIS:
Generic Letter 88-17 and NUREG 1410 involve concerns associated with a loss of Residual Heat Removal during NC system reduced inventory.
Numerous events have occurred in the industry that resulted in a loss of residual heat removal during reduced inventory operation.
This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.
This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.
p
\\
l 16.5-2 01/94
l l
McGuire Nuclear Station i
Selected Licensee Commitments List of Effective Pages Pm Revision Date LOEP Tab L0EP 1 01/94 L0EP 2 01/94 LOEP 3 10/90 L0EP 4 1/92 L0EP 5 1/92 LOEP 6 2/91 L0EP 7 9/93 L0EP 8 12/93 L0EP 9 12/93 L0EP 10 9/93 Tab 16.0 16.0-1 16.0-2 Tab 16.1
- 16. *,
Tab 16.2 16.2-1 3/91 16.2-2 5/91 16.2-3 16.2-4 Tab 16.3 01/94 Page 1
--<4--
e i
1 Page Revision Date 16.3-1 Tab 16.4 i
l.
Tab 16.5 16.5-1 01/94-l 16.5-2 01/94 l:
-16.5-3 3/93 16.5-4 3/93 l
1 16.5-5.
3/93' 16.5-6 3/93 16.5-7 3/93 16.5-8 3/93
'16.5-9 3/93 16.5-10 3/93 Tab 16.6 Tab 16.7 16.7-1 Tab 16.8 16.8 10/90 Table 16.8-la 1 of 39 10/90 Table 16.8-la 2 of 39 10/90 Table 16.8-la 3 of 39 10/90 Table 16.8-la 4 of 39 10/90 Table 16.8-la 5 of 39 10/90 O
g g Table 16 8-la 6 of 39 10/90 01/94 Page 2
[~'
16.5 REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less than 60" Wide Range NC system level, the following conditions shall be met:
a.
If steam generator (S/G) nozzle dams are in use, at least one hot leg vent path shall remain open whenever the reactor vessel head is in place.
The vent path may be satisfied by no hot leg nozzle dam installed and removal of either:
1.
hot leg diaphram and manway or
- 2. cold leg diaphram and manway in the vented loop.
b.
If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
hot leg S/G manway and diaphragm (no hot leg nozzle dam) or 2. no hot leg nozzle dam and cold leg manway
[O-s) and diaphragm in the same steam generator or by the removal of the reactor vessel head.
c.
A detailed review of each outage schedule which involves operation at reduced inventory shall be conducted, looking in particular at evolutions which could perturb the NCS.
d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor.
The reactor has been subcritical for at least 7 days; e.
or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218.
REMEDIAL ACTIONS:
a.
With the vent paths of 16.5-la and b not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.
/T
/
l l
N' 16.5-1 01/94 t
l i
[
b.
If the vent path of 16.5-1b cannot be provided, ensure
\\
containment closure can be achieved prior to the onset j
of core boiling and suspend any activities that may reduce NCS inventory.
1 TESTING REQUIREMENTS:
None
REFERENCES:
1)
Generic Letter 88-17, Loss of Decay Heat Removal 2)
NUREG 1410, Loss of Vital AC Power and-Residual Heat Removal During Mid-Loop Operation at Vogtle i
3)
Integrated Scheduling Management Procedure'3.1, Outage Planning and Execution Responsibilities-4)
McGuire Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24,_1993.
5)
McGuire Station-Directive 3.1.3-(MSD403) Shutdown Risk
-~s Management Guidelines-(
\\
\\m-6)
Design Study:
CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By Decay Heat Level Before Mid-Loop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services 7)
Design Study:
MGDS-0228/CNDS-0218,.McGuire/ Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department BASIS:
Generic Letter 88-17 and NUREG 1410 involve concerns associated with a_ loss of Residual Heat Removal during NC system reduced inventory.
Numerous events have occurred in the industry that 3"
resulted in a loss of residual heat _ removal during reduced
}
inventory operation.
This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.
This selected Licensee Commitment depicts 4
those commitments which are extremely important'to nuclear safety, however, are not presently covered by Technical' Specifications.
[\\
16.5-2 01/94 3
6 s
lf l'
McGuire Nuclear Station l
Selected Licensee Comitments l
List of Effect.ve Pages i
l-M Revision'Date L0EP Tab L0EP 1 01/94 i
IJ L0EP 2 01/94 i
L0EP 3 10/90 l
f L0EP 4 1/92 L0EP 5 1/92 i
L0EP 6 2/91 L0EP 7 9/93 LOEP 8 12/93 l
LOEP 9 12/93 LOEP 10 9/93 Tab 16.0 16.0-1 16.0-2 Tab 16.1 16.1-1 Tab 16.2 16.2-1 3/91 16.2-2 5/91 16.2-3 16.2-4 Tab 16.3 01/94 Page 1
4 i
P_ age '
Revision Date 16.3-1 Tab 16.4
' Tab 16.5 16.5-1 01/94 16.5-2 01/94 16.5-3 3/93 16.5-4.
3/93 16.5-5 3/93 16.5-6' 3/93 16.5-7 3/93 16.5-8 3/93 16.5-9 3/93 16.5-10 3/93 Tab 16.6 Tab 16.7 16.7-1 Tab 16.8 16.8-1 10/90 Table 16.8-la 1 of 39 10/90 i
Table 16'8-la 2 of 39-10/90 lable 16.8-la 3'of 39 10/90 Table 16.8-la 4 of 39 10/90 Table 16.6-la 5 of 39 10/90 Table 16.8-la 6 of 39 10/90 01/94 Page 2
9 16.5 REACTOR COOLANT SYSTEM
[O REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMITMENT Prior to reducing the Reactor Coolant System (NC) level to less than 60" Wide Range NC system level, the following conditions shall be met:
a.
If steam generator (S/G) nozzle dams are in use, at least one hot leg vent path shall remain open whenever the reactor vessel head is in place.
The vent path may be satisfied by no hot leg nozzle dam installed and removal of either:
1.
hot leg diaphram and manway or
- 2. cold leg diaphram and manway in the vented loop.
b.
If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
hot leg S/G manway and diaphragm (no hot leg nozzle t
dam) or 2. no hot leg nozzle dam and cold leg manway and diaphragm in the same steam generator or by the j
7-ss removal of the reactor vessel head.
c.
A detailed review of each outage schedule which involves operation at reduced inventory shall be conducted, looking in particular at evolutions which could perturb the NCS.
1 l
i d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor.
The reactor has been subcritical for at least 7 days e.
or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218.
REMEDIAL ACTIONS:
a.
With the vent paths of 16.5-la and b not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.
N 16.5-1 01/94
l,
-j a
i
'j i
b.
If the vent path of 16.'5-1b cannot be provided, ensure l
\\_/
containment closure can be achieved prior to the onset of core boiling'and suspend-any activities that may reduce NCS' inventory.
TESTING REQUIREMENTS:
None y
l
REFERENCES:
1)'
Generic Letter 88-17, Loss of Decay Heat Removal 2)
NUREG 1410, Loss of Vital AC Power.and Residual Heat. Removal During Mid-Loop Operation-at Vogtle 3)
Integrated Scheduling-Management' Procedure 3.1, Outage' l.
Planning-and' Execution Responsibilities I
4)
McGuire Nuclear Station responses to Generic Letter 88-17' dated January 3, 1989,. February 2, 1989, March 10,1 989 and 1
February 24, 1993.
5)
McGuire Station Directive 3.1.3'(MSD403) Shutdown Risk Management' Guidelines ew
\\ms/
6)
Design Study:
CNDS-0242, Catawba and McGuire: Nuclear Stations, Shutdown By Decay Heat' Level Before:Mid-Loop Operation, Safety Analysis, Nuclear Engineering,' Nuclear-Services 7)
Design Study:
MGDS-0228/CNDS-0218, McGuire/ Catawba: Nuclear Stations, Loss of Decay Heat Removal With Steam Generator-Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department BASIS:
Generic Letter 88-17 and NUREG 1410 involve concerns assoc'iated with a loss of Residual' Heat Removal during NC system reduced' inventory._ Numerousfevents have occurred in the industry that-i resulted.in a loss'of residual heat removal during; reduced inventory operation.- This is of great concern due to'the potential'for substantial. core damage occurring in a.relatively.
short time period.
This Selected Licensee Commitment depicts I
those commitments which are extremely important to: nuclear safety, however, are not presently covered by Technical Specifications.
16.5-2 01/94
1
- N McGuire Nuclear Station I-Selected Licensee Commitments List of Effective Pages k
Page Revision Date L0EP Tab 1
L0EP 1 01/94 l
L0EP 2 01/94 i
LOEP 3 10/90 j
L0EP 4 1/92 i
L0EP 5 1/92 i
j L0EP 6 2/91 i
i L0EP 7 9/93 i
l L0EP 8 12/93 J
d j
L0EP 9 12/93 j
L0EP 10 9/93 1
Tab 16.0 i
j 16.0-1 i
16.0-2 i
}'
Tab 16.1 2
s l
16.1-1 e
f l
Tab 16.2 16.2-1 3/91 j
16.2-2 5/91 16.2-3 f
i l
16.2-4 i
{
)
Tab 16.3 s
l 01/94
{.
l Page 1 i
--,_ _ - - _ _. _.. _,, _ _ _ _. _ -... - -... -........,...,.... -. _.... _.. ~. _ _,. - -......
l~
P_ age Revision Date l
16.3-1 l-Tab 16.4 Tab 16.5 l
16.5-1 01/94 16.5-2 01/94 l
16.5 3/93' l
l J
l 16.5-4 3/93 16.5 3/93 16'.5-6 3/93 16.5-7 3/93 l
l 16.5-8 3/93 16.5-9 3/93 16.5-10 3/93 l
Tab 16.6 l
Tab 16.7 i
16.7-1 Tab 16.8 16.8-1 10/90 Table 16.8-la 1 of 39-10/90 Table 16.8-la 2 of 39 10/90 i
Table 16.8-la 3 of 39 10/90 l
Table 16.8-la 4 of 39 10/90 Table 16.8-la 5 of 39 10/90 j
O Table 16.8-la 6 of 39 10/90 01/94 Page 2
[~'h 16.5 REACTOR COOLANT SYSTEM
~
REDUCED INVENTORY OPERATION WITH IRRADIATED FUEL IN CORE 16.5-1 INVENTORY CONTROL COMMI<TMENT Prior to reducing the Reactor Coolant System (NC) level to less than 60" Wide Range NC system level, the following conditions shall be met:
a.
If steam generator (S/G) nozzle dams are in use, at least one hot leg vent path shall remain open whenever the reactor vessel head is in place.
The vent path may be satisfied by no hot leg nozzle dam installed and removal of either:
- 1. hot leg diaphram and manway or 2.
cold leg diaphram and manway in the vented loop.
2 b.
If the reactor coolant system cold leg side is to be opened with total openings of one square inch or greater, a hot leg vent path shall be provided.
The vent path may be satisfied by the removal of either 1.
hot leg S/G manway and diaphragm (no hot leg nozzle dam) or 2.
no hot leg nozzle dam and cold leg manway and diaphragm in the same steam generator or by the
(
removal of the reactor vessel head.
\\m 4
c.
A detailed review of each outage schedule which involves operation at reduced inventory shall be conducted, looking in particular at evolutions which could perturb the NCS.
d.
Actions that could perturb the NCS during reduced inventory operation shall require prior notification of the shift supervisor.
The reactor has been subcritical for at least 7 days; e.
or as specified in Design Study CNDS-0242 based on unit rated power operation time; or as specified in Design Study MGDS-0228/CNDS-0218.
REMEDIAL ACTIONS:
a.
With the vent paths _of 16.5-la and b not available immediately initiate action to provide the required hot leg vent path and suspend all activities which may perturb NCS level or which may reduce the reliability of the operating ND Loop.
O'-s 16.5-1 01/94 4
[
b.
If the vent path of 16.5-1b cannot be provided, ensure l
l containment closure can be achieved prior to the onset of core boiling and suspend any activities that may reduce NCS inventory.
1 i
TESTING REQUIREMENTS:
None l
REFERENCES:
1 1)'
Generic Letter 88-17, Loss of Decay Heat Removal 2)'
NUREG 1410, Loss of Vital AC Pcwer and Residual Heat Removal During Mid-Loop Operation at Vogtle 3)
Integrated Scheduling Management Procedure 3.1, Outage Planning and Execution Responsibilities l
4)
McGuire Nuclear Station responses to Generic Letter 88-17 i
dated January 3, 1989, February 2, 1989, March 10, 1989 and February 24, 1993.
5)
McGuire Station Directive 3.1.3 (MSD403) Shutdown Risk l
Management Guidelines l
\\
/ 6)
Design Study:
CNDS-0242, Catawba and McGuire Nuclear Stations, Shutdown By-Decay Heat Level Before Mid-Leop Operation, Safety Analysis, Nuclear Engineering, Nuclear Services 7)
Design Study:
MGDS-0228/CNDS-0218, McGuire/ Catawba Nuclear Stations, Loss of Decay Heat Removal With Steam Generator Mitigation, Safety Analysis, Engineering Support Section, Design Engineering Department i
l BASIS:
l Generic Letter 88-17 and NUREG 1410 involve concerns associated with a loss of Residual Heat Removal during NC system reduced inventory.
Numerous events have occurred in the industry that resulted in a loss of residual heat removal during reduced inventory operation.
This is of great concern due to the potential for substantial core damage occurring in a relatively short time period.
This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently. covered by Technical Specifications.
16.5-2 01/94 I
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