ML20003J327
| ML20003J327 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/01/1981 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105110271 | |
| Download: ML20003J327 (6) | |
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?crJerd Gereral EecMc Ccouny s
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May 1, 1981
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Trojan Nuclear Plantg')'T~
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Docket 50-344 s g "~ -
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'J Director of Nuclear Reactor Regulation i'. 9,, '. C _, ' ',
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Mr. Robert A. Clark, Chief 1.3 4f:.. ~ /?e, '
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Operating Reactors Branch No. 3
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- 's Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
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Dear Sir:
Your letter dated March 30, 1981 requested additional information regard-ing Auxiliary Feedwater (AFW) Automatic Initiation and Flow Indication f or the Trojan Nuclear Plant. Most of the requested information has already been submitted to the NRC.
References and copies of tables have been included in the attached response for your convenience.
Sincerely, w
Bart D. Withers Vice President Nuclear Attachments i
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Mr. Lynn Frank, Director l
State of Cregon Department of Energy l
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ATTACHNENT TROJAN NUCLEAR PLANT PGE Response to the March 30, 1981 NRC Request for Additional Information -
Trojan Auxiliary Feedwater (AFW)
Automatic Initiation and Flou Indication
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a NRC Item 1 3
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Elementary wiring diagrams for:
__ u a) AFW System initiation circuits.
b) AFW System annunciation circuits.
c) AFW pump control circuits.
d) AFW valve control circuits.
PGE Response The requested drawings were submitted to the NRC as part of the PGE-to-NRC letters dated December 14,1980 (C. Goodwin, Jr. to A. Schwencer) and January 2, 1981 (B. Withers to D. Eisenhut). Some of these drawings are currently undergoing revision to incorporate recent changes to the Auxiliary Feedwater System in response to previous NRC questions and positions. A significant portion of the drawing revisions are scheduled to be completed next month and be submitted at that time.
NRC Item 2 Describe the steam generator level instrumentation at the Trojan facility.
This description should include:
a) Type and number of level channels per steam generator, including the range of each channel.
b) The specific source (vital bus) from which each of these channels is powered.
c) Capability for testing and calibration, including interval between tests.
d) The type of indication available in the control room for each channel (indicator, recorder, etc.).
PGE Response The answers to Items 2a and 2d can be found in Trojan FSAR Table 7.5-2,
" Main Control Board Indicators and/or Recorders Available to the Operator, Condition IV Fvents", a copy of which is attached. The information requested by Item 2b can be found in Table I of the PGE-to-NRC letter 2
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1 dated April 15,1980 (C. Goodwin, Jr. to A. Schwencer), a copy of which is also attached. With regard to Item 2c, channel. calibration is per-formed at least once every 18 months, and channel functi'onal testing is performed at least once every 31 days during Modes 1 and 2 for the narrow-range channels in accordance with Technical Specification 4.3.1.1.1.
The wide-range channels are calibrated every 2 years. Available indi-cated accuracies and required accuracies are given in FSAR Tables 7.5-1 (cepy attached) and 7.5-2, respectively. Alarm functions and trip setpoint settings of the narrow-range steam generatos water-level-channels are checked during the channel functional tests in accordance with Trojan Nuclear Plant Periodic Instrument and Control Test (PICT) procedures 5-1, 5-2, 5-3, and 5-4.
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1 of 2 f.1M Cot 4Troi. 30?!'" l'il ICf.T'es fnt./or FIcarPERS AV'.1'J%E TO T1T GPERATOR co r.17i073 I" rvrn*c No. of Channels Accuracy Parameter Avail.
Raq.
Range Required
' Indicator /
Purn p u,ca rs e 1
Containment 4
1 0-115% of de-
+ 10% of span All 4 are Monitor post-LDCA Pressure sign pressure indicated Containeer.t conditions, i
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Refueling Mater 4
2 0-110% (3 channels) i 3?. of level span All 4 are ir.dicated Ensure that water is J
U Storage Tank 75-1002 (I channel) and alarmed flowing to the safety Water Level injection system after a IDCA and determine when to shift from injection to recirculation mode.'
3.
Steam Cenerator 3/ Steam
+7 to -5 feet
+ 10% f level All channels indi-Detect steam generator tube Water Level Generator from nominal full span cated; the channels rupture; monitor steam gen-(narrow range) load level used for control are erator water level follow 1r.g 1
recorded a steam line break.
4 Stean Generator 1/ Steam
+7 to -41 feet
+ In?. of level All channels
, Detect steam gererator
[b]
al Water Level Gene ret n r f rom nominal span are recorded
,e abe rupture; monitor (wide range) full load skeam generator water level level foi,lowiag a steam line Nreak.
r-(a ) For the steam break, when the water level channel is exposed to a hostile environment, the accuracy required can b'e relaxed. Tae g
indication need only convey to the operator that water level in the steam generator is somewhere between the narrow range stear.
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,, y generator water level tapa.
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[b ] Hinimum Requirements en g'd one level channel per steam gen,,rator (either vide or narrow range).
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Sheet 1 of 2 YABLE I Power Supply Matrix for Auxiliary Feedwater Flow and Stea= Generator Level Indications Steam Steam Steam Steam
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Title Generator A Generator B Cenera;or'C Generator D l.uxilic:-; T :dr::::
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riew e; ranel C05-
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Indica;cs TI 204:A2 Tl 30433; Il 304302 FI 20,3D2 Pc-cr -pply
'i13 513 ii3 ii3 Steam Generator Level (Wide Range) at Panel C05 Recorder LR 501 LR 501 LR 503 LR 503 Power Supply Y24 Y24 Y24 Y24 Steam Generator Level (Narrow Range) at Panel C14 Indicator LI 517 LI 527 LI 537 LI 547 Power Supply Y24 Y24 Y24 Y24 Steam Generator Level (Narrow Range) at Panel C14 Indicator LI 518 LI 528 LI 538 LI 548 Power Supply Y13 Y13 Y13 Y13 Steam Generator Level (Narrow Range) at Panel C14 Indicator LI 519 LI 529 LI 539 LI 549 Power Supply Y22 Y11 Y11 Y22 T u. ~
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".AIN LXUlktG h0An'D !!4 DICA rorS AN9/ott Ci v0RDt ilS AVAll.A&Lt. TO Till' OPtHAf01:
s etInt Tlini Il MJD Ill FV6Nr%
No. of Cleannels Available Indicated Indicator /
Pareneter avat1.
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Range Accuracy Recorder Puspose 6
Steam Generatur 1/ Steam
+7 to -41 feet
+ 5% of level span All thannels Ensure matutenance of Wate r Level Generator f rom noralnal (cold) recorded reactor heat sink.
(wide range) full load water level 7.
Steam Generator 3/ Steam
+7 to -5 f eet from + 3% of level span All cl.annels Ensure maintenance of Wate r I.= vel Generator nominal full (hot) indicated; ti.e reactor heat sink (narrow range) load water etiannels tased level for control are recorded.
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8 Minimum kequireismucm:
u..e 1.veI *L..suneI per u t e.am gene s oit ur s
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