ML19209B588
| ML19209B588 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/02/1979 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| References | |
| 1102-16, NUDOCS 7910100191 | |
| Download: ML19209B588 (12) | |
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00ER0LLED COPY DEda 0 08/02/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 OPERATING PROCEDURE 1102-16 C I-N. inim .L F)1LE RCS NATURAL CIRCULATION COOLING -
Table of Effective Pages cuidR0Lu~ir-d boP Paoe Date Revision Pz.ce Date Revision Pace Date R evision 1.0 08/02/79 0 26.0 51.0 2.0 08/02/79 0 27.0 52.0 3.0 08/02/79 0 28.0 53.0 4.0 08/02/79 0 29.0 54.0 5.0 08/02/79 0 30.0 55.0 6.0 08/02/79 0 31.0 / 56.0 7.0 8.0 08/02/79 0 32.0 6 57.0 08/02/79 0 33.0 i 58.0 9.0 08/02/79 0 34.0 59.0 10.0 08/02/79 0 35.0 g\
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45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0. 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recom nos Approval Unit 2 Staff Anm ends / Approval Approval ' / Date Approval I \/ ~~
Date Cognizant Os;it. Head Cogniza'nt Deit. Head Unit 1 PORC Recommends A:: proval Unit 2 PORC Recotimends Ahproval GA&ss Date Vbl79 Y i
~
Date y Chaerrnen of PORC Chairmis, cf PORC-Unit 1 Superintencent Approval ,
Unit 2 Superin(endent Aobroval CI sV7#' Date i'?O -
. . Date o
Manager Generat?on Quahty Atsurance Accroval /(. Date '-
rw ss 4 . .m 1122 310
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1102-16 Revision 0 08/02/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 OPERATING PROCEDLRE 1102-16 RCS NATURAL CIRCULATION COOLING CONTROLLED TRANSITION TO NATURAL CIRCULATION NOTE: This Procedure is to be utilized in the event there is a need to stop reactor coolant pumps. The use of reactor coolant pumps is preferable to natural circulation for maintaining RCS flow.
1.0 INITIAL CONDITIONS 1.1 Reactor has been tripped for at least 10 minutes (In emergency conditions loss of flow may be coincident with reactor trip).
- 1.2 One or more RCP's operating (one per loop is preferred).
1.3 Feedwater available d
1.4 HPI available 1.5 Reactor coolant pressure stable 1.6 T cis stable (cooldown rate not to exceed 10 F/hr, no heat up) with steam pressure being maintained by the turbine bypass system.
2.0 LIMITS AND PRECAUTIONS 2.1 Maintain RCS subcooled 2.1.1 Before RCP's tripped (refer to Figure 1).
2.1.2 After RC?'s tripped (refer to Figure 2).
2.2 Normal cocidown limits should be maintained (including NOT limits).
Refer to Figure 1 and 1A 1102-11 2.3 Maintain pressuriser level 100 inches.
J.a Prior to stopping the past pair of operating 3.CP, OTSG level must be establisned at or above 50'; on the operating range anc aintainec there wnile on natural circulation.
,.0 \\ll
1102-16 Revision 0 08/02/79 2.5 The conditions of pressure and temperature a'iewed by Figure 2 must be maintained at all times or RCP operation and/or HpI cooling es tablished.
3.0 PROCEDURE 3.1 Establish subcooling in RCS per Figure 1 u.ing the following as -
required:
3.1.1 Use available pressurizer heaters to increase RCS pressure.
3.1.2 Decrease secondary pressure using turbine bypass system to decrease Tg .
3.' 3 Use additional makeup flow to maintain or increase RCS pressure and pressurizer level.
3.1.4 Initiate HPI if required. .
3.1.5 Increase steam generator level.
3.2 Take hand control of FWV16A and B and sicwly increase OTSG to 50%.
3.3 Start Emergency Feed pumps EF-P-2A&B and establish control of OTSG level by taking hand control and opening EF-V-30A&B until Emergency Feed Flow can be seen on console.
CAUTION:
Do not increase OTSG level above 60% on the operating range.
L 3.4 Close FWV16A/B 3.5 Establish pressurizer level between 100 and 200 inches with level control in automatic.
3.6 Verify SG level is greater than 50% and stop the operating RCP's simultaneously.
3.7 When OTSG ievel has decreased to < 505 and EFV30A/B have demand to be partially ocen place the control station in AUTO.
2.0 1122 312
1102-16 Revision 0 08/02/79 3.8 Maintain constant or slowly decreasing (cooldown rate not to exceed U
10 /hr, no heatup) Tc by controlling steam pressure with the turbine bypass system.
3.9 Continuously monitor Th in both lo ps to assure the pressure and temperature allowed by Figure 2 are maintained. If the conditions of Figure 2 cannot be maintained, go immediately to Step 3.12.
3.10 Verify natural circulation by one or more of the following methods.
NOTE: Indication of natural circulation may not -tablize for 15 30 minutes.
- 2. Verify heat removal from OTSG's.
- a. Turbine bypass valve positions. -
- b. Atmospheric dump valve positions.
- c. Feedwater vulve positions.
- d. Feedwater flow.
NOTE: May not indicate for low decay heat case.
- 3. Incore thermccuple temperatures stablize.
3.11 If natural circulation is confirmed by Step 3.10, continue to remove decay heat with natural circulation.
3.12 If natural circulation cannot be confirmed by Step 3.10, maintain the pressure and temperature limits of Figure 2 or restart one RCP in each loop.
3.13 If the limits of Figure are exceeded and at least one RCP cannot be started, initiate HPI cooling and refer to EP 1202-6 " Loss of Reactor Coolant / Reactor Cociant Pressure".
3.14 If feecwater flow is lost:
- 1. Star; an RCP.
1122 513 3.3
1102-16 Revision 0 08/02/79
- 2. Immediately attempt to restore feedwater flow. il feedwater flow is restored, transition to natural circulation may be attempted again starting at Step 3.2.
- 3. If the limits of Figure 2 are exceeded or OT5G 1evel drops below the low level limit, initiate HPI cooling.
1122 314 4.0
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1102-16 Revision 0 03/02/79 ENCLOSURE I 4.0 EXPECTED PLAriT RESPO!15E 4.1 General This procedure is to be utili:ed in the event that there is a need to secure reactor coolant pumps with initial conditions as -
defined in Section 1.0. The principles which fom the basis of this procedure are:
- 1. It is preferred to use reactor coolant pumps to supply core flow.
- 2. The hot leg of the RCS must be maintained subcooled to prevent famation of a steam bubble which could inhibit natural circulation. -
- 3. With natural circulation or reactor coolant pumps unavailable, the alternative is the HPI ccoling mode.
s 4.2 Plant response to long term actions 4.2.1 Establishing desired conditions i- the RCS Paragraphs 3.1 through 3.3 will establish conditions in the RCS favorable to the initiation of natural circulation.
, First adequate subccoling must be established in the RCS
, preferably by raising RC pressure using pressurizer heaters or by lower primary temperature using turbine bypass system valves.
Next, steam generator level must be raised to a level kncwn to promote natural circulation.
1122 317 7.0
1102-16 Revision 0 08/02/79 Caution must be exercised during the feeding of the generators since overcooling may result in a fairly rapid decrease in pressurizer level an.1 RC pressure. The attached Figures 3 and 4 provide guidance on the exoected system response during the feed operation.
It should be noted that it may be desirable to raise OTSG level above the 50% level in the operating range. Since it is known that the 50% level is adequate for initiation of natural circulation, this procedure was based on that level.
If the decision is made to raise level above the 50% level caution must be exercised to prevent overcooling the RCS causing loss of RC pressure control or pressurizer level. -
The final action prior to tripping the RC pumps is to stablize pressurizer level. After the pumps are tripped, Th*
increase with Tc remaining essentially constant, resulting in a pressurizer level increase.
4.2.2 Securing the RC pumps With steam generator pressure being automatically controllec, Tc can be expected to remain essentially constant after tra RC pumps are secured. With the decrease in RC flow, core T h
will increase. As a point of reference, a typical increase of 25-35 F in Th is expected. Figure 1 is intended to provide adequate subcooling before the RC pumps are secured, so that U
the hot legs will be at least 20 F subcooled after the pumps are cff.
Stopping the last RCp causes the OTSG level con:rol to shif: tc the emergency feedwater system.
1122 318 a.g
1102-16 Revision 0 08/02/79 4.2.3 Verifying natural circulation flatural Circulation may be verified by:
- 1. Monitoring that Tc stays essentially constant with T h
increasing and then leveling out. The hot leg should emain subcooled.
- 2. Monitoring the heat removal from the OTSG's signifying that primary flow is available to remove core heat production.
- 3. Monitoring incere thermocouples. The temperatures should rise and then level off and stablize. The final temperature will be a function of many variables including decay heat removal . -
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