ML20090B554
| ML20090B554 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/02/1987 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20090B375 | List: |
| References | |
| FOIA-91-106 1-PT-46.2C, NUDOCS 9203030461 | |
| Download: ML20090B554 (6) | |
Text
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~
REQU ST TO CHANGE PROCEDURI
-5.4 NORTH ANNA POWER STATION i
VIRGINIA POWER Paga l'of 1 07-09-87 I., APERVISOR RESPONSIBLE FOR FOLLOVING PROCEDURE:
1 O OP' RATING O VELDING O ABNORMAL O CURVE B00E E
O ADMINISTRATIVE O EMERGENCY
@, PERIODIC TEST O
O ANNUNCIATOR O IN-SERVICE INSPECTION O HEALTH PHYSICS O
O CALIBRATION O MAINTENANCE O SPECIAL TEST O
O CHEMISTRY O NON-DESTRUCTIVE TEST O START-UP TEST O
2 UNIT NO:
- 3. REVISION DATE: % g PROCEDURE NO: /,
[
TITLE:
5/c-8/~u Lf;.f-:m Nfer Al3,_ 64 #
4/,Jurm CHANGES REQUESTED:
(GIVE STEP NUMBER, EIACT SUGGESTED VORDING, AND LIST REFERENCES, STAPLE 4
COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.)
U G ua Pre coda m
REFERENCES:
bl e C-t el4 e-Sn.
N, 97-V7VA REASON FOR CHANGES:
^ I%)
Prw daro-
/
8 DATE:
5
(
GE REQUESTED BY:
ACTION TAKENs 1C DOES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN THE UFSAR/
O YES S NO DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS /.
O YES S NO DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEWED SAFETY QUESTION /
O YES g.NO IF ALL "NO", NO " SAFETY ANALYSIS" IS REQUIRED.
IF ANY "TES", A " SAFETY ANALYSIS" IS REQUIRED, (10CTR50.59) APPROVED COPY TO BE PROVIDED TO LICENSING COORD. POR INCLUSION IN ANNUAL REPORT.
RECOMMENDED ACTION:
1:
PROVED O DISAPPROVED DOES THIS PROCEDURE CREATE A QA DOCUMENT /
YESM NO-]
BY:
(COGNIZANT SUPERVISOR) 12 DATE:
12 REVIEWED BY QUALITY ASSURANCE:
YESb NO 7 14 CHANGES MADE:
I 15 U*I*
16 8"*
Wenr; p.(3 d p-oc@
REVIEWED TATION NUCLEAR SAFETY AND OPERATING COMMITTEE:
1; APPROVED C DISAPPROVED D APPROVED AS MODIFIED BY COMMITTEI 1
iRMAN SIGNATURE:
18 DATE:
li j
/h NEW PROCEDURE REVISION DAIE:
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I. '#'.
9203030461 910819 l
-106 PDR 21 DATE:
i'
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ACTION COMFLETED BY:
o PERIODIC TEST CRITIQUE NORTH ANNA POWER STATION VIRGINIA POWER Periodic Test No: 1 To be Performed By:
2 Unit No:
3 1-PT-46.2C SHIFT TECHNICAL ADVISOR 1
Test Titles 4
S/G BLOWDOWN RADIATION MONITOR ALARM SETPOINT CALCULATION Test Frequency:
' " ~ '
5 SPECIAL Unit Conditions Requiring Test
~' s MODE 1 Test Performed By:
7 Date Started: Bi
$ 6i?IS 2 7 d "8B Test Results (To be completed by performer of test and Cognizant 9
Supervisor (s)):
1.
/
/ Satisfactory
/
/ Unsatisfactory
/
/ Partial Procedure
- 2. The following problem (s) was encountered (use back of sheet for additional space):
- 3. Corrective action tak'en or initiateda
- 4. Work Order No.:
Sated:
Forward To Cognizant Supervisor Test Reviewed and Approved By Cognizant Supervisor (s) or Designee:
10 Date:
Reactor Engineer Date:
Supervisor, Sury. & Test Comments:
Forward To Performance Engineer Comment (s) of Performance Engineer:
11 Stamp:
12
1-PT-46.2C Page 1 of 3^
00-00-00 VIRGINIA POWER PERIODIC e PROCEDURE FOR NORTH ANNA POWER STATION UNIT NO.:
1
. TITLE:. S.'; 3 LOWDOWN RADIATION MONITOR ATARM SETPOINT cATMffitION
REFERENCES:
L 1-PT-46.2
-L Letter to the NRC, 9/15/87 (serial no. 87-474A) l
~-REVISION r m n:
-APPROVED CHAIRMAN STATION NUCLEAR SAFETY 1REV.
.E.
PAGE(S)-
DATE AND OPERATING COMMITTEE l:
I-1 RECOMMENDC 1.JPROVAL:
APPROVED BY:
CHALILMN STATION NUCLEAR SAFETY AND OPERATING COMMIITEE l'
DATE:
IEPERINTENI:D~ IECHNICAL ' 'E. VICES f
1 i
i
w ee
_2 c a,. da m : e-.u>
1-PT-46.2C Page 3 of 3 00-00-00 4'. 2 Calculate the new "High" alarm setpoints for the S/G Radiation Monitors using the equation at the bottom of Attachment 6.1.
.4.3 Immediately notify the Shif t Supervisor of the new alarm setpoints.
4.4 Complete Attachment 6.2 and forward a copy to the Health Physics
. Shift Supervisor.
4.5 Verify _ that the new setpoints has been implemented.
4.6 Post an Operator Aid (ADM-19.27) next to the S/G Blowdown i
Radiation Monitors stating the "High" alarm setpoints.
1 5.0 Acceptance Criteria 5.1 The new setpoints have been implemented and an Operator Aid has J
been posted.
6.0 Attachments 6.1-S/G Blowdown Radiation' Alarm Setpoint Calculations 6.2 Memo to change -the S/G Blowdown alara setpoints.
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t-m.
m m.
1-PT-46,2C.1 Page 1 of 1 00-00-00 S/G Blowdown Radiation Alarm Setpoint Calculations Recent Steam Generator Blowdown Radiation Monitor Count Rates (from 1-PT-46.2):
"A" Steam Generator (1-RM-SS-122)
Date(s):
Count Rate (s):
cpm Average:
cpm
- New "High" Alarm Setpoint:
cpm "B" Steam Generator (1-RM-SS-123)
Date(s):
Count Rate (s):
cpm Averaget epm
- New "High" Alarm Setpoint:
cpm "C" Steam Generator (1-RM-SS-124)
Date(s):
Count Rate (s):
cpm Average:
cpm
.New "H'gh" Alarm Setpoint:
cpm
- New "High" Alarm Setpoint = 2 x The most recent count rate.
PREPAPl.D BY:
DATE:
e
- i r
.,-p.-
1-PT-46.2C II.2 Page 1 of 1 00-00-00 MEND TO CHANGE THE S/G ALARM SETPOINTS Health Physics Shif t Supervisor North Anna Power Station TO:
FRON:
Shift Technical Advisor Dates
-Please immediately update the "High" alarm setpoint to the Unit 1 S/G Blowdown-Radiation Monitors as soon as possible, as fc11ews:
1 "A" S/G "High" Alarm (1-RM-SS-122) =
cpm "B" S/G "High" Alarm (l-RM-SS-123) "
cpm-
"C" S/G "High" Alarm (1-RM-SS-124) "
. cpm 4
Date:
l.
Shift Technical-Advisor l
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