ML20212P204
| ML20212P204 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/24/1986 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20212N983 | List:
|
| References | |
| SP-349, NUDOCS 8703160026 | |
| Download: ML20212P204 (28) | |
Text
______ - __
a Rev. 48 02/14/86 1
l Document Sect!cn N F O R M A T'i,0 N O N L h l
C. R. Nuclear J
l a
SURVEILLANCE PROCEDURE SP-349 TLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 EMER0ENCY TEEIT4ATER SYSTEM OPERABILITY DEMONSTRATICN TEIS PROCEDURE ADDRESSES SAFETT RELATED COMPONENTS TEIS PROCEDURE ADDRESSES ENVIR000ENTALLY QUALIFIED (EQ) EQUIPMENT APPROVED BY: Responsible Section Superintendent /
Supervisor
&L19 kALL Date 2 - 1. f 2L INTERPRETATION CONTACT: Nuclear Plant Engr. Supt.
t 8703160026 870305 PDR ADOCK 05000302 P
prg
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7.3 The Plant Operator should be in communication with the Control Roca during performance of this procedure.
8.0 PHEREOUTSITES 8.1 Notify the Shift Supervisor on duty prior to commencing this surveillance for
'A' train and
- B*
train.
8.2 Section 6.0 Limitations and Precautions have been read and understood.
' D '" '
f...m Cm wa Cu eca. wr ~ M= n 4, m ila- 's.-
g, s r
un gtta gusato ro acct.vt.. rt 1m Fac m C4n net. iEs.a*.:Un. r /u. 2.
9.0 TMSTRUCTIONS 9.1 Verification of oil levels:
Ini-ials NOTE: Perform the oil level verification (s) applicable only to the section to be performed.
Oil level verification for the section not performed may be marked 'N/A*.
9.1.1 Verify turbine bearing oil levels are within sight-glass casing scribe marks that are overlayed in y
black markings.
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SP-349 Rev. 4g Page 7 i
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Initials 7( avi*g L-r /.
9.1.2 Verify turbine-driven pump bearing oil levels are within the sightglass casing scribe marks that are g
j overlayed in black markings.
9.1.3 verify motor-driven pump bearing oil levels are indicating approximately aidrange.
/
9.2 PR W DRE
'A' fETP-1)
IIOTE:
Once per quarter (January, April, July and October), perform SP-370, Quarterly Cycling of
- Valves, Enclosure 1,
concurrently with this procedure.
'A*9.2.1 Insure initial conditions, Section 9.1 is complete.
N 190TE:
All data is to be recorded on Data Sheet 11.
'A*9.2.2 Close EFv-33 and 14 (EFP-1 isolation to "B"
and
'A' OTSG's).
l
[
l
'4 g Page 8 SP-349 Rev.
1 zu s.4. _.
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a
Initials "A*9.2.2.1 In the EFIC Room, inside the
'D' EFIC Aux Relay Cabinet, place the key operated test /norsal switch H
to the test position.
/
NOTE: The above step disables the EF7-33 and EIV-14 open signal from EFIC on an EFP-1 start.
'A*9.2.3 Record EFP-1 initial suction pressure and the con-densate storage tank dater level.
/
NOTE: Step 9.2.3.1 need only be performed for the initial surveillance upon a startup following a refuel outage.
N/A this step at all other occasions.
This information is required for SP-145, ETIC Time Response Testing.
l l
'A*9.2.3.1 Start a stopwatch upon performing Step 9.2.4.
1 l
1 NOTE: The stopuntch is to be stopped immediately * $ 5K when IFP-1 reaches operating pressure.
TZ~{dlCtk et.hs d d %
'A*9.2.4 Start EFP-1 by depressing the two EFW actuation EFIC Matrix pushbuttons labeled EFIC CHA to ETP-1 start logic.
/
j SP-349 Rev.
48 Page 9 4
f j
kk&mu m ~:
= = x===::-
= w y;g m F ~2 D W 8~...-
Initials s
'A'9.2.5 Verify EFP-3 Auto Started upon start of EFP-1.
Then place the EFP-3 control switch in the
'STOP" position.
I NOTE: Beariaqs "A",
'B*,
'G",
and
- H" vibrations are measured in the horizontal direction.
Bearings "C",
- D*,
- E*,
and
'F*
vibrations are measured in the vertical direction.
'A'9.2.5.1 Verify the test lights, in tr.e ' D ' EFIC Aux. Relay Cabinet indicate ETV-14 and 33 would have received an open signal had the signal not have been blocked in Step 9.2.2.1 (i.e.,
the EFV-14 and 33 pen lights are illuminated) unle EFV v fill protection is in effect.
/
'A*9.2.6 Complete Data Sheet 1A after transients have diminished.
/
'A*9.2.7 Depress the EFIC CHA to ETP-1 start logic reset pushbutton, shut down EFP-1 and record shutdown time.
/ J "A*9.2.8 Verify control switch is in the
- Normal' position.
'A*9.2.9 open EFv-33 and 14 if the valves are not receiving a l
+
close signal from an EFIC ETV overfill limit l
actuation.
l NOTE: If it is desired to open these valves, refer l
to Enclosure 3.
l SP-349 Rev.
g Page 10 9
y_.= n
._m=wn_s,=. :a :..e
Inituls
'A'9.2.10 Initial Valve Check List 1A, verifying that each valve in the flow path is in its correct position.
"A*9.2.11 Place EIP-3 control switch in " Auto *.
'A*9.2.11.1 Inside the
'D' EFIC Aux. Relay Cabinet, place the key operated test / normal switch to the normal position and return the key to the Shift Supervisor.
' A'9.2.11.2 Verify the ETV-14 and 33 test lights in the
'D' EFIC 00!f Aux Relay Cabinet are all extinguished.
"A*9.2.12 Have another person perform an independent verification of Valve Check List 1A.
' A* 9.2.13 Notify Shif t Supervisor that this surveillance for "A*
train is complete.
1
~b W
- Lklft, hl Lit Supervisor
' Dite 9.3 PROCEDURE
- B' (ETP-21 NOTE: Once per quarter (January, April, July, and I
October), perform SP-370, Quarterly Cycling of
- Yalves, Data Sheet Y
and Enclosure I
concurrently with this procedure.
/
- B'9.3.1 Notify the Shif t Supervisor prior to beginning this i
surveillance on the
'B' train.
'i
'B'9.3.2 Insure initial conditions, Section 9.1 is complete.
5
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')
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-j SP-349 Rev. Ag Page 11
-4
//
- i. 4
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c Init als
\\
10.0 erevenation 10.1 Verify that the key operated test / normal switches for the
'A' and
'B' train have been returned to the normal position.
f 11.0 C6-iin
--irs 11.1 If EFP-1 or ETP-2 does not develop sufficient discharge pressure, refer to STS Section 3.7.1.2 for limiting conditions for operation.
11.2 If there is not an operable flow path associated with either EF pump, then refer to STS Section 3.7.1.2 for limiting conditions for operation.
11.3 If reacte shutdown sonitoring channel EF-2-PI is inoperable, refer to STS Section 3.3.3.5 for limiting conditions for operation.
11.4 If A.S.M.E Section XI test quantities fall in ' Alert Range
- or ' Action Range', refer immediately to CP-102 for corrective action.
11.5 If either EF pump does not actuate when called for, l
refer to STS Section 3.3.2.1 for limiting conditions
[
l for operation.
l i
12.0 namnenure l
l Data Sheet 1A, Energency Feedwater Pump (EFP-1)
I Data sheet is, Energency Feedwater Pump (ETP-2)
EFW Overfill Bypass and Reset Valve check List 1A Valve check I.ist it j
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CN/#neA) of Ny%I 7 d".,, <. Xe
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SP-349 Rev.- g g Page 16
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Enclosure !
- DATA SEEET 1A -
IMIEGENCY FIEDWATER PUNP (IFP-1) s MACHINE SIETCg LOCAL PTMOR.ANCE D/.TA i
E p d
5 Displacement Yelocity 011 (milm-ok to ok)
(ic/see)
Level g
Normal j
O
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't U. au teve1 pt
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.c 04 30 N/A D
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./I
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. /2 ',20 1 xtr l
"A",
"B",
"C",' and "I" vibration measured in
/9
'80l~**N/&
~~~
the horizontal direction.
Y
/Y /d 9r 2.9 "43
..z y ". yc I
~
C",
"D",
"E", and "P" vibration measured in the vertical direction.
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- Position "G" is the only A.S.M.E. Section n required measurement.
sTSTD rrm.rviviANCE DATA STAIT m E
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rump
. Idle operacias stor umE
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327.o i n.w regio manne 4
> f a, M M ////2 8Ie 72(p.C '
>/.fde Einh Alert Ranae kcual Test value '
- 2. S.1 7A ) I
/4?O N Yb.L GECK VALvZs g formal Range 23 df.a Ed '). d !/Ma-/. Bra' / dis-//*5 EF7-4 opens EF-2-PI
.aw Alert Range
- I 4 d7. o
- d. //%1
=
aow Actica lange I
- 4. 4. d*
t,. jaQ_g I
i EFY-35~ opens EF-2-PI Condensate Storage Water tavel M (A221) f Verificacias that EFP-3 has stamaltaneously started with IFP-1 operatism. (Inistals)
Discharge Pressure t 1100 peig
.EFV-14-and-33 open test-1ightL.t).1uminated # ock 6)
Shut Mown EFF-3 i*ter star'+. verification.
- -K EFV-14 and 33 test lights all extinouish K cek O EFP-1 start tSe erating pressure time (ed co sec)
.5 set applicab
.1 Differential Pressere (pois)
- Discharse Pressure - Sectica Pressure
- !f A.S.M.E. Sectio test quanttt1es fati..in
- Range" or " Action Range", refer 1sumediately to CP for. corrective action.
le f N
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time
/Ihv Performed my Date
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PROCEDURE APPROVAL AND TRANSMITTAL SHEET s
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CYet hob WG PR CEDURE DISPCSIT:6ti
.=.:.=
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NCN-SURVEJLLANCE PACCECU AES SURVEILLANCE ACCCECL:55 V
l ACUTETC:
Reso. Sect. Suovt__.
'M ACUTE TO.
SP O e<=
Ctne7'.-
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U Ct e*
L.,
Comoiiance Comenance
- .3 5 Cuahty Files 5 Cuanty Saes J
PROCEDURE IMPLEMEN TER CA R '
f, O bC b
I Cor-oieted oy Sections Enclosed l
Acason performed i
! Comments i Ceviations Corrective / Followup Action initiated swee =come rune me.:
i I-Aetest Aecuired O Yes When U
RESPONSIBLE SUPERVISOR PART
, PROCED, URAL REQUIRE,M,l[5TS' Techni Specification ASME on XI Other (Non; Technical Soecification L ACCootance Cntena MET L Acceptance Critens MET GCineletec Satisd 2:::
- C Acceptance Criterfa NOT MET and O ai.rt aanse 4cesotanc. Cnt.na C "niatisfac:= y: a-e:- e Corrective Measures initiated NOT MET "easures In':: ate:
Not Applicaele O 4ction aanse 4cc.oiance Cni.ria O Noi 4aoncacie NOT MET and Corrective Meesures Initiated
__. _ _.. _O_ noi apoiieaci.
'l
/
The enclosed or ion was catained. reviewed. and accroved accordins to the steos outlined in the procedure. I have rew'e*ed "e '-*: -
matto ci god.
m satistled that ine above indicated result nas been octained.
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.i A -400 Rev. 62 Page 29 i.
Rev. 49 06/04/36 0/86/3 7-M6 Document Section ORKING COP N C. R. Nuclear SURVEILLANCE PROCEDURE SP-349 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 EMERGENCY FEEDWATER SYSTEM OPERABILITY DEMONSTRATION THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS THIS PROCEDURE ADDRESSES ENVIRoleENTALLY QUALIFIED (EQ) EQUIPMENT APPROVED BY:
Responsible Section Superintendent /
Supervisor R ) [ IAU' Date t /se /r /
INTERPRETATION CONTACT:
Nuclear Plant Engr. Supt.
s
7.3 The Plant Operator should be in communication with the Control Roca during performance of this proce-dure.
8.0 PREREOUTSITES 8.1 Notify the Shift Supervisor on duty prior to consencing this surveillance for
'A' train and
- B*
train.
8.2 Section 6.0 Limitations and Precautions have been read and understood.
8.3 For the refueling outage test in Mode 4, the aux.
l4 steam supply to ETP-2 has been aligned to receive steam from Crystal River Unit 1 or 2.
l 9.0 INSTRUCTIONS Initials 9.1 Verification of oil levels:
NOTE:
Perform the oil level verification (s) applic-able only to the section to be performed. Oil level verification for the section not performed may be marked *N/1".
9.1.1 Verify turbine bearing oil levels are within sight-glass casing scribe marks that are overlayed in black markings.
//
l l
l l
SP-349 Rev.' 4 O Page 7 l
~~~ ~
~
--. x
.a.
Initials 9.1.2 Verify turbine-driven pump bearing oil levels are within the sightglass casing scribe marks that are M!A overlayed in black markings.
/
9.1.3 verify motor-driven pump bearing oil levels are indicating approximately midrange.
9.2 PROF *TDURE -
- l' (EFP-1)
NOTE:
Once per quarter (January,
- April, July and October),
perform SP-370, Quarterly cycling of
- Valves, Enclosure 1,
concurrently with this procedure.
'A*9.2.1 Insure initial conditions, Section 9.1 is complete.
NOTE:
All data is to be recorded on Data Sheet 11.
'A*9.2.2 Close EFV-33 and 14 (EFP-1 isolation to *B' and ' A' OTSG's).
l l
i l
l t
l l
l 1
Rev( 4 g l
SP-349 Page 8
~.
Initials
- A*9.2.2.1 In the EFIC Room, inside the
'D' EFIC Aux Relay Cabinet, place the key operated test / normal switch to the test position.
NOTE: The above step disables the EFV-33 and EFV-14 open signal from EFIC on an IFP-1 start.
'A*9.2.3 Record EFP-1 initial suction pressure and the con-densate storage tank water level.
NOTE: Step 9.2.3.1 need only be performed for the initial surveillance upon a startup following a refuel outage.
N/A this step at all other occasions.
This information is required for SP-145, EFIC Time Response Testing.
"A*9.2.3.1 Start a stopwatch upon performing Step 9.2.4.
NOTE: The stopwatch is to be stopped immediately when EFP-1 reaches operating pressure, i
'A*9.2.4 Start EFP-1 by depressing the two EFW actuation EFIC Matrix pushbuttons labeled EFIC CHA to EFp-1 start logic.
l l
t SP-349 Rev.' 4g Page 9
Initiais "A*9.2.5 Verify EFP-3 Auto Started upon start of EFP-1.
Then place the EFP-3 control switch in the
- STOP" position.
NOTE: Bearings "A",
"B*,
"G*,
and
'H*
vibrations are measured in the horizontal direction.
Bearings
- C*,
'D*,
"E*,
and
'F*
vibrations are measured in the vertical direction.
' A*9.2.5.1 Verify the test lights, in the
'D' EFIC Aux. Relay Cabinet indicate EFV-14 and 33 would have received an open signal had the signal not have been blocked in Step 9.2.2.1 (i.e.,
the ETV-14 and 33 open lights are illuminated) unless EFW overfill l4-2 protection is in effect.
l
'A*9.2.6 Complete Data Sheet 1A arter transients have diminished.
'A'9.2.7 Depress the EFIC CHA to EFP-1 start logic reset pushbutton, shut down EFP-1 and record shutdown time.
dN
'A*9.2.8 Verify control switch is in the ' Normal" position.
b
'A'9.2.9 Open EFV-33 and 14 if the valves are not receiving a l47 close signal from an EFIC EFW overfill limit l
actuation.
l NOTE:
If it is desired to open these valves, refer l47 to Enclosure 3.
l SP-349 Rev.'
O Page 10
Initials
- A*9.2.10 Initial Valve Check List 1A, verifying that each valve in the flow path is in its correct position.
'A*9.2.11 Place EFP-3 control switch in " Auto'.
88
'A*9.2.11.1 Inside the
'D' EFIC Aux. Relay Cabinet, place the key operated test / normal switch to the normal position and return the key to the Shift Supervisor.
"A*9.2.11.2 Verify the EFV-14 and 33 test lights in the
'D' EFIC Aux Relay Cabinet are all extinguished.
'A*9.2.12 Have another person perform an independent verification of Valve Check List 1A.
'A'9.2.13 Notify Shift Supervisor that this surveillance for
'A' train is complete M
D
/h JUL 081986 Shif't' Super' visor Date
~
9.3 PR0f*E URE
- * (ETP-2)
NOTE: Once per quarter (January, April, July, and October), perform SP-370, Quarterly Cycling of
- Yalves, Data Sheet Y
and Enclosure I
concurrently with this procedure.
'B'9.3.1 Notify the Shif t Supervisor prior to beginning this surveillance on the
'B' train.
'I
'B'9.3.2 Insure initial conditions, Section 9.1 is complete.
i I
49
~
SP-349 Rev.
Page 11 j
l l
f
- DATA SHEET 1A -
IMEIGENCY FEEDWATER PCMP (EFP-1) i MACRINE SEETCH LOCAL PER?oRMANCE DATA i
e p
o*
2 Displacement Velocity 011 (mils-ek to ok)
(ic/see)
Level e
Normal u
Oil Level a
F c/h j
.M
,' ~
3
'L 3
W o
a u
u Verified
'M
- =
4 4
4 p,u i
O A
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, ()&
.jo
,fff F
l I
N} 6 n
',1)
/.o H
30 Als l
.C
./0
/. a
.07
.So l N/x l
,/f
/.o
,OT 3d N/A l
D E
./Y
/. O
.[0 ',80 N/A "A",
"3", "G",'and "R" vibration measured in the horizontal direction.
F
_/2
/.4
. [2 80l"N/A G**.7'} ~2.9 "44 3
.l9 "M st&
I "C',..,, D,,,,,E,, and,'7" vibration measured in the vertical direction.
1
.90 dddr
. 2[,
fo
/ffh l
" Position "G" is the only A.S.M.E. Section x1 required measurement.
SYSTD PERFORMANCE DATA START TIME NW rump rump o===ine STor nxE M7 Iaie v
E 5
w l.s,.,
non nuE 2'*
E".
IsI IIMITs w
a 3 E GI 3EY
.E E M EQ "E~7
" : %7
- :17 I E.
TEST Ecc1rME:r esED 3 % Eh a t 25 5 % hk 5%&
52 Vibration TI bd
- 2274 !
lieh Action Ranze 4 i > / 5'4 o 72ip.O !
>/Soo Einh Alert Ranze Lctual Test Value *
.2 3. (,
.R3. k !
/4 f b
/W6.*/
CHECK VALVF.S 7ERIF.
TIS Cornal Range 26 '),a 2 b '). 0 '/S~to /.5G JDe*/196 EFV-6 opens EF-2-PI
/
t 1.o I
i4. //pg
.aw Alert Range
- I l
Ww Action Range
( g.. S'
< /h93
/
i j
EIT-35~ opens EF-2-PI v
/
l Condensate Storage Eater Level 33 (Azz1)
Verification that EFP-3' has stamiltaneously started with EFF-1 operation. (Initials)
N Discharge Pressure > 1100 psig EFV-14-and-33 coea-test _. lights.t).luminated
/4
~
~
Shut Mown EFF-3 i'ter'it d*. verification.
Av EFV-14 and 33 test lights all extinouish W
EFP-1 start to coerating pressure time (ed.
secj mt v/A-
- Not Applicable ~
1Differential Presenre (peig) = Discharse Pressure - Suction Pressure
If A.S.M.E. Section kI test quantities fati fn " Alert Range" or " Action Range", refer innediately to CP-102 for corrective action.
l
.erfor.ed >7 W #
meeJl]L 0 81986 n.e
/600 w e.ed,, 6&R JUL 0 81986 m.,
geoo De vss si g/a w an)
W$+
'm
- SP-349 Ravl 4g Page 17 L
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10CFR$0.59 CHECKLIST PROCEDURE NO.
AEVISiCN No.
5/-349
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la the plant procedure a change to the facility as described in the Safety Analysis Report, or will the addition of the procedure change the facility as described in the Safety Analysis report?
O Yes @ No V
is a change in the Technical Specification involved?
@ No O Yes y
~
is any unreviewed safety question involved,i.e.,
(1) is the probability of an occurrence or the consecuences of an accident, or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report increased? O Yes ENo (2) is the possibility for an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report created? O Yes K No (3) is the margin of safety, as defined in the basis for any l.
Technical Specification reduced? O Yes % No Any answer Oyes V Allanswers T No
,m v
y Document Change including:
Request and receive (1) Description of Change NRC authorization (2) Written Safety Evaluation which provided for change.
bases for item (1),(2),(3) above.
Description and Safety Evaluation complete T Authorization Received O
+
+
Initiate Procedural Change
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w ENCLOSURE 5 QUALITIED REVIEWER CHECK-0TT SHEET SF-30 Procedure The attached procedure requires a Qualified Reviewer (s) review and approval. Upon completion of the review, initial and date, and forward to the Responsible Superintendent / Supervisor.
Ceasents and questions say be attached to the proce-dure and must be resolved by the Responsible Section Superintendent / Supervisor.
INITIALS /DATE QUALITIED REVIEWERS
.NUCL8R OUTAGE & N00!T.ICATION MANAGER
/
/
NUCLEAR SEC k SPECIAL PROJECTS SUPT
/
NUCLEAR SATETT & RELIABILITT SUPT I
NUCLEAR CNEN & RAD PROT SUPT
@/ Z /vArz NUCLEAR PLT ENGINEERING SUPT
/
NUCLEAR MAINTENANCE SUPT
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NUCLEAR OPERATIONS SUPT
/
(OTBER)
TECHNICAL REVIEWER 0 * ** '
R.aham Afa/ C/t/84, be 3%
/
/
/
/
/
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RESP SECT SUPT /SUPV e
AI-401 Rev. O g Page 35
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Safcty-Relatcd Non-Safety-Related NQE DOCUMENT EVALUATION l l O
has been evaluated 8Ch ge No.
b-Rev. No.
This document I
for the identification of inspections which are necessary to asssure compliance with the engineering design and with the material, fabrication, assembly, erection, installation, and examination and test requirements.
Pertaining specifically to this document, the following applies:
INSPECTION REQUIREMENTS No Change to Existing Inspection Plan No inspection is Required Existing Inspections are Revised Inspections are Required.
Refer to DEFINITIONS HOLD POINT An established stopping point within a function, process or procedure, beyond which work shall not proceed without inspection action performed by an appropriately qualified
(
inspector or examiner.
l An established stop' ing point within a function, process or p
WITNESS POINT procedure where notification of an appropriately qualified inspector or examiner is required. The contacted inspector or examiner may exercise the option of when the identified inspection is to be performed.
Work may proceed beyond a Witness Point following permission granted by the contacted inspector or examiner; however, the inspection shall be
(
accomplished prior to closure of maintenance records.
i l
SURVEILLANCE An overview of activities pkrformed by Inspection personnel to ascertain and verify conformance.
Notification of the Inspector prior to beginnink of work is required; however, the I
I work may continue following such notification.
l J
l O b.O M-Names
/ ate D
l Senior Nuclear QA Engineer / Nuclear Quality Engineer
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Florida INTEROFFICE CORRESPONDENCE Power QUALITY PROGRAMS NT20
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rocedure No. Sf 3d f
, Rev.
SUBJECT:
Review of Judd
Title:
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(/
/
6' To:
he-d8 DATE:
/
Responsible Sect 2cn Superintendent / Supervisor The subject procedure has been reviewed for In-Line approval by the Quality Programs Department. This procedure is:
Approved Rejected Returned per Request of The following comments apply:
(Asterisked items must be resolved for procedure approval) i l
l l
rD.O.0LeGR QPD Reviewer 900.TS $1
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l PREPARATICN OF SAFETT, NCD-11
- 5
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9 ver REGUI.ATCRY AND ENVIRCNMENTAL h
CCMpLIANCE REVIEYS d _ _ __ _.
ae.is cN nt NUCLE AR CF ER AT;CNS :
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- F ;.t:t.A::RY As:: 9.q : : ::..I3:2 SP-3NT R C V. 48 Document Reviewed:
1.
19._C D.3.Q_ D I m iY b s:
A.
Is this a chinge to Tec'.nical Specifications?
Ya:
b B.
Is this a change to the TSAR 7 Yes C.
Is the probability of occurrence or the consequences of an accident or =alfunction h N:
evaluated in the TSAR increased?
Yes Secause:
qe.4 t fA.k D.
Is the possibility for an accident or aalfunction of a dif f erea.t type than any evaluated in the TSAR created?
Yes N:
Secause:
dd E.
Is the sargin of safety, as defined in the basis for any Technical Specification reduced?
Tes No Because:
gg Complete If any are 'Yes,' contact the Manager, Nuclear Licensing Yes N/A NRC approval received if needed and attached.
Yes N/A m
t
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PPEPARATION OT SATETY, NCO-11
. f SSUE CATE M
REGULATORY AND ENVIRCNMENTAL l 01/ 3C. if o
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QNor CCMPLIANCE REVIEWS REVIS ICN P A ;E 0
5 cf 6 s,., NUCLE AR CPERAT:CHS j i
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A..;ci.i : A D:
uv EV CME:yt:i 7 :7.- E ;.". A! ;' t AN: i A T E Y Cc.'.v t.'. :S 2.
10_CFR 50.54 Reviews Oces this acdificaticn or decunnt revision che.;e what is described in any of the f olicwing plans /prograns?
bo Quality Program Cescription (TSAR Section 1.7)
Yes N
Licensed Operator Requalification Progran g
(TSAR Section 12.2.3.4 and Appendix 12 C)
Yes P No Modified A3 ended Security Plan Yes No Safeguards Contingency Plan Yes No Security Guard Training and Qualification Plan Yes No Radiological Emergency Response Plan Yes No Evaluation If any yes:
1.
Contact appropriate responsible Ccaplete N/A persen to perfora evaluation and attach.
Ccaplete N/A 2.
MRC approval received if needed g
and attach.
3.
Could this affect the environment in a g Yes No i
non-radiological way?
Complete N/A If Yes contact the Manager, Nuclear Licensing IT ALL OF ABOVE ARE CHECKED NO, NO FURTHER REVIEWS ARE REQUIRED.
O>M M cNu L R $ o k (.-3 %
1 Prepared By 04te Approve Date I
T e
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ENCLOSURE 9 N.
y PROCEDURE TRAINING
SUMMARY
Procedure No. :
Revision:
==
Description:==
(Provide a brief sumany, clearly describing those porn::ns of -
the procedure which were changed and why changes.ere made. )
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Date:
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i Rev. b 3 Page 39 (LAST PAGE)
AI-401
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Other Ctree Corrohance L_ Comenance 3
5 Cuanrr Files 5 Cuality 8 es t
d PROCEDUREIA MENTER CARI OOMOas 3,,,,,,,,,,,,,,,hOA,opaf3jg,o C-o,eied ey l
oakn C r S~4orbop - m EP0'l E cl ric 4 no, son oer,ormed i
l Comrrents s Deviations 00Ne-Correctivei Followuo Acticn initiated iwas acone rune u NO h-aetest A.cuir.d $ No d
UM Yes When RESPONSIBLE SUPERVISOR PART
, PROCED_ URAL REQUI. REM,E5_T_S)
Technical 3eecification ASME Section XI Other (Non. Technical Soecificationi Acceptance Crisena MET Acceptance Critona MET Cemaletes 54t's m *F*
C Accaptance Criteria NOT MET and Alert Range Acceptance Criterta C Unsatisf acten.u-ect Corrective Meeures initle3ed NOT MET "eassres Ini::atec Not ApplManle C Action Range Acceptance Criteria Not AcolicaDie NOT MET and Corrective Measures Initiated Not Apoticable The oecioned information was obtained.' reviewed and soproved according to the steps outlined in the procedure. I nave reviewed tre inter-mattort enclosed and am.. satisfied that the above indicated result has been octained.
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