ML20214T467
| ML20214T467 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/02/1987 |
| From: | Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20214T470 | List: |
| References | |
| GCA-87-040, GCA-87-40, NUDOCS 8706100282 | |
| Download: ML20214T467 (19) | |
Text
gSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JUN 0 21987 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.
Associate Director for Projects "
Philips Building 7920 Norfolk Avenue Bethesda, MD 20014 DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 RANCHO SECO NUCLEAR GENERATING STATION - EFFECTS OF THE DECEMBER 26, 1985 OVERC00 LING EVENT, REPLY TO REQUEST FOR ADDITIONAL INFORMATION
Dear Mr. Miraglia:
This letter is in response to a request for information by Mr. Sydney Hiner and Mr. Mark Rubin in a telephone conversation on March 10, 1987, with our R. Little, H. Kemper and S. Redeker. Additional information is attached (Attachment 1) related to questions 23 and 24 of the May 30, 1986, letter (J.F. Stolz to J. Hard,
Subject:
Rancho Seco Nuclear Generating Station:
Effect of the December 26, 1985 Overcooling Event). The attached responses supplement our December 16, 1986 Rancho Seco Restart Report and address specific concerns expressed by Mr. Miner and Mr. Rubin on March 10.
A copy of the latest Emergency Operating Procedures is attached as requested by Mr. Rubin. Note that there will be some improvements to the Emergency Operating procedures prior to startup based on recent simulator training.
Mr. Rubin also requested a list ing of SPDS parameters. The SPDS functional specification included detailed inputs and processing information and is available for review as discussed in our April 30, 1987 submittal to you, subject "SPDS/ Regulatory Guide 1.97 Response to NRC Questions." Copies of the SPDS displays are attached. ,
Should you have any questions, please contact Mr. Steve Redeker at I (209) 333-2935, ext. 4353.
Sincerely, G,
I fyt u arl,Andoggifu Chief Executive Officer, Nud ear Attachments 0706100282 870602 G 0500 g 2 h
pq cc w/atchs:
t l
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G. Kalman, NRC, Bethesda (2)
A. D'Angelo, NRC, Rancho Seco t i RANCHO SECo NUCLEAR GENERATING STATloN U 1444o Twin Cities Road, Herald, CA 95638 9799,(209) 333 2035
ATTACHMENT 1 ADDITIONAL INFORMATION IN RESPONSE TO REQUEST FOR INFORMATION OF MAY 30, 1986 QUESTION 23a ADDITIONAL INFORMATION All failure modes of the ICS or NNI which initiate a plant trip will result in one of three plant responses or symptoms: loss of subcooling margin, excessive primary to secondary heat transfer (RCS overcooling) or inadequate primary to secondary heat transfer (RCS overheating). It is thus not neces-sary to evaluate Emergency Operating Procedure (EOP) treatment of all possible ICS/NNI instrument or component failures, but rather it suffices to demonstrate that the E0Ps adequately address the three symptoms which could be caused by ICS/NNI failures.
The function of the ICS and NNI is to control primary to secondary heat transfer rate, reactor power and generated megawatts. The major parameters controlled are RCS pressure, Tave, pressurizer level, reactor power, main feedwater flow, main steam pressure and flow, once through steam generator (OTSG) level and generated megawatts. Pressurizer level and RCS pressure are not controlled by the ICS, but by independent circuits which receive NNI inputs. Main steam flow rate is controlled indirectly through OTSG pressure and generated megawatt control. Failures of the NNI, ICS, RCS pressure or pressurizer level controls must therefore result in upsets in one or more of the above parameters, thus affecting either primary to secon-dary heat transfer or RCS subcooling margin (SCM).
The ATCG approach recognizes that control failures must result in one of the three symptoms. The Rancho Seco E0Ps implement AT0G by providing separ-ate, prioritized procedures for each of the symptoms:
- Procedure E.03, " Loss of Subcooling Margin"
- Procedure E.04, " Loss of Heat Transfer"
- Procedure E.05, " Excessive Heat Transfer" Treatment of loss of SCM has highest priority because if SCM is lost, RCS inventory cannot be known with certainty and a continued loss of RCS in-ventory will lead to hindrance of emergency transport to the steam generator, core uncovery and inadequate core cooling (indicated by RCS superheat).
As long as SCM is maintained, adequate core cooling will be assured, even if there are upsets in primary to secondary heat transfer. Excessive heat transfer and loss of heat transfer are mutually exclusive, thus I y are given equal second priority.
l The E0Ps are always entered at E.01 Immediate Actions, followed by E.02 Vital Systems Status Verification. E.02 then branches at steps 14, 15 and 16 to the symptom oriented procedures E.03, E.04 and E.05 discussed above.
The following shows that E.01 and E.02 insure prompt and effective operator action in the event of complete loss of ICS power, NNI power or both. Mal-functions other than c'omplete power loss are also properly handled by the I
. ,. v.--. -
6'
- 7
% e g7 ATTACHM NT P{ Cont'inued) Pagc 2 of 8 '
- r V procedures because fewer instruments and controls are affected. The t
/ following discussion describes steps which are affected by NNI/ICS power 4"
loss, indicating how compensatory or alternate measures are treated by the procedure. Steps not affected or required by the loss of ICS or NNI power are not discussed. It is useful to follow along with the E0Ps when reading this discussion.
NNI/ICS AFFECT ON SPDS t
iThe only input to SPDS from ICS is a reactor trip signal. Loss of
'ICS causes automatic selection of the post trip SPDS display, after
[ y' , which the operator may select any desired display. SPDS has some f T - inputs from NNI. These inputb are used by SPDS in one of two ways. ,
', First, the displayed parameter value.is the NNI value, or includes !
the NNI in an average value, or is compensated by the NNI input, etc. In this submittal, this first type of NNI use is referred to as "Affected by NNI."
The second type of NNI,use does not affect the SPDS displayed value but may L result in a question mdrk next,to the displayed non-NNI value. The question mark is displayed only if the non-NNI input is suspect due to other checks !
(such as comparison of two non-NNI signals) and the non-NNI signal does not
- compare favorably with the NNI signal. The parameters Affected by NNI will be identified on SPDS as Affected by NNI, or otherwise dealt with so the operator has a clear indication of which points are Affected by NNI. The parameters Affected by NNI are indicated on the attached copies of the SPDS displays. Photographs are also included. The AT0G post trip display is not ;
Affected by NNI and as shown below, the parameters which are Affected by NNI are not required to be used to deal with a loss of NNI--or ICS power.
E.01 IMMEDIATE ACTIONS !
E.01 manually reduces RCS_ letdown flow to 40 gpm in Step 3, which is accom-plished by reducing the letdown flow controller to minimum. Upon loss of ,
NNI power, letdown will fail and will not be reduced at this step.
It will be terminated shortly (about one minute later) by Step 6 of E.02, which directs closure of the letdown block valve if flow cannot be reduced.
The short delay will have little effect on trip response for even with maxi-mum letdown for this short period, pressurizer level will be only about four inches lower than normal at the point of minimum post trip level.
l E.02 VITAL SYSTEM STATUS VERIFICATION E.02 starts with a caution directing the use of Safety Param6 er Display l System (SPDS) and Emergency Feedwater Initiation and Control (EFIC) in- l strumentation should NNI power be lost. EFIC is not affected by NNI power l loss. All SPDS parameters in the following discussion of the E0Ps are not-Affected by NNI. It is important to note that the post reactor trip SPDS video " Post Trip Display" is automatically selected and is normally used along with EFIC instrumentation in conjunction with NNI/ICS instrumentation.
< _. I
ATTACHMENT 1 (Continued) Page 3 of 8 Use of all available instrumentation is emphasized in classroom and simu-lator training. The SPDS post trip display is a primary tool used to assess heat transfer upsets, primary plant status and steam generator (OTSG) status. E0P Guidelines, which are part of the approved E0Ps, call out SPDS as the primary tool and typical SPDS traces are included in the
, E0Ps on the left-hand Information Page to assist the operator in system diagnosis. Loss of NNI/ICS thus causes a minor disturbance to the operators use of instrumentation when assessing plant status and carrying out the emer-gency procedures. Instruments powered by ICS or NNI are clearly labeled so
, the operator will know what is Affected by a power loss. Unambiguous main annunciator alarms indicate NNI or ICS power failure.
Continuing with E.02, Step 1.4.1 requires maximum letdown and makeup as part of one of two primary means of emergency boration, but letdown can-not be maximized because the letdown controller / valve fails upon loss of NNI Y power. Preferred Method 2 is provided in the next substep and is not affected by loss of NNI or ICS power. Step 1.5 maintains the feedwater system in operation to remove reactor heat if there has been an ATWS. Loss of NNI or ICS power will trip the main feedwater pumps and AFW will automatically actuate to supply feedwater.
Step 3 verifies main feedwater flow decreasing and main feed pump speed running back to assure no main feedwater overfeed is occurring. Loss of NNI/ICS power will trip the main feedwater pumps, the operator will note the tripped pumps and AFW (EFIC) will automatically initiate thus there will be no overfeed. SPDS or EFIC instrumentation are normally used for Steps 4 and 5 as independent checks of the NNI instruments. OTSG pressure will be controlled by the main steam Atmospheric Dump Valves (ADV) which are controlled 4
by EFIC and are independent of NNI/ICS, the Turbine Bypass Valves (TBV) having been closed by loss of NNI/ICS power. Letdown will be isolated manually by Step 6.1 if it was greater than 40 gpm when failed by loss of NNI Y.
Letdown flow is available on SPDS alpha numeric display. Step 7: pressurizer level is on the post trip SPDS display. Step 8: RCS pressure is on the post trip SPDS also. Substeps of Steps 8 and 9 are not entered on a loss of ICS or NNI power. Step 12.3 is being revised to include any steps from C.15, loss of NNI power, which are required to stebilize the plant. C.15 will be implemented or; a not to interfere basis with stabilizing the plant. C.15 re-stores NNI power. Immediate power restoration is not required to reach a stable post trip status. For Steps 12 and 13, unambiguous separate main annunciator windows alert the operator to loss of ICS or NNI power.
Plant modifications have been made so that, with no operator action other than normal E.01 and E.02 Post Trip acticns, loss of NNI or ICS power or both does not cause a loss of SCM, nor over or undercooling. The plant will respond with very close to normal response inside the post trip window of RCS pressure versus temperature (see E.02, Page 26, 18.0, for this window).
There will be no branching out of E.02 at Steps 14, 15, 16 or 17, and the transient stops at Step 18 of E.02. Other E0Ps are not required.
1
ATTACHMENT 1 (Continued) Page 4 of 8 ICS/NNI MALFUNCTIONS OTHER THAN POWER LOSS Each of the three symptom-oriented E0Ps (E.03 Loss of Subcooling Margin, E.04 Loss of Heat Transfer, and E.05 Excessive Heat Transfer) assure prompt and correct operator action regardless of what caused the symptom. Miti-gative steps address the upsets of controlled parameters possible through NNI/ICS or other device malfunctions by providing diverse control methods.
Each of these procedures is discussed below.
E.03 LOSS OF SUBC00 LING MARGIN ICS/NNI malfunctions can cause loss of SCM by either (1) an extended over-cooling (extensive feedwater or steaming), which results in loss of pressur-izer level, (2) loss of pressurizer level due to level control malfunction, (3) extended undercooling (inadequate feedwater or steaming), or (4) loss of pressure control by inadvertant pressurizer EMOV (PORV) opening or spray valve opening. Procedure E.03, Loss of SCM, addresses each of these situa-tions with non-ICS/NNI controls and indications. Overcooling is addressed by Step 2, initiating HPI to restore pressurizer level, and Step 5 which transfers to E.05, Excessive Heat Transfer. HPI is not dependent on NNI/ICS and HPI flow indication independent of NNI is displayed on the SPDS alpha numeric display.
Loss of pressurizer level is also addressed by Step 2. Undercooling is addressed by Stcp 3, which initiates the auxiliary feedwater system through ETIC. Undercooling caused by understeaming is prevented by EFIC control of the main steam atmospheric dump valves (ADVs) and main steam code safety valves: No operator action is required. Step 11 transfers to procedure E.04 Loss f Heat Transfer; however, as discussed below, AFW and ADV control will prev ( t loss of heat transfer for ICS/NNI failures and transfer to E.04 is unnecessary. Loss of SCM due to inadvertent EMOV opening is addressed by Step 6, which closes the EMOV block valve. Step 6 also handles the in-advertent pressurizer spray valve opening by closing the spray block valve.
The block valves do not require the NNI or ICS. Step 6 actions are taken based on loss of SCM alone.
E.04 LOSS OF HEAT TRANSFER ICS/NNI malfunctions can lead toward loss of heat transfer by underfeed or understeaming of the steam generators. Loss of heat transfer is pre-vented however by automatic auxiliary feedwater actuation on low OTSG level and ADV control on high OTSG pressure through EFIC. The steam line code safety valves also provide for automatic steam relief capability. No operator action is required. Procedure E.04, Loss of Heat Transfer, will not be entered for NNI/ICS malfunctions due to the above automatic AFW and ADV actions.
(
ATTACHMENT 1 (Continued) Page 5 of 8
?
l E.05 EXCESSIVE HEAT TRANSFER d
NNI/ICS malfunctions can lead to excessive heat transfer by overfeed or oversteaming the OTSGs. Automatic termination of main feedwater by EFIC ,
i independent of NNI/ICS will terminate the overcooling using controls and '
l components independent of NNI/ICS: low OTSG pressure or high OTSG level l will actuate main feedwater isolation. EFIC control of AFW will direct AFW
, flow to the unaffected 0TSG at'a rate dependent on OTSG pressure to control i the heat transfer rate, preventing overcooling. Automatic action to terminate overcooling will occur at about 490 F RCS temperature (600 psig 0TSG pres-l sure). Procedure E.05 Excessive Heat Transfer, provides earlier termination by operator action. Step 1 directs manual tripping of the ICS controlled main feedwater pumps on either low pressurizer level, high 0TSG level or ;
- low RCS temperature (525'F). These parameters are displayed on the post :
reactor trip SPDS display. Main feedwater pump manual trip circuits are [
independent of ICS/NNI. Overcooling termination is also accomplished in '
Steps 3 and 4. These steps close and isolate ICS/NNI controlled components which could cause overcooling by taking manual ICS control and closing the !
valves or by closing non-ICS/NNI affected isolation valves. Slower over-cooling events caused by ICS/NNI failures will be terminated by this step before main feed pump trip is directed at 525 F by Step 1. The ICS/NNI can initiate an overcooling through the main turbine controls; however, this 3 is terminated by automatic turbine trip upon reactor trip. The reactor will
- trip on low RCS pressure induced by the overcooling and with no operator
, action other than normal E.01 and E.02 post trip actions the plant will achieve normal post reactor trip conditions.
1 PROCEDURE CHANGES The primary changes to procedures which will improve operator performance in a situation similar to the December 1985 event (i.e., extended over-i cooling regardless of cause) are in procedure E.05, Excessive Heat Transfer.
Step 1 now includes specific setpoints for pressurizer level or OTSG level or RCS temperature at which the main or auxiliary feedwater pumps which are causing an overcooling must be tripped to stop the overcooling. The steps to trip pumps were in place in December 1985 but lack of these specific criteria d
i for when to trip the pumps contributed directly to the extended overcooling.-
The auxiliary feedwater pumps overfed the OTSGs and were not tripped dur-ing the event. The makeup pump was damaged when a suction valve was closed with the pump running while recovering from an automatic SFAS actuation.
Throughout the E0Ps a caution has been added (such as before E.05 Step 8).
to assure proper pump suction alignment. Additionally, a new Casualty Pro-cedure has been written for recovery from SFAS actuation. This procedure ,
ret'rns SFAS actuated systems to a standby status, thus avoiding equipment damage. E.05 has been revised to indicate that throttling HPI for applica-ble PTS limits take precedence over maintaining pressurizer level (caution before Step 2). This reinforces the existing Rule 2 which directs HPI throttling to avoid PTS if SCM exists. HPI throttling to avoid PTS and its relation to SCM are discussed further in the response to Question 23b. In 4
~ , . - . - . . . _ . ~ , , , ,- , . . . . . . . , . - - - . .
ATTACHMENT 1 (Continued) Page 6 of 8 1
December 1985, post trip control of makeup and letdown and coolant waste
- tank inventories were not timely or coordinated. E.02 now references a new checklist in Procedure B.4 which periodically checks tank levels after a trip to detect and allow correction of unexpected flows within the system such as open relief valves or filling tanks.
23.b ADDITIONAL INFORMATION All actions necessary to achieve stable plant conditions for NNI/ICS fail-ures are incorporated in the E0Ps as shown in the reply to question 23.a.
Event-related nrocedures are in place to recover NNI and ICS power.
AT0G Part 1, Loss of ICS/NNI, Section 15, has specific steps for dealing with loss of ICS power. These steps gain control of and terminate overfeed i and oversteaming. The E0Ps in effect in December 1985 had steps which j accomplished the same result. The only steps not explicitly included in
- the E0P regarded local manual operation of valves. Valve operation was i directed, but not the locations. Training coupled with the procedure re-1 sulted in the operators taking exactly the steps on December 26, 1985 as j called out in AT0G. AT0G did not include steps on how to recover ICS power,
- however, a procedure for this is now in place.
i; The failure to promptly terminate the overcooling on 12/26/85 was caused by a lack of specific criteria, such as pressurizer level or RCS temperature, j for when to trip feedwater pumps, and not by a flaw in the AT0G concept nor by failure to have implemented the AT0G loss of ICS steps. The lack of the J. criteria in the Rancho Seco E0Ps is due to these criteria not being in the original ATOG, and not an error in the development and implementation of the AT0G based E0Ps. Had there been an event related procedure for loss of ICS rather than the AT0G E0Ps, the same lack of specific criteria (for when to trip feedwater pumps) would have existed. The three major divisions of the E0Ps (Loss of Subcooling, Excessive Heat Transfer, and Inadequate Heat
, Transfer), now contain explicit criteria to assure prompt and correct actions.
Event-related (Casualty) procedures are a necessary compliment to the E0Ps.
- These procedures contain the Operator actions to control readily identifiable events which may or may not cause a reactor trip, however, these actions are
- not required to assure proper core cooling. Any event which could jeopardize i
proper core cooling will result in excessive or inadequate primary to secondary heat transfer, or a loss of subcooling margin and a reactor trip. All necessary actions for these symptoms are contained in the E0Ps. Should a loss of ICS or NNI power cause a reactor trip and an overcooling, the upgraded E0Ps would rapidly terminate the event without the need to identify the initiating event as a loss of ICS/NNI power. However, once plant control is attained and ,
loss.of ICS/NNI power is identified, the event related procedure for loss of l ICS or NNI power would restore the ICS/NNI in a controlled manner.
I I
ATTACHMENT 1 (Continued) Page 7 of 8 QUESTION 23.c ADDITIONAL INFORMATION The Rancho Seco plant specific simulator contract has been awarded and the simulator is expected to be in operation in late 1989.
Use of the SPDS and EFIC instrumentation upon failure of NNI/ICS is discussed in the answer to question 23.a. SPDS has been in operation, and modeled on the Powe,r Safety International simulator since mid-1983, which includes over one full cycle of plant operation and several reactor trips.
QUESTION 24 ADDITIONAL INFORMATION PTS versus HPI Throttling. The Rancho Seco procedures implement one of the basic fundamentals of ATOG to assure core protection, which is that full HPI must be sustained as long as there is not adequate subcooling margin (SCM).
HPI must not be throttled below maximum allowable for runout concerns if adequate SCM does not exist (below the variable subcooling margin line (VSM)
E.03, page 16, Figure 1) per E0P Rule 2. This is also evident in E.03 loss of SCM where HPI is initiated in Step 2 and not throttled until Step 13 after checking that subcooling margin is restored in Step 7. Core protection is thus assured by prohibiting HPI throttling below the adequate SCM line (VSM line).
When PTS is a concern, the reactor vessel should not be operated more than 100*F subcooled if the RCS is below 500*F. Above 500 F there is no PTS limit.
The PTS limit is shown in E.03, page 16, Figure 1. HPI should be throttled to avoid the region above and to the left of the PTS curve. There is no concern that throttling HPI to avoid PTS will jeopardize reactor core cooling because the PTS limit and adequate subcooling margin line ("VSM" on Figure 1) are mutually exclusive limits with a permissible operating region between them.
The PTS limits are conservative and calculations are underway which will allow moving the PTS limit lower than 500 F. Resumption of power operation is not dependent on this change, however because as shown above, there is proper procedural guidance regarding HPI throttling versus PTS concerns.
PTS versus Pressurizer Level. The AT0G and E0Ps (for example E.02, Step 7.0, E.05, Step 2.0) emphasize maintaining pressurizer level immediately after a reactor trip (E.02) and at the onset of overcooling (E.05). This is done to prevent losing pressurizer level with the related loss of subcooling margin.
E0P rules provide instructions and criteria for certain equipment operation which always apply regardless of the plant condition. They are written to be compatible and not provide conflicting requirements. Thus Rule 1 - HPI Initiation, Rule 2 - Control HPI, and Rule 6 - Reactor Vessel Thermal Shock Consideration, taken together assure proper core protection and reactor vessel PTS protection. Note that pressurizer level is not a parameter of concern to throttle HPI, Rule 2, Step 3, and must be maintained on full flow if SCM does not exist, Rule 1, Step 1.1. It is not the intent, nor is it procedurally required or implied to maintain full HPI until pressurizer level is restored
ATTACHMENT 1 (Continued) Page 8 of 8 1 to 100 inches. On the contrary, specific instruction.is given to throttle i HPI to avoid PTS particularly in overcooling events where PTS is a concern.
E.05, Excessive Heat Transfer, the caution prior to Step.2, states,
" Throttling HPI for applicable PTS limits takes precedence over maintaining pressurizer level." This comes directly before-Step 2 which gives direction i intended to prevent losing pressurizer level and thus SCM, during an over- t cooling.
Violation of PTS Procedural Guidelines The discussion above and in the answer to: question 23 shows that there is ;
explicit procedure guidance which requires the operator to avoid the PTS region. Additionally, specific direction is given to use all available l means to avoid the PTS restricted region, use of pressurizer spray, EMOV (PORV) or pressurizer vents, for example, Step 12 of E.05. Note that Step 12, "If RV Thermal Shock Limits are Exceeded", means that the zonditions exist which require the RCS to be operated below the PTS :imit, t that the RCS is in the restricted PTS region. The December 1985 sooldown transient was not the most severe possible. A main steam line rupture results in a much more rapid cooldown and loss of pressurizer level and subcooling margin. The most severe cooldown, regardless of cause, will thus result in loss of SCM. The E0Ps then provide adequate instructions, '
l discussed above, to avoid PTS as SCM is regained due to action of full HPI i initiation.
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/ LOW RANGE P-T NOTE: 1) Loss of NNI or ICS will not cause overcooling or de-pressurization thus RCS pressure and temperature will ;
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- 2) Parameters Affected by NNI:
a) T-HOT (H+134 on diagram) i b) T-COLD (C+ 106 on diagram) c) RCS pressure (47 on diagram)
- 3) OTSG Pressure and 0TSG Tsat (vertical line) include second category NNI inputs but the display values are not Affected by NNI. Refer to question 23a section Nhi/ICS Affect on SPDS.
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' f. .;;: ..j 2'*:-]"U[f_.;-
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y = . . . :._ ,_ pan'. un
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7 -=.5...-.
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' ': M" " & . ' f : . 5 .
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- - --~**; s- : . :.=ln . ..'.'" ~..~.
d%[. . > $$h '*f'...A
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x' j.' :.L &.:^f*N:- w?.'.'?:~['?:-fQ$y%.!M';-
- ...e 9:.e. . .aY.y>.%.,;n;g'.g':*g.a.;.; - : 4.: - :7 .L5 ?
7'
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.. ~ .~.~;. .\.. .
l
- ; ,;
- '- ' M I.'
.: ._600 609 ! L 6h. . A ..9.
.'I'..'.'0'E
9.l. ;:a -:
l eos saa see.
^
l ik.' ':',((: 4.~.~.v:
.5 .. p. .. O nf '.>':~ .h.. &~:. :..
s.... ~.-
s
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-~,.~s, :: l , Q. - .. C -
-san 9 y=9_ f*g ca w: ~ [: . . .. m .... w see. .. x: - .. :
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- ,4,5
. ', : J k 7 3- 8"
.:7. A$ .a.
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.. t
. - :. . . w .:x .
- g. m , > y .. . . .
._, m. .
17.: W f- s. a : y . ,r;+a.-ag.:b&_ ...;,.. * * -
c .t .-w Y Y4W , f3 '.
'! ?9L:w:juw%&MNw: s -l: $.
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- ",- 8.r.
Mh'd,h@x.:. : :-n.ww 9 >IN 2::-,,S5O:bN.%. w..%;EYMN i t
INADEQUATE CORE COOLING DISPLAY (PAGE 2) {
i i
NOTES: 1) Inadequate core cooling will not result from loss
,- of NNI or ICS power, thus this display will not be required to be used for loss of NNI or ICS events.
- 2) RCS loop A has two T cold indic'ations, one of which -
. (T cold B) is Affected by NNI. RCS loop A has two T cold indication, one of which (T cold D) is Affected by NNI.
- 3) Hot leg level temperature compensation is Affected l by NNI.
I
{
- 4) Thot is Affected by NNI. i i
l i
i
\
l
. .. .>2.. . ;;,, +;: . .. -
O
.h_. , ._ g. . , ,. v . -
. .>y _. :; .' . .v _
+
- LOOR %.v-RX PWR RCSFL ,'{.* -k.n
. o 0 0*/.
lgut7 C. D1 s- . .
. j;;h p I Ef', ~ ^ '/ i f.~gg.,* -
,aemenk ?} emer'aE kb
,,,,,,,,,.j.
gj.
eus, ase
{ .' ; . -' - *7 . .,',-
n -
em an I **'**
85 - .
- u. _ ,
i, y
. .:f
~
b
,un ,,,.
m -
~
+.
fv.g. j
..e
- == f. ,em
.. w ' ' ' . . ..
5 .. , . , , . t .;. . N . m z, ., .s
/ '
a
, 7 _ j h ['., ,
h, g ' '
. .=4 e, :
e q.' 3 as W #l W ,
-= -me cae = *
" mi .
. ,,n , j, 4.g
_ e.
E
. ?/pO3 , 3 k, , , ,
l,- [,k,, (. x % k, E 4' . * ! _ h. . . . ' . ' .
FLUX / FLOW IMBALANCE DISPLAY NOTE: Not Affected by NNI I
i e
e t
l I I l
i r
O !
r
. n QA:.!T,W.].&:: 3.W&*1,.,#& b;? n:N':??:.?..
- ; . .. . . . h. u5. ,l. , ..W. -.:.m.h%+&.lg'W5i?? , , . w~-
.'7..'.'*'.* .. .-..:...
- _ . -' ' , . .
- % * . _ *~_,?'.Y,"...n...-,. , ;:, ..s'
'. ';' .~ Q -f ' '
. .c , .
- ,~ -_
- x. ' '-';" 5' t ;. .. . . .
- ** != y N;
. y+'( man ! -;y
.?riI ' f.;t.co'.,p ' C. 't:.RX
- o o gPWR . .+ ~~..?WCS v o o *s -',rFLOW
-9' 7.. w. ..
-f;.93;.' '; . L .: . *;,.seeg ...g:;... ' unm; Y&.\
- 3. r- i, . ., .- r.m - . y'.
- . . > .q newm . :- ~. ,
& m ' '
- G* ~'
i&~% ":' ~' '. ; ... _." } --
. . - _ _ _ . ._'.,_r.'.[.
l }'
.-)- .
e.a m . ; : .
i
, .7- ;--' . . .. .
._.;. .- ;=. .
a ,. _
q - . . . .. .
. . y,, w ,
EM : '. . . .
ggy g y
SM '. ' ' ' - ' . . . . .
. 2150 C I+' > - - .-
. SW . . .
1
.- sie. ,. . . . - . . . . -
. *. .:J ~..n> . ~ ~. :
r - -
1 M, ,
Sl4 ses
,, . u . . .
==.. . . . . . . , . ., ..
+..-
' f. p p .': - ~ }. ; .
b - ;; ;.Q., . 3:~
T*
e
. .Yl. / '
, o
. , .. == 4 *.:, -
~,. .
t 5:-8 0,.i .
.n e, . . -, .
.i
~
l
^
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. .. . . . . :s '- , :-
,..}
, .- '~Q . _
, , _ _ ,- :[ f ' l r
I REACTOR PROTECTION TRIP ENVELOPE P-T (NORMAL DISPLAY) l
. t NOTES: 1) Loss of of NNI or ICS power results in a reactor ,
trip thus this display is not used. ;
.' 2) Thot and Tcold Are affected by NNI. ,
i i
I I
I r
l l
I I
l l
f
I
-W.~~ #?' ..
b' ~
WNW?#%i$
?;.W!i5:'%Y*b M.~f'.r. . ef*, NRY@$$h%W::}9eb&.M M ? .'? ?.f 4** & W-
$4 " S ? $:%' i T.T: & N E L: R .
Equ RCS...A,: **ee*i.k . xxxx % ~ ..- ~ ****e*: - ~
Je.dasur.sw .; g 2.
R h m .**** 2: .xgMfF *- "UW "'s*sese; Vi& SRCS'.D fRCS: imsee%g-** ' ' < 4gys' Y ~* ~
~^
ise**cQggow,;ga.u--W:w -
i dim. ' * . cg ..
.T - C O L D D ce, i.m 1, . !
?C RCS LRcon=. F . ,- xx.. f._
~
- . .. . . o :- c-woT.R
.iesae.:., , .:73
.issa . - .. . . . .':
7".f 17 ' pf,p?.- NiQ '
- 1: : OTSG h meseea' . J,f . .'.;,.-; , - n o -* .. f* ~ naises f - j.J. .c j OTSG A meseso .?. .-? :. .e- -~v-r-HOT K .aisse w isesc . .~. ...,
. : 'i ,. ~ . . s . . .
~
cf :-: . . . :
~X- OTSG B me**ea m- s ::,;c. i OTSG D meenee- : ' VL:::? . . ..
-./- '. : 7 LU ~T*i.?q .3..>,..c.
-c. J -
1_
. ,ggx $. T-INCORE.e usme' db: fgy{p. . '_.
2 v CONT : NR maeone Q 9y_. _ . .. ;; . , .c 4y:; .::d ;. q, l
. ' CONT tdR mesas - ?y xxxf P2R' TEMP;assseaa . '.;(y"rt;-*;.5._ -
. . , . . ;r. :
1r CONT .WR masas. . ~. _ P2R TEMP weiseen ~ _ " = ' ~ . , ;d. .. ;,..; . - .
RCS R 6-
~f.h_b j. -
l
',. ' xxxxn . RC9 %gT & g-- _l c
RERCTOR TRIPS g
~
XXXX,Xf ,
, , , e ,,
.[ e:-! .CRD GR0UPS
.v e 1.~ ...S
~ SF RS -. CH ' '1 R J-~ 2:~X~ XXXXXX XXX; , - ' ' ' . '
~
.- - SFRSfCH 1B[3 .
- . , . . .~;.
- .
- . j.s
- . Y.i.:: .:' a m .n-NOTES: 1) Parameters Affected by NNI:
a) RCS LR PRESSURE (low range) b) T-COLD B
,- c) T-COLD D d) T-HOT A (only one of two is Affected by NNI) i e) T-HOT B (only cne of two is Affected by NNI) _
f) RCS A AT :
g) RCS B AT ;
i l
r- : + e..: S:.z.;s:;;,y:;g$,';'-a y.:x . - ~ : g: OmysW..;. p, EkN' h.4.,.,;3,y?y?.?.'
? ~.
ny'DW 'f -:.; :::m;:m. .; .
=
.. -?:Y? * .
m3g :$g.f~5&~ ,pc hf'N'-f.hu M.m' w;&.ft*.h :b::?:: .0 M&~A-2.:-w:h,.y. 3.c **
M &.; E.,. h.L:%2'-p. h, I
%ii&%' ,,i,3, '; J';4+ 3. *** smef - i!
4t NT.@~ 4 'sivisee ' .S' ? Inf.7' $ 'dei P2R., % A ;.. n'l- ,q ;l
@ i.trasene.?^E. P2R'g . ama. n b? w.w ' - m 1 i,, aan is. :o . -. .
i,
- N; g :.g,A ;.v.; 4 -J. . n. v 1. e.e..' c
- MeU 7 TNn j
~
.;- CFTJRg,temeF; V rI'n -:-;_ 3. case
, i 'C F T . 0 i.,3sses- 'X :'n-
~ .'. . -
9 "' .l
!l
- 'L*'
':-- - W;$ ..:,.. .
- .. . ; . - - HOT Los .R .. i.
3 SG.' RTH .,smoken T f f . . HOT LG A, .- .- l!
~ . ~. . SG A H ,see.y ~- c-
~
i 3 HOT ~LG.B - -
. i. W -
j!
HOT LG B l' ,l
.SG~B~H6 p - ,i-);.i. . i.;
SG B H ti <- - - . !
p.: ' ; N. ; s. -f5. '
~
- .'SG A .L i,,seeSG:A L', 1 . -
..; -- - . .w <
_~
SG- B L ,meses. - : : : :.
SOURCE R - X . x>:E r:c:
.,SG B Li., :.:'. . ~ SOURCE S- M . >::- F W M .,. J
-.INTRMED R . :-: . 5:.' :E :: on c = .'2
- - SG SGR
- SG B' SU SU 6
,asess.
.,s - : .-' ":-: ' :. . ;INTRMED B r::M 1. * ' C an~:-- 2, . . ':
A OP 6,3 i
- ~ - ~.I-'7 s
' . : r- - 1 : ' '1 1 ' ' '
. : -ry SG" . O,; OP .va i p~ i, POWER RNG A = j
~
POWER RNG BE - - ": : = c . . - ' . . . .
i f _ CST'1.,, ,- 1
. . . . POWER : RNG C t.-
'n-= Y '
- . i
-=
_37g zy., . w'. ::
.. .-1 .,..___ P._.O.;W
__ , .E_ R :. R N *;... G~D.1
_ .-;_ ;zCST.2,,,3 i._...:.-: .
. J ; ^ : .; -;.
~_ 7 ._ ~._'e ._l. . : _.
~ _ L L . .' ,1;'. .
' f,{
i
.- ' - - :[ ;_ d,f '*~. :.Q}Yq ..h y ..;QL; ' _. ' _ y
. . ~ . ~ ..) ;_ .
' '^
~ ' ^ ' q'1 ""-
- } : .4. .- ; - .. '- .._.; - .. .. :+ .5 -
)
NOTES: 1) Parameters Affected by NNI j a) MU TNK (Makeup Tank Level)
An additional Makeup Tank Level not Affected by NNI will be on this display.
b) HOT LG A, HOT LG A, HOT LG B, HOT LG B These four hot leg levels receive temperature compensation affected by NNI.
I I
)
l l
l l
l l
1 l l
l l
t
c m, -n....;. :: ..y. - :.p,., :..:4. ;[ n- a ^.W . +--Gat: 42g5%?):;;f2. <M
.. m :Q. 6 tV . &%y s '&.5k
. :.!Jcl.it..g:1- " ~ .s = *% g .g. N.. %,.
sf.,~in'r-
.- y - ,
- t. . 3 . ;. . % :_y y ';.f. .,ri_ .' .4&. .O. : W.
r-',;l
'g:'^;d;i.g. ..p.-. -
u . = . . .
l QQ'lf:'i~ ' ~Sf$1:f'.~.;__ '&f.TyQ f- .
.,7 ., y' l aM[ kNb.~. h J.Ih[... _ 4h ivh.5 k
' W} R F W f R :m iese 9.
. .I ana ' ~ -
' . J:
sm;1CI4TJ.. H1;;,:.'1 (X . :;5 . . . m == *==
- - ' U~ . -
. . ; ~~ . e*"'*'".w.-
W' ...';Z RFW 0 ' mewC
~
.m.CNTC JRFW H I cD, 2 1misee. ' . j: '. . .C : -: ,, *=a .sa. - - ,
... .- _ con .= .
' ' L P / D H A m eses'XXXX A MSL R: . : .:~.. F...: .: oram u v i
.:.. . LPeDH B .
XXXX = MSL B - .'- M . ;W ',- t ' '. -: :'
XXXan, RS.EFF :. ~ 2$^. :-:: :t- :h.-:),,$ '
- i HP I . S ' ms , Xxx RS ATF1 EFF . R F.xE x;-:'.4 m,, c -
!<? HPI C m zees _ XXX e,a . RAD .WST EFF f.' >':-:C?ypizi, c ; .
~
. _' HP I . D.' . ms . XXX ares
.: tETDOWrw. . .. X X X anse ., ~
waanian X X X ane
.s . * - *"- i w m XXX , CONT-H2 1 mi, :..X=qr
. . . .nns:.ur mm X X X ,,, CONT :H;2 2 ,es .e" X . :< .- ~ J.--. b c.~- ( ~,
P-' SERLINJ : ms .XXX 1.-> . s f. . . :
.- 1-- R C S D O R O N ... v " '. : -
.n .
'f I -.
.r1FW n g .
.- ;; ' ~
MFW B "
.Y - "o i .' }. .. .. . 1
. . ,.?.'. . _ .cf 7 - - ,
.. ; ~'/.RCS '.TOTRL .' - .i-:xx ,, S b ,U -6 5 - .i.8 . ' ' %- T Yi+.'. .L
. r.x.a .?
a ;
. . s. -g . . . .
c u ..
. - . / <
I NOTES: 1) Parameters affected by NNI:
a) Letdown l 4
A non-NNI affected letdown flow is provided t
b) Makeup A non-NNI affected makeup flow is provided c) MFWA, MFWB l
l l
k
h
' ~^
- *:,'$ O~
- I'
. = .p -;.' -r.x..
^.R -'*?.
N" - . $1. . ' .,.o...u..& .-
. . n; .' . , ;.
l -
- .. . . ,2:;,
.,a~.
DE!::q C - Y i %. i' ~--.':=;:-:;. ? % L:
I
.. f.: :'.,,.O :..,g. , ?.*:-
. .. .. s m . e s ' 3..
T,C
+ ~ ; , ... . . . g:
-. .' .s%. c ;.'. ._} .i f f s
- *; ., * .l c. ;
., 'n ' : I^ : + ~s.~ L.%, y
.,.? f:. . ' . , '
, _. . ,; .:: r s . . .,
..p.
~y*,
- - ' . [ ^. ..;....<,. . . . . _ L a.,-
. _,. y
-_ . :A ._ :,., 3 - 3 egg g d - . , , _ . ,
< 'M,. -: ;.'f r. .. . . . , . . . .
. J ' .g [;. -- 2.; .- fl l 1 ~ f.-~uw~ j=a=n=r man _. 7..~l r
i . -f f u D4 SUCT'S - - HU2OOO 1 - CLOSED ' *r == - -:; - " 5
- C DH SUCT : - HU2OOO2 NOT CLOSED *
- i
' ~ ? - DH LT DRN ' HU2OOO3 NOT CLOSED * *-
-l.=.SG"~ ENRG SUMP BLWDWN HU20611-' CLOSED > .:==va . 7. - ~ '
HU261OS 1~~ENRG SUMP NOT Ct OSED .* **i = . s s '.
HU26106 " CLOSED ~ 4:w>~
,,.:,.r. . .. . .
.RCS MU SFU22OO9 SFU23604'~ NOT CLOSED;m :
. . -l-CLOSED ^ -< 6' ~
2' .J3 ' 6SFU22023
. PRG"IN AB - SFUS3SO3.<J ' CLOSED ~ t', -
. r. " -
PRG IN RB SFU535_04 NOT* CLOSED ~'- - ^'
!t . .-
- - o. :
K '" W. :-'PRG OUT RB SFU53605 .'. CLOSED: . ' ~. :n. . K,; i' $.r ':
EQLIZE AB SFU53610 ~ CLOSED
' ~
44 '
Ji EQLIZE RB
~ SFU53603~ eNOT CLOSED . ' ' ' '
NORM. SUMP' - SFU663OO.- "NOT CLOSED ~.c3 . .
!, - ; NORM' SUMP ; - SFU6dli309 4,NOT (CLOSED uf 5N
.:q- 5:.; ,f.-. .i.(={".i;if lyk . ..yx'ky_:Q W
~
. . 7. . f.h . f, ',j ~ -l.Y.C:i' f..-'.. .. ill_f j.. '. W WYf _.,' '^ .
1 1
= l NOTE: Not Affected by NNI l 1
1 i
1 a
e m.
I l
i i
1
l ,
l I
l l
gc=.<QCcLQ
.kb dNhN b .N.
- n*v
\ )_Q J: S T -+.C f;.3? 3^ h njy.%:k % .:v.fffgg . _. yQ- : $;: . ,-.
\
i M N.hfb b .:';:h N 5.d:N
- c-nk::tx::N y& ?' **R' x ., k* h ? ?
l l $5L '.: . .:: ' r. ..-+;. ..' J SFU24013 J 'CCOSE p : ~ ~ .
L
.- Jib'S lll5.~'
1 ':JJiSEAL.-RT A .**'a a=*
l i
- - , SFU24004 :- NOT CLOSED.5*a'a' i y:- :'C<$.RCS t SEAL DRAI E RT. HDR . SFU60003 J NOT ' CLOSED ?"* **J .n'~~
- 7. .
- v :.RCS UNTMHD j v e SF060.O'01 E NOT CLOSED 89 -~
r:
< -;h.'RCS.lONT HD i.-'SFU60002c:pLOSED.:H i M +$ TT
^
^ 'PZR - L I Q _ AB. ' . : SFU7.OOO2 V- CLOSED / c r W-;.S i . z .. >
32d AlPERr-LIQ;RB .* SFU79991W NOTTCLOSEDS. Til 1R -
- ~ ;, 3'
- , ;Q ,.[ e2R
- ' ~ ' .z. GAS
, .' ' .,_ _. *RB
,- DO'F .' -
- SEO70003ffNOY'~C%.O.SE.D
" a ,1. f L;r.:- ,.:...;
~~
' ~ ,' $;?Z - ;
' .: M
~
SFU72SO2-:-f CCO' SED' ' n v -
J'PRT~ GAS RB --
. SFU72SO1- . ' NOT CLOSED. : r --
... .N2 TO PRT- 'SFU92520.JCLOSED. ..J Y ' 1 , ;
..J.QJJ'A.-H2.PRG
.E.1'.i '3
'-SFU53612 CLOSED .. gh'M,: .
AB: .'SFU53615' ~
CLOSED- .: NM ' -'
.T.:_ ATH2! PRG B1-H2..PRG AB RB S F U 5 3 6 1 3 NOT CLOSEDi1.i
@@?1,8
~ :: : f c.H2 -PRG. RB . . SFU53616 NOT CLOSED 4h f . Sip:PIERh CODE:
=<.g!; PERECODE '2' . + b= PSU2 %596': :. CLOSED 1. . G. PSU21.507 ' NOT C
- 5
. M':. .
1
-v . ..J :;.t,.PE.R.
P, py . - .OR.,U. n
,.l
, s, .. PSU2151-1. .*. CLOSED ~ : -- : f-'-V'.~
7 -- .
i j
Q:M ..
Q:kNiN.h;f'Af':k.
1:': \. ' ~ - I -f . . '.
N f ,: $ k:l k ?~' Y
' . . .. . !: - -t.i ', . - ,
' k -? :L n . - '
2 ' $. k $ 5. F}.? Y : l A Y'
- - =-
NOTE: Not Affected by NNI
=
I 3
1 i
i L