ML20205A216
| ML20205A216 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 03/20/1984 |
| From: | Mccollum W, Mroczka E, Palmer R CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-569, NUDOCS 8810250425 | |
| Download: ML20205A216 (11) | |
Text
.
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E.J. Mroczka 8-25-83 Form Approved by Station Superintendent Effective Date STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number E0P 569 Rev. 1 Title E0P ADMINISTRATION PROCEDURE Prepared By W. R. McCollum B. REVIEW I have reviewed the above procedure and have found it to be satis'actory.
TITLE SIGNATURE DATZ DEPARTMENT HEAD ( k, d' 2[1F/fV h.Y bt "V k W 2 1kV C.O. KOTde ,
Eh/ ry C. UNREVIEWE0 SAFETY QUESTION EVALUATION DoCU:4Ei1tATION REQUIRED:
(Significant change in pro':<aure method or scope /
as described in FSAR) YES ( ] NO [/ ]
(If yes, document in PORC/SORC meeting minutes)
ENVIRONMENTAL 1MPACT (Adverse r.nvironmental impact) YES ( ) NO [d (If ye s, document in PORC/50RC meeting minutes)
D. PROCEDUfE REQUIRES PORC/SORC REVIEW YES ( NO [ ]
E. PORC/SC 4C APPROVAL SI'RC Meeting Number hb! _
F. APPRO\AL AND IMPLEMENTATION The at tached procedure is hereby approved, and ef fective on the date below:
h]c*y 0 !Q 3 20-/r St ation/Serviqf/tJnit Superintendent Effective Date SF-301 Rev. 6 8010250425 00'.007 PDR ADOCK 05000213 P PDR
- _ . . , _ _ , . _ , _ _ , _ _ _ . _ , _ , . _ _ _ _ . ~ _ . - _ . _ - . __
. E0P Administration Procedure E0P 569 Page 1 Rev. 1 N,]
UNIT 1 E0P ADMINISTRATION PROCEDURE-PAGE NO. EFF. REV.
1-4 1 EMERGENCY OPERATING PROCEDURES MILLSTONE UNIT 1
References:
- 1) Emergency Procedure Guidelines, Millstone Unit One
- 2) Emergency Procedure Guidelines, Appendix B
- 3) Emergency Procedure Guidelines, Appendix C
- 4) ACP-QA-3.02, Attachment A
N
. E0P Administration Procedure E0P 569 Pr.ge 2 Rev. 1 ,,
~
O 1. PURPOSE ,
Based on the BWR owners group Generic Emergency Procedure Guidelines, 7 and the Millstone Unit 1 Plant Specific Emergency Procedure Guidelines, i the following' Emergency Operating Procedures have been developed:
E0P-570 RPV Level Control i E0P-571 RPV Pressure Control E0P-572 Rx Power Control i
E0P-573 RPV Spray Cooling E0P-574 RPV Steam Cooling ,
E0P-575 RPV Level /Rx Power Control E0P-576 RPV Level Restoration E0P-577 Emergency RPV Depressurizatien l E0P-578 RPV Flocaing E0P-579 Alternate Shut-down Cooling E0P-580 Containment Control E0Ps 570-579 restore and maintain RPV water level within a satisfactory -
i 1
range, shuts down the reactor, controls RPV pressure, and cools down :
.the RPV to cold shutdown conditions.
t E0P-580 controls primary containment temperatures, pressure, and level whenever Suppression Pool temperature, Drywell temperature, Drywell pressure, or Suppression Pool water level are above their !
normal operating limits, or if Supression Pool Water Level is below its normal operating limit.
l At various points within the Emergency Operating Procedures, limits f l
are specified beyond which certain actions are required. While [
conservative, these limits are derived from engineering analyses f utilizing best estimate (as opposed to licensing) models. Consequently, f these limits are not as conservative as the limits specified in Millstone 1 Safety Technical Specifications. This is not to imply that operation beyond the Technical Specifications is recommended in an emergency. Rather, such operation may be -equired under certain E0P 569 E0P Administration Procedure
9
- E0P Administration Procedure E0P 569 Page 3 Rev. 1
-3, x-degraded conditions in order to safely mitigate the consequences of those degraded conditions. The limits specified in the Emergency Operating Procedure establish the bour.daries within which continued safe operation of the plant can be assured. Therefore, conformance with the Emergency Operating Procedure does not ensure strict conformance with Millstone Unit 1 Safety Technical Specifications.
The entry conditions for the Emergency Operating Procedures are symptomatic of both (1) emergencies and (2) events which may degrade into emergencies. The E0P's specify actions appropriate for both.
Therefore, entry into E0P's is not conclusive that an emergency has occurred.
Entry condition's listed which are applicable to the 3 basic Rx Pressure Vessel Control pink colored procedures (EOP's 570, 571 &
572) are any of the following:
/) (1) RPV water level less than +8"
-/ (2) RPV pressure greater than 1085 sig.
(3) Drywell pressure greater than 2.6 psig (4) An isolation condition exists wrich requires or initiates a reactor scram.
(5) A condition which requires a reactor scram and reactor power is above 3% or cannot be determined.
In the event that plant conditions degrade beyond the scope of E0P's-570,571, & 572, the operator is then directed to the yellow colored contingency E0P's as conditions warrant.
Entry conditions listed which are applicable to the basic Containment Control pink colored procedure (EOP-580) are any of the following:
(1) Suppression Pool level above 13.8 ft.
(2) Suppression Pool level below 13.5 ft.
(3) Drywell pressure above 2.0 psig.
(4) Orywell temperature above 150 F.
(5) Suppression Pool Temperature above 90 F.
O V
E0P 569 E0P Administration Procedure
E0P Administration Procedure E0P 569 Page 4
.- Rev. 1 O In the event that plant conditions degrade beyond the scope of E0P-580, the operator is directed to the yellow colored contingency E0P's as conditions warrant.
- 2. ENTRY CONDITIONS 2.1 This procedure is entered in accordance with the entry conditions dictated by individual Emergency Operating Procedures.
- 3. OPERATOR ACTIONS 3.1 Follow OPERATOR PRECAUTIONS (OPS Form 569-1) which are generally applicable at all times to the Emergency Operating Procedures.
3.2 Use TABLE I abbreviations (OPS Form 569-7,) as necessary for
- additional guidance in execution of Emergency Operating Procedures.
RP:ejz O
I I
l l
1 O FINAL E0P 569 E0P Administration Procedure
e .
4 I
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D. C. !N?ENT CwANOT AUT*0'!!!.ft:N (N/A for Intent chaeges)
McN !NTENT CHANGE 1,000E3 >J ft't! $10Narval C_A ?,!
$nt's $ wee v'sor faa suty) 1.
2ad $to comeve eace !__
fest 5.ee-viser f!$7 Caly)
E, tiv!!.!3 Cesaetment Head N,T , d' /
I p r. $st::::: u.'stvtr.to $ Art?< Cut $ tCN tw.vart:N SE:UttE0 Modifies Intent of process i and caanges oceastien of systems as described in design doc.eents. _
YE3 ( ) No M
(!' yes, pe fs a .ritten U$0 determinatten aed Safety !valsation, and contact wanage , $afety Analysis trancs to determine need for Integrated Safety Eva1watton.)
ENyta:Nr' ENTAL #Ev![w n_EQUIRE3 (Adverse environmental imcact) tt$ ( ) NO [
G. $8t;;t!C $28(?v E /At,vAttCN tt0ut t!3 af fects ressonse of safety syste-s, performance of systems
.nica say have been credited in the safety analysis or non credited syste+s .hten may indirectly affect safety systes response. YE5 ( ) NO (
(If yes. cerfors .ritten Saf ety (valwation and Contact wa941er, $af ety Ana*ysis Branen ta detersiPe need for Integrated Safety Evalwatiot.)
H. !NI[02ATED $AF(TV [yA(yAf!CN 410g! RED f[$ ( ) NC ,
- l. P:8 /$0AC R(**??'(NC$ APPtQv&L (or confir*ation of interit C*a ge ithin 14 days 1
.ceseent all f t$ responses to sbove questions in 7:R:/$02 seettng strates;
. h:::eetingus,eer /-pp.r3 J. AP8e0 VAL Ah0 (M8t.twtNtattCH TPe change is hereby imple*ented and is ef fecthe this date, escent f or inter's changen mica v'e impletented and ef fecthe per the Awthori:nism of 0 aeove.
aation .w.r_
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,nse a s n a e.,ntese,t s / ,, in aate
$F:0 ce,s.JP)/M ta/ loft
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& hf! ShNn EFFsCTIVE DATE s-n-n PORC MTG. NO.
g FORM [ ROVED'BY' UNIT 1 SUPERINTENDENT b OPERATOR PRECAUTIONS i'
I i
GENERAL i
This section lists "Cautions" which are generally applicable at all
+ times.
hi-CAUTION #1 1 t Monitor the general state of the plant. If an entry condition 4
for either EOP 570, 571, 572 or 580 occurs, enter that procedure.
When it is determined that an emergency no longer exists, enter the appropriate normal or off-normal operating procedure, as applicable.
Oi CAUTION #2 Monitor RPV water level and pressure and primar) containment temperatures and pressure f rom multiple indications.
4 CAUTION #2A When conditions are stabilized, review the status of control room panels. This review shall include annunciators and system ;
parameters to be those which should be expected, Off-normal or {
unamplained conditions shall be :mmediately reported to the
! Shift Supervisor, i
l CAUTION #3 If a safety function initiates automatically, assume a true initiating even has occurred unless otherwise confirmed by at ,
- vn least two independent indications.
OPS Form 569-1 Rev. 2 Page 1 of 3
,i' s
[ %
CAUTION 4 Whenever LPCI is in the injection mode, inject through the heat i exchangers as soon as possible.
CAUTIONS #5 Suppression pool temperature is determined by the CRP 903 l
'femperature Instrument (Suppression Pool Temperature Channel A/B). Drywell temperature is determined by the CRP 903 Temperature Instrument (TI-1602-5A).
I l CAUTION #6 ,
l Whenever drywell temperature near the instrument reference leg j vertical runs (TI-1602-5A) exceeds the temperature in the table and the instrument reads below the indicated level in the table.
the actual RPV water level may be anywhere below the elevation O of the lower instrument tap.
I Temperature Narrow Wide Narrow Wide Range Yarvay Range Yarvay Range Gemac Range Gemac 150*F -50 -325 0 -52 200*F_ -49 -317 0 -45 250*F ,
~47 -307 0 -38 300*F -44 -296 0 -29 350*F -41 -283 0 -19 400*F -38 -269 0 -7 450*F -34, -253 0 6 500*F -30 -233 0 21 550*F -26 -210 0 40 OPS Form 569-1
.le v . 2 Page 2 of 1 JW 2 013:3
i O -
CAUTION #7 j
Narrow Range yarway indicated levels are not reliable during !
. I rapid RPV depressurization below 500 psig. For these conditions, utilize Wide Range Yarway and Wide Range Gemac Level Instruments to monitor RPV water level.
CAUTION #8 Observe NPSH requirements for pumps taking a suction from the Suppression Pool. If it can be determined that Drywell pressure (CRP 925 PR 1602-9) did not exceed 10 psig at anytime, then use the NPSH requirement curves for non-LOCA condition (see Figures Ic and Id, Page 3b), otherwise use the curves for LOCA condition (see Figures la and Ib, Page 3a).
O O OPS Form 569-1 Rev. 2 Page 3 of 3
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NPSH Requirements for LPCI' Pumps OPS rorm 5604 Rev. 2 Page 3a JUN 2 e US5
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NPSH Requirements for LPCI Pumps OPS Form 569 1 Rev. 2 Page 3b JUNE E