ML20235H432
| ML20235H432 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/08/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20235H435 | List: |
| References | |
| NUDOCS 8707150135 | |
| Download: ML20235H432 (8) | |
Text
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i TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 SN 157B Lookout Place JUL 0 81987 TVA-SQN-TS-87-02 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Centlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT - TECHNICAL SPECIFICATION CHANGE 87-02
)
Reference:
TVA letter to NRC dated April 14, 1987, "Sequoyah Nuclear Plant (SQN) - Technical Specification Change 87 Functional Testing of Radiation Monitore in Steam Generator Blowdown and Condensate Demineralized Lines" l
This clarifying information regarding technical specification change l
87-02 is provided in accordance with a request from Tom Rotella and Sang Kim during a June 17, 1987 telephone conference call.
provides clarifying information about the functional operation of radiation monitors in steam generator blowdown and condensate demineralized lines. contains a list of drawine,s and 1
schematics that are contained in attachments 1 and 2.
If you have any questions, please telephone M. R. Harding at (615) 870-6422.
Very truly yours.
TENNESSEE VALLEY AUTHORITY R. Gridley, Dir ctor Nuclear Safety nd Licensing Subscribed and worn to or me on this //.
day o
/ 1987
_ Mil j
Notary Public My Commission Expires Enclosures cc:
See page 2 3
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8707150135 870708
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PDR ADOCK 05000327 P
PDR g g An Equal Opportunity Ernployer b.
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'U.S.-Nuclear Regulatory Commission l-
.ccl(Enclosures):
Mr. Michael H.:Mobley, Director'(w/o Enclosures)
Division of-Radiological Health T.E.R.R.A. Building 150 9th Avenue, N Nashville, Tennessee' 37203 Mr. G. G. Zech, Assistant Director for Inspection Programs Office of Special Projects U.S. Nuclear Regulatory Commission-Region II 1
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director for Projects Division of TVA Projects Office of Special Projects I
U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 322' Bethesda, Maryland 20814 Sequoyah Resident Inspector 1
Sequoyah Nuclear Plant l
2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 i
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ENCLOSURE 1 SUPPLEMENTAL INFORMATION REGARDING TVA-SQN-TS-87-02 This enclosure provides clarifying information when a downscale failure of an effluent radiation monitor occurs in the steam generator blowdown or condensate demineralized effluent lines as discussed in the justification for change in technical specification change 87-02.
The steam generator blowdown effluent monitors, RM-90-120 and RM-90-121, provide independent isolation signals to the blowdown monitor isolation valves. Should one monitor have a downscale failure, the other monitor has the capability of isolating the effluent in the event of an increase of radioactivity above the setpoint as shown in the drawings listed in enclosure 2, item A.
A downscale failure of a radiation monitor initiates a main control room alarm. Upon receipt of this alarm, the operator declares the radiation monitor inoperable and initiates corrective action to return the radiation monitor to service. Because of the redundant radiation monitors, the automatic termination of the effluent line would needlessly isolate steam generator blowdown and have adverse effects on steam generator blowdown chemistry. This design provides redundant isolation capabilities for high radioactivity signal while maintaining blowdown and steam generator chemistry during a monitor downscale failure.
The condensate demineralized effluent is a batch process.
When a tank is ready for release, it is sampled in accordance with Regulatory Guide 1.21.
The condensate demineralized effluent radiation monitor, RM-90-225, will initiate a main control room alarm (instrument failure) and a local alarm (high radiation / instrument f ailure) when a downscale failure occurs as shown in the drawings listed in enclosure 2 item B.
Upon receipt of the local alarm, the operator is required to terminate the release per System Operating Instruction (SOI)-14.3 (see attachment 3).
$0I-14.3 states that, if high a radiation alarm annunciated, discharge should be stopped immediately. The local alarm (high radiation) is a multipurpose alarm that is initiated by a high radiation signal or instrument failure.
Therefore, in summary these radiation monitors do not require automatic termination of the effluent in the event of a downscale failure in the radiation monitors.
In one case, a redundant monitor exists to provide automatic isolation.
In the other case, the batch release is required by procedure to be terminated upon receipt of a downscale failure alarm.
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ENCLOSURE 2 A.
The drawings listed below pertaining to steam generator blowdown effluent radiation monitors RM-90-120 and RM-90-121 are contained in attachment 1.
47W610-15-1 Control drawing for steam generator blowdown showing isolation valve 15-44.
47W610-90-2 Control drawing showing steam generator blowdown liquid sample monitor.
47W801-2 Flow drawing showing steam generator blowdown isolation valves and radiation monitor connections.
45N615 Schematic showing steam generator blowdown radiation monitor high radiation relay isolation contacts and functions.
45N1651-6 Wiring diagram showing 0-RE-90-120, -121, and -225 pin connections.
45N1651-10 Schematic showing steam generator blowdown radiation monitor high radiation relay isolation contacts.
45W6S7-30 Schematic showing steam generator blowdown radiation monitor high radiation relay isolation j
contacts.
B.
The drawings listed below pertaining to condensate demineralized effluent radiation monitor RM-90-225 are contained in attachment 2.
1 47W610-14-9 Control drawing for condensate demineralized effluent isolation valve 14-360.
j 47W610-14 Control drawing for condensate demineralized effluent isolation valve 14-288.
47W838-4 Flow drawing showing condensate demineralized effluent isolation valves and radiation monitor connections.
47W768-5 Schematic showing high radiation relay isolation contacts and functions.
45N1651-14 Drawing showing cable connections.
45W788-10 Schematic showing 0-RE-90-225 pin connections.
ELE 281-5653 -
Vendor wiring diagram for radiation monitor l
RE-90-225.
ELJ 281-0140 -
Schematic showing radiation analyzer 0-RE-90-225 high radiation relay contacts.
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Page 15 i'.i.-
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INSTRUCTIONS (con'tinuedI
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4.0. Release of Neutralization Tank to Coolina Tower Blowdown (continued) 4.16 Start release by:
(a)
/
OPEN FCV-14 451 ketease neacer isolation valve (b)
/
OPEN and place in Neutralization auto FCV-14-187 tank release valve l
(c)
/
CLOSE and place in Neutralization auto FCV-14-188 tank recirc valve CAUTION: If high radiation alarm annunciated, immediately stop discharge by opening FCV-14-188 and closing FCV-14-187. Contact U-l SRO and consult SI 400.1.
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l step 3.2.3, Note 9 for further instructions.
y 4.17 Verify neut tank pump (s) #1 and/or #2 is running.
4.18
/
Throttle valve 0-14-1095 to obtain the flow rate stated in step 4.8.
4.19
/
Verify flow rate by FR-14-456. If FR-14-456 is inoperable, go to step 4.20 and N/A this step.
FR-14-456 gpm.
4.20
/
In the event that FR-14-456 is not
]
operational, verify flow rate using the es neutralization tank pump discharge flow recorder, FR-14-185. If FR-14-456 is operable, N/A this step.
"j FR-14-185 gpm.
s 4.21
/
Set composite sample flow rate at a constant
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flow between 1.59 through 4.76 gal /hr by 3
throttling valve 14-355.
Composite sample flowrate gal /hr.
(F1-14-466) j I
4.22 Notify U-l SRO and Radiochemical Laboratory Shift Supervisor of release start time and j
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flow rate.
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CATEGORY 4
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Nonreclaimable Waste Tank Operation (continued) 3.0 Release of Nonreclaimable Waste Tank to Coolina Tower Blowdown (continued) 3.13 Verify the high crud tanks or the neutralization tank is not being ivieased.
(a)
/
Verify FCV-14-310 closed, Neut, tank release to HCF.
l l
(b)
/
High crud tank effluent valve, FCV-14-288, is closed.
l (c)
/
Neutralization tank effluent valve FCV-14-187 is closed.
l 3.14 Verify the release will be made to cooling tower blowdown by checking; (a)
/
O-14-997 OPEN (condensate demineralized waste to CTB, located elevation 685 of turbine building).
(b)
/
0-14-998 CLOSED (condensate demineralized waste to turbine building sump, located elevation 685 of turbine building).
3.15 Start release by performing the following steps:
(a)
/
Open FCV-14-451 Release header isolation valve.
(b) _
/
Open FCV-14-360 and place in Auto; NRWT release valve.
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(c)
/
Close FCV-14-345 and place in Auto; NRWT t
Recirc valve.
s 9
CAUTION: If high radiation alarm annunciated, immediately dj stop discharge by verification of opening of recirc FCV-14-345 and closure of discharge FCV-14-360. Contact U-l SRO and consult SI
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400.1, step 3.2.3, note 9 for further a
instructions.
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INSTRUCTIONS:(cc.atinued);z _ - -d-f.~
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fj 5.11 (continued)
(c)
/
FCV-14-360 closed NRWT release header
' valve r:
s CAUTION:
Hnen realigning from CTSD to st6 tion sump, monitor station sump for possible increase in e.ctivity.
If alarm set point on 0-RM-90-212 is reached contact U-1 SRO and Radiochemical Laboratory Shift Supervisor.
5.12 Verify the release wl.11 be'made to the station sump.
(a)
/
0-14-998, condensate demineralized waste to
.h-station sump is open (elevation 685 of t
turbine building).
(b)
/
0-14-997, (condensate demineralized waste to CTB, is closed (elevation 685 of turbine building).
5.13 Record the following information:
Neutralization tank level at start L (1.T-14-181)
M
.i Release start time and date
/
Time Date l
CAUTION:
If high radiation alarm annunciated,
'immediately stop discharge by closing FCV-14-137 and opening FCV-14-188. Contact U-1 SRO and Radiochemical Laboratory Shift TT{j Supervisor for further instructions.
5.14 Start release by performing the following steps:
2 p
E (a)
/
Open FCV-14-451 release header isolation valve P
(b)
/
Open and place in auto FCV-14-187 neutralization tank release valve.
L (c)
/
Close and place in auto FCV-14-188
'I neutralization tank recirculation valve.
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