ML18038A629
| ML18038A629 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/01/1984 |
| From: | Lempges T NIAGARA MOHAWK POWER CORP. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8403060439 | |
| Download: ML18038A629 (244) | |
Text
4 REGULATORY&FORMATION DISTRIBUTION S M (RIOS)
A'L.CESSION NBR s8403060439 DOC ~ DATE t 8LI/03/0 f NOTARIZED! NO DOCKET' FACIL:50 220 Nine Mile Point Nuclear 'Stationr Uni,t 1J Niagara Powe 05000220 AUTH NAME AUTHOR AFFILIATION L'FMPGESJTBE ~ Niagara Mohawk,Powe'r Corp.
RECIP ~ NAIIE" RECIPIENT AFFILIATION VASSALLOJ D s 8 s Operating, Reactors Branch 2
SUBJECT:
Forwards marked up procedures generation .packaget for implementing..symptom>>based emergency operating proceduresJ per Sup 1 1 to NUHEG 0737 for comment, DISTRIBUTION C9 E: AO 3SCOPIES RECEIVED:LTR L'ENCL J SIZE:., l.Z~
TITLE: OR/Licensing Submittal: 'Suppl 1 to NUREG 0737(Generic Ltr 82"33)
'OTES:
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NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST. SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 March 1, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Dear Mr. Vassallo:
Provided herein is the Nine Mile Point Unit 1 Procedures Generation Package for implementing the symptom based Emergency Operating Procedures. As outlined in Supplement 1 to NUREG-0737, the package includes:
(1) a description of the method for developing plant specific Emergency Operating Procedures from generic guidelines; (2) the Emergency Operating Procedures Writer's Guide; (3) a description of the Verification/Validation Program; and (4) a description of the Training Program.
F'.
Supplement 1 to NUREG-0737 indicates that implementation of the Emergency Operating Procedures is not contingent on Nuclear Regulatory Commission review and approval of the Procedures Generation Package. However, Niagara Mohawk requests that significant comments be transmitted to us as expeditiously as possible to allow for consideration in the implementation process.
Sincerely, NIAGARA MOHNK POWER CORPORATION
'DR0>060pgq hooch 05 80~p022O E. Lempg s
- (
pDR Vice President Nuclear Generation TEL/BDW:slw Enclosure
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Nine Nile Point Unit 1 Procedures Generation Package Niagara Mohawk Power Corporation March 1, 1984
CONTENTS Description of the Method for Developing Plant Attachment 1 Specific Emergency Operating Procedures from Generic Emergency Procedure Guidelines Emergency Operating Procedure Writer's Guide Attachment 2 Verification/Validation Program Description Attachment 3 Training Program Description Attachment 4
ATTACHMENT 1 Method for Developing Plant Specific Emergency Operating Procedures from Generic Emergency Procedure Guidelines
Method for Developing Plant Specific Emergency Operating Procedures from Generic Emer enc Procedure Guidelines Niagar a Mohawk Power Corporation is a participant in the Boiling Water Reactor Owners Group Committee for developing generic Emergency Procedure Guidelines. Revision 3 of the Guidelines has been reviewed and accepted by the Nuclear Regulatory Commission, as noted in the staffs'ovember 23, 1983 Safety Evaluation Report. The Boiling Water Reactor Owners Group generic Emergency Procedure Guidelines will form the basis for the Nine Mile Point Unit 1 specific Emergency Operating Procedures. Changes to the Emergency Procedure Guidelines will be appropriately incorporated into the Nine Mile Point Unit 1 plant specific Emergency Oper ating Procedures only after Nuclear Regulatory Commission review and acceptance has been obtained.
The personnel involved in developing the Nine Mile Point Unit 1 plant specific Emergency Operating Procedures are members of the plant's operating staff. Niagara Mohawk has participated in the Emergency Procedure Guideline Committee of the Boiling Water Reactor Owners Group since its incept'ion.
Therefore, familiarity with the plant and the generic Emergency Procedure Guidelines is assured.
Plant specific information will be reviewed for inclusion in the Emergency Operating Procedures during the conversion from the generic Guidelines.
Sources for plant specific information include the Nine Mile Point Unit 1 Final Safety Analysis Report, Technical Specifications, existing Special Operating Procedures, normal Operating Procedures, and as built plant dr awings. Extensive operating experience provides an additional source of information.
The generic Emergency Procedure Guidelines will be reviewed step by step, substituting in plant specific information as appropr iate. This will result in plant specific Emergency Procedure Guidelines. The plant specific Emergency Procedure Guidelines will be reviewed for technical accur acy in accordance with the Emergency Operating Procedures Verification Program. This review will insure that plant design features and system configurations which have been incorporated into the plant specific guidelines are consistent with the underlying philosophy and technical basis of the generic Emergency Procedure Guidelines. Calculations performed to determine or support plant specific numbers, limits, or curves will receive an independent review, in accordance with Niagara Mohawk's guality Assurance Program. The plant specific Emergency Operating Procedures will then be generated in accordance with the methods described in the Writers Guide. For illustrative purposes, a marked-up copy of the "RPV Control" section from the generic Emergency Procedure Guidelines and a preliminary draft of the plant specific Emergency Procedure Guidelines are attached..
As described in subseauent sections, the Emergency Operating Procedures will be subject to verification and validation programs prior to implementation.
Page 1 of 1
I EMERGENCY PROCEDURE GUIDELINES Revisf.on fjg 0
/eh~~, JP+
December , 982
EMERGENCY PROCEDURE GUIDELINES 0
Revision P' gab~~, egg+
December , 982
TABLE T ABBREVIATIONS Automatic Depressurization System Average Power Range Monitor CRD Control Rod Drive gC ErnavqEencq C~<ansCv ECCS Emergency Core Cooling System EUZ t=rae~ency Vow'Warm Spcb e HCU Hydrau1ic Contxol Unit Heating, Ventilating and Air Conditioning HVAC LCO
(~
Limiting Condition for Operation KC)
LOCA Loss of Coolant Accident ec on LPCS Lou Pressure Core Spxay MSIV Main Steamline Isolation Valves NDTT Nil-Ductility Transition Temperature NPSH Net Positive Suction Head nfA RPS Reactor Protection System RPV Reactor Pressure Vessel RWCU Reactor Water Cleanup (See Wl/8)
SLC Standby Liquid Control SORV Stuck Open Relief Valve SRV Safety Relief Valve (I>>4) Rev. 3
OPERATOR PRECAUTIONS This section lists "Cautions" which are generally applicable at all times.
CAUTION Pl Monitor the general state of the plant. If an entry condition for a
[procedure developed from the Emergency Procedure Guidelines} occurs, enter that procedure. When it is determined that an emergency no longer exists, enter [ ormal operating procedur CAUTION 42 Monitor RPV vater level and pressure and primary containment temperatures and pressure from multiple indications.
CAUTION d3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications.
UTION 84 Wheneve R is the LPCI mode, n)ect rough the heat e ha ers as soon as po le.
(I-5) Rev. 3
~~gag/~
vaCuez +y" +ha
~ A~ ~~~~>'~
/nckccctk 8W p<NI Wmgoarurhc+c. gnakerS l Occvt +~ cled g foo~
CAUTION g +
Suppression pool temperature is determined by Dryvell temperature is determined by g Her Znc4c~~ values Tedge.ra.ta44L NtcWrz Acu.+enL ~ "L" gao~
CAUTION 8 Whenever [temperature near the instrument reference leg vertical runsj exceeds the temperature in the table and the instrument reads below the indicated level in the table, the actual RPV Mater level may be anywhere belov the elevation of the lover instrument tap.
Indicated Instrument any 617 in Shutdown Range Level ( 500 to 900 in-)
107oF -107 in- Wide Range Level (-150 to +60 in )
310oF 19 in. Narrow Range Level 1
( 0 to +60 in.)
545oF 168 in- Fuel Zone Level ( 200 to 500 in )
[*List in order of increasing temperature.]
CAUTION 8 Res~~//array CP indicated levels are not reliable during rapid RPV depressurization below 500 psig. For these conditions, utilize 4li c4 Ron o 9 NAL ilhh+Yliwe.A~
to monitor RPV water level.
(IW) Rev. 3
0 j
\ t I P V
' ~ ~ ~ ~
r CAUTION d V
Observe,NPSH requirements for pumps taking suction from the suppression pool.
VV ~&
V ~ Vt
~ ~ I ~
'I ' \
~ 1
'.L ~
- 40. 4 10-psig o u-00 Q
5 psig a < 220 S
S CL Cl C5 0 psig cL. E 4l 200 RHR NPSH Limit 2 4 6 8 0 RHR Pump Flow {X1000 gpm)
)VO EH/
240 psl9 Punrp ou OO 5 psig 0
220 0 psig S 4I a.
cL E a
ch I 200 LPC PSH Limit 2 4 LPCS Pump Flow (X1000 gpm)
- Suppression chamber pressure Suppression pool at normal ~ater level
( I-7) Re v. 3
s s Ni a
s e
"; r. I'"
'. C ION 09 If sign s of high suppress'ool Mater level 12 ft. 7 in. ( 'gh level suction in rlock)] or oM condensate storage tank ter 1 el [0 in. (loM level suction 'ng oe}c)] occur, confirs) aatomat$ c tr fer af.wr hagtially
~ e e ~ ~ .4
-transfer HPC ', CS, .and RCIC suction from the c dentate torage-tank to the su ession poa SPECIFIC-This section lists "Cautions" which are applicab'le at one or more specific points Mithin the guidelines. Where a "Caution" is applicable, it is identified with the symbol CAOIION P Do not secure or place an EBS in MANUAL mode unless, by at least two.
independent indications, (1) misoperation in AUTCNATIC mode is confirmed, or (2) adequate core cooling is assured. If an ECCS is placed in MANUAL mode, it vill not initiate automatically. Make frequent checks of the initiating or controlling parameter. When manual operation is no longer p required, restore the system to AUTOMATIC/STANDBY mode if possible.
CAUTION 8 3.$
II a high dryuel1 pressure ECCg initiation signal (grp prig)~~
occurs or exists Mhile depressurizing, prevent injection from those LPCS pumps not required to assure adequate core cooling prior to reaching their maximum injection pressur st When the high drywell pressure ECCS initiation signal clears, restore LPCS
~~~ to AUTOMATIC/STANDBY mode.
( I-8 ) Rev. 3
Hl <~on RCIC Z~m WrAke CAUTION Do not thro tie or RCIC systems below 200 rp minimum turbin sp d limit per tur e vendor manual)].
CAUTION //3 $5 Cooldown rates above 00 F/hr may be required to accomplish this step.
CA ION 014 Do not d ress ize the RPV w [100 psig (HPCI or C C low pressure isolation s oint, whicheve is igher)] unless moto ven pumps sufficient o intain RPV ater leve are running a d avail e for in5ectio jUo HPCl ave QCIC. z~am Wrbinw cu~ze~ n 4k /0 Open SRVs in the following sequence if possible:
fl,2~ I$ 8 dr g 0 I *c7pepg, )%au RSsaccia4ec< kckck ~Lie vcr~
wzz1, ~~,u~~kza.
CAUTION //P6 W1 Bypassing low RPV water level MSIV isolation interlocks may be required to accomplish this step. /Vo ~AIM~
~~@~
Cooldown rates above 0 00 F/hr CAUTION //~ ~ (
may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the environment.
CAUT ON //18 If c ntinu s LPCI eration s requ ed t assure adeq te core cooling, do not vert all RHR ump from LPCI rm e. AJO LPCX /VOICE (1-9) Rev. 3
CAUTION PIN /~P g
~~ in the SLC tank.
CAUTIO 20 Defea ng RSCS interl may be re d to ac p sh is step.
8CZZ n rlock ION 821 Elevate sup ssion chamber ure ma t the R C turbine on h h exhaust ssure.
P)O /ZCIC 7urbA~
Defeating isolation interlocks CAUTION may be t ~(
required to accomplish this step.
CAUT N 023 Do not initia dryw ll sprays sup ession ol wa r level i a ve
[17 ft. . (elevatio of ottom of Ma internal su re on cham r to dr el vacuum brea s ess vacuum ea r opening p ssu e in feet o w r)J. jn~~ ~+~~ +~~ck UTION 824 Bypassi h drywe re ure an low PV wa le sec dar ontain-ment HV olation in r ks may uired t a omplish step.
J~o zilch'c War c V C inMr LecJc 6 A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage.
CAUTION E2tt 8jF (k>
Large reactor power oscillations may be observed while executing this step.
( I-10) Rev. 3
RPV CONTROL GUIDELINE PURPOSE The purpose of this guideline is to:
~ Haintain adequate core cooling,
~ Shut down the reactor, and
~ Cool down the RPV to cold shutdown conditions ( 100 F ( RPV water temperature ( 212 F ) ~
ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
53 RPV water level below + +R. in.
3 (oSO RPV pressure above g&46 psig
'E.K
~ Drywell pressure above~ psig e A condition which requires MSIV isolation
~ A condition which requires reactor scram, and reactor power above 3X or cannot be determined OPERATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate reactor scram.
Irrespective of the entry condition", execute Steps RC/L, RC/P, and RC/Q concurrently.
(RC-1) Rev. 3
RC/L Monitor and control'PV water 1'evel ~
~
e~
RC/L-1 Confirm initiation of any of the following:
~ '.. ~ ." Is'o]ation a ~
~ . ~
re I ~
~o
\ ~
- ~ -ECCS C~d>>~
initiate any of these uhich should have initiated hut did not
~
~ptr~5 ~
~)
If while executing the following step:
~ Boron In)ection is required, enter [procedure developed from CONTINGENCY ~71 '
RPV water level cannot be determined, RPV FLOODING IS REQUIRED; enter [procedure developed from CONTINGENCY t6J-
~ RPV Flooding is required, enter fprocedure developed from CONTINGENCY 46]e RC/L-2 Restore and maintain RPV Mater level
+S in.
and with
~
be t~een one in.
or more of the following systems:
~ Condensate/feedwater system 1110 0 psig
~ CRD system 1110 0 psig or s (RC-2) Rev. 3
ND RPcZ.
eo Hrc~
>&K -
e LPCS system 0 psig Po LPcZ If RPV vater level cannot be restored and maintained above
~~ in.-84 A , maintain RPV vater level above ~$ in.
-8S.4 and the ADS timer has initiated, prevent automatic RPV depressurization by resetting the ADS timer.
-84.4 If RPV vater level cannot be maintained above J-'ikey'n. +top~
enter fprocedure developed from CONTINGENCY dl].
If Alternate Shutdown Cooling is required, enter [procedure developed from CONTINGENCY 05].
A QIQ<<OP $ 3, "SkcuA.~ a-<<d Sk<<ktaum PAo<<eaLuAA"iS <<<<~.,~
Z
~
/J~
~Os 43, S~hrpg a
+<A Wymta~ Paa~m~."
( /AN Ptf 0GZf~c~t7lt coovlAlllRIU'6~
~</4 cuiA exi+
~C// )
(RC-3) Rev. 3
RC/P Monitor and control RPV pressure.
If vhile executing the following steps:
~ Baersency Rpv Depressurdsatdcn ds anticdpated, rapddly n jg depressurize the RPV vith the main turbine bypass valves.
~ Emergency RPV Depressurization or RPV Flooding is required and less than .
9SRVs are open, enter
[procedure developed from CONTINGENCY 02).
~ RPV Flooding is required and at least
-u~~SRVs are open, enter [procedure developed from CONTINGENCY t6}.
FC.
RC/P-1 If any SRV is cycling, initiate~and manually VSO open SRVs until RPV pressure drops to +~isig, (RC-4} Rev. 3
If while executing the following steps:
~ Suppression pool temperature cannot be maintained e below the Heat Capacity Temperature Limit, maintain RPV pressure below the Limit. sz 191 if) ~y+
e 1SS Pbr&- spec, CtAN~
t lleat C00atity Teopeeature i.iei t j
RFf ~~ {Po2S)
~ Suppression pool water level cannot be maintained below the Suppression Pool Load Limit, maintain RPV pressure below the Limit.
20 V
8 0
C SMporesael m Pool O 1. ood l. I+ 1 1
~1 A 12.5 0 F00 1200 kPV Measure (psi9)
~ Steam Cooling is required, enter [procedure developed from CONTINGENCY 83].
(RC-5), Rev. 3
If while executing the following steps:
'%4 ~ '~e =-
0 t
~- Bohoh Infect'ion is required, and
~ The main condenser"is available, and
~ There ha's been no indication of gross fuel failure or steam line break, open MSIVs to re-establish the main condenser as a heat sink.
RC/P-2 with the main turbine bypass valves.
RPV pressure control may be augmented by one or more of the following systems:
SRVs only wh suppression nool wate 1 v
~
is above f. (
relic~
]. If the continuous SRV pneumatic supply is or becomes unavailable, depressuri.ze with sustained SRV opening.
/f0 FfMZ 5/D 4c'TC.
(RC-6) Rev. 3
I
~ RWCU (recirculation mode) if no boron has been in)ected into the RPV.
~ Hain steam line drains
~ RWCU low wn mod f no boron s een in)ect into V. Ref o [samp ocedures rio to ting owdo
)V0 kfouretauor Lineccpa- cnn bc ft74CP4l If while executing the following steps the reactor is not shutdown, return to fStep RC/P-2).
RC/P-3 When either:
~ All control rods are inserted beyond position ~ , or ZM.S
~ +NO- pounds of boron have been in5ected into the RPV, or
~ The reactor is shutdown and no boron has been infected into the RPV, depressurixe the RPV and maintain cooldown rate helen (f100 Plhr,
&66+j.
RC/P-4 Mhen the ~shntdovn coolant interlocks clear (RC-7) Rev. 3'
If the further shutdown cooling ~ SQStenl cannot be established and cooldown is required, continue to cool down using one or more of the systems used for depressurization.
If RPV cooldown is required but cannot be accomplished and Cg
, ALTERNATE SHUTDOWN COOLING IS REQUIRED; enter [procedure developed from CONTINGENCY IS].
RC/P-5 Proceed to cold shutdown in accordance with OR AR.'b f-'~ J~h P RC/Q Monitor and control reactor power.
If while executing the following steps:
~ All control rods are inserted beyond position e terminate boron injection and enter (scram procedure].
~ The reactor is shutdown and no boron has been injected into the RPV, enter I
+0p gg "Zcranr ProccK~ ~
~
RC/Q-1 Confirm or place the reactor mode switch in SHUTDOWN.
RC/Q-2 If the main turbine-generator is on-line confirm or initiate recirculation flow runback to (7S ~an onlyke m-)iree
&4/Vc cFw Oped)
RC/Q-3 If reactor power is above 3X or cannot be determined, trip the recirculation pumps.
(RC-8) Rev. 3
0 1
~
Execute [Steps RC/Q-4 and RC/Q-5) concurrently. ~
~
e 0 rl RC/Q-4 If the reactor'annot be shutdovn-befo e 0
suppression pool temperature reaches'ORON INJECTION IS REQUIRED; inject boron into the RPV vith SLC and prevent automatic initiation of hDS.
If boron cannot be injected vith SLC, inject boron into the L ~ RPV Q S lJ~2 Agcy.ro @urn@.
HPCS WCU Fe water CI RCIC Hydro pump RC/Q-4 ' n is bein n e
@Ag5~confirm automatic isolation of or manually isolate RWCU.
29/. 8'oou~~
RC/Q-4.2 Continue to inject boron until of boron have been injected into the RPV.
RC/Q-4.3 Enter QQ7p-/Q,'c.ram / ~ceMM (RC-9) Rev. 3
RC/Q-5 Insert control rods as follows:
RC/Q-5 1 If any scram valve is not open:.
~ Remove:
FLl$6'k7 8 I'py C~ )g S~
MzE~ 8 in Cob. 16'-~
relay ~
~
valve XA-2o7a~a ~m~ vent pip< cap a%
X&2.M Shen control rods are not moving inward:
~ Replace:
FUSE CAT'8 /n &0 /$'$'3 u~
FCC4C ckrZ i'tv Cub IS-gg
<~ l'e/+~
Rep4c.c. men+ gapa cay cL+ XA-Zo7 (scram gkr 0
heac4uv up~ valve and open z.a o7 RC/Q-5.2 Reset the reactor scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue in this procedure at (Step RC/Q-5 6.1] ~
(RC-10) Rev. 3
I
- 2. Close CU accumulator charging eater header valve >O<-gp, 3, Rapidly insert control rods manually until the reactor scram can be reset.
- 4. Reset the reactor scram..
- 5. Open CU accumulator charging water header valve~ Pgrd.-te9.
RC/Q-5.3 If the scram discharge volume vent and drain valves are open, initiate a manual reactor scram.
- 1. If control rods moved inward, return to
-fStep RC/Q-5 '].
- 2. Reset the reactor scram.
If the reactor scram cannot be reset, continue in this procedure at (Step RC/Q-S.5.1J.
- 3. Open the scram discharge volume vent and drain valves.
RC/Q-5.4 Individually open the scram control rods not inserted beyond position ~
test svitches for g'P, When a control rod is not moving inward, close its scram test switch.
(RC-11) Rev. 3
RC/Q-5.5 Reset the reactor scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue in this procedure at (Step RC/Q-5.6.1].
- 2. Close HCU accumulator charging vater header valve~god.-iog.
RC/Q-5.6 Rapidly insert control rods manually until all control rods are inserted positionPP'eyond If any control rod cannot be inserted beyond positionP
- l. Individually direct the effluent from ~a-Ik (Lctatetc n+ ~ RcR) to a contained radvaate drain and open Hta.
I+.
for each control rod not inserted beyond position
- 2. When a control rod is not moving inward, close its CRD withdraw line vent valve (RC-12) Rev. 3
~O
~(
2OO 420
N X AGARA NOHANK POWER CORPORAT X ON N X NE N X LE PO X NT NUCLEAR STAT X ON UN X T ENERGENCY PROCEDURE GUIDELINES Revision 0 FEBRUARY~ 1984
NMP1 EPGs Introduction TABLE I ABBREVIATIONS ADS Automatic Depressurization System APRM Average Power Range Monitor CRD Control Rod Drive EC Emergency Condenser ECCS Emergency Core Cooling System EVS Emergency. Ventilation System HCU Hydraulic Control Unit HPC I HIgh Pressure Cool ant In j ecti on HVAC Heating, Ventilation and Air Conditioning Limiting Condition for Operation LOCA Loss of Coolant Accident LPCS Low Pressure Core Spray MSIV Main Steamline Isolation Valves NDTT Nil-Dectility Transition Temperature NPSH Net Positive Suction Head RPS Reactor Protection System RPV Reactor Pressure Vessel RWCU Reactor Water Cleanup SLC Standby Liquid Control SORV Stuck Open Relief Valve SRV Safety Relief Valve Revision 0 I-3
NMPl EPGs Operator Precautions OPERATOR PRECAUTIONS GENERAL This section lists "Cautions" which are generally applicable at al l times.
CAUTION ¹1 Monitor the general state of the plant. If an entry condi-tion for a Cprocedure developed from the Emergency Procedure Guidelines3 occurs, enter that procedure. When it is deter-mined that an emergency no longer exists, enter normal operating procedures.
CAUTION ¹2 Monitor RPV water level and pressure and primary containment. t temperatures and pressure from multiple indications. I CAUTION ¹3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications.
CAUTION ¹4 Suppression pool temperature is determined by averaging the indicated values of the bulk suppression pool temperature meters located on "K" panel.
I I I I Drywell temperature is determined by averaging the indicated values of the Drywell Temperature meters located on "L" panel I
Revision 0 I-4
I NMP i EPGs Oper at or Precaut i ons CAUTION ¹5 Whenever drywel 1 temperature at Elevation i~0 f t. (Drywel 1 Temperature meter on "L" panel) 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 bel ow the el evat i on of the lower instrument tap.
I I
1 I
I Tem erature Instrument CLater3 CLater3 CLater 3 CLater3 CLater3 CLater3 CLater3 CLater3 CLater3 CLater3 CLater3 CLater3 CAUTION ¹h Rosemont/Yarway indicated RPV water levels are not reliable during rapid RPV depressurization below 500 psig. For these conditions, utilize Wide Range GEMAC instruments to monitor RPV water level.
Revi si on 0 I-5
NMP1 EPGs Operator Precaut i ons SPECIFIC This section lists "Cautions" which are applicable at one or more specific points within the guidelines. Where a "Caution" is applicable, it is identified with the symbol ¹ CAUTION ¹7 Do not secure or place an ECCS in MANUAL mode unless, by at least two independent indications, (1) misoperation in AUTO-MATIC mode is confirmed, or (2) adequate core cooling is assured. If an ECCS is placed in MANUAL mode, it will not initiate automatically. Make frequent checks of the initi-ating or controlling parameter. When manual operation is no longer required, restore 'the system to AUTOMATIC/STANDBY mode i f possible. I CAUTION ¹8 If a high drywel1 pressure ECCS initiation signal (3.5 psig) s occul 5 or ex i st.s whi I e depressuri z i ng, prevent i n j ecti on from those LPCS pumps not required to assure adequate core cooling prior to reaching their maximum injections pressures.
When the high drywel I pressure ECCS initiation signal clears, restore LPCS to AUTOMATIC/STANDBY mode.
CAUTION ¹9 Cooldown rates above 100 F/hr may be required to accomplish this step.
CAUTION ¹10 Open SRVs in the f ol lowing sequence i f possible: ¹111, ¹112 and ¹113 relief or if any fail to open, their associated valves ¹121, ¹122 and ¹123.
back-up Revision 0
NNP 1 EPGs Oper at or Pr ec aut i on s CAUTION ¹11 I
I Bypassing RPV low water level NSIV isolation interlocks may be required to accomplish this step.
CAUTION ¹12 s Cooldown rites above 100~F/hr may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the environment. I CAUTION ¹13 Confirm automatic trip or manually trip SLC pumps at 0 (zero) gallons in the SLC tank.
CAUTION ¹ 14 I Def eating i sol ation interlocks may be required to accomplish this step.
CAUTION ¹15 I I
l A rapid increase in injection into the RPV may induce a large power evcursion and result in substantial core damage.
CAUTION ¹16 Large reactor power oscillations may be observed while executing this step.
Revision 0 I-7
NMP1 'EPGs RPV Control RPV CONTROL GUIDELINE PURPOSE The purpose of this guideline is to.
o Maintain adequate core cooling, o Shut down the reactor, and o Cool down the RPV to cold shutdown conditions (100 F <RPV water temperature <212~F) .
ENTRY CONDITIONS The entry conditions for this guideline are any of the following.'
RPV water level below +53 in.
o RPV pressure above 1080 psig o Drywell pressure above ~.5 psig 0 A condi ti on whi ch requi res MS I V i sol at i on o A condi tion which requires reactor s'cram, and reactor power above 3/ or cannot be determined OPERATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate reactor scram.
Irrespective of the entry condition, e>:ecute ESteps RC/L, RC/P, and RC/Q3 concurrently.
Revision 0 RC-1
NMP1 EPGs RPV Control RC/L Moni tor and control RPV water level .
RC/L-1 Confirm init,iation of any of the following.
o Isol ati on o ECCS Initiate any oW these which should have initiated but did not ~
If while e):ecuting the following step.
i 0 Boron Injection is required, enter Cprocedure I
I developed %rom CONTINGENCY ¹73.
RPV water level cannot be determined, RPV FLOODING IS REQUIRED~ enter Cprocedure developed from CONTINGENCY I
¹63.
I i o RPV Flooding is required, enter Eprocedure developed from CONTINGENCY ¹63.
RC/L-2 Restore and maintain RPV water level be-tween +53 in. and +95 in. with one or more I ¹7 I of the following systems'. ¹8 o Condensate/feedwater (1110 0 psig) o CRD (1110 0 psig) o LPCS ( .65 0 psig)
If RPV water level cannot be restored and main-tained above +53 in., maintain RPV water level above -86.4 in.
If RPV water level can be maintained above -86.4 in. and the ADS timer has initiated, prevent auto-matic RPV depressuri"ation by resetting the ADS timer.
IW RPV water level cannot be maintained above
-86.4 in. enter Cprocedure developed from CONTINGENCY ¹1 3.
Revision 0 RC-
NNPl EPGs RPV Control If Alternate Shutdown Cooling is required, enter Cprocedure developed from CONTINGENCY 053.
RC/L-3 When OP-43, "Startup and Shutdown Procedure" is entered from CStep RC/P-53, proceed to cold shut-down in accordance with OP-4 ~ "Startup and Shutdown Procedure.
Revision 0
I NMPl EPGs RPV Control RC/P Monitor and control RPV pressure.
If while executing the following steps.
s o Emergency RPV Depressurization is anticipated and Baron Injection is not required, rapidly depressurize the RPV with the main turbine bypass valves.
I o Emergency RPV Depressuri "ation or RPV Flooding is required and less than 3 SRVs are open, enter Lprocedure developed from CONTINGENCY 023.
RPV Flooding is required and at least 3 SRVs are open, enter Lprocedure developed from CONTINGENCY 063 ~
RC/P-I If any SRV is cycling, initiate EC and manually open SRVs until reactor pressure drops to 950 psig.
Revision 0
NMP1 EPGs RPV Control IW while executing the following steps'.
Suppression pool temperature cannot be maintained ¹7 below the Heat Capacity Temperature Limit. main- ¹9 tain RPV pressure below the Limit.
205
+ Heat. CaP+<+ +Y mf 4 Tmmpar aCur a Lf 1000 RPV Pressure"(psig)
Suppression pool water'evel cannot be maintained s ¹9 below the Suppression Pool Load Limit, maintain RPV pressure below the Limit.
0 h.
0 0 Q
C 8
~
0 W
CLater3 Ul A 8
8 c 8 O. CL O. E Gl N I-o Steam Cooling is required, enter Cprocedure developed pro CONTINGENCY ¹~3.
Revision 0 RC-5
NMPi EPGs RPV Control If while e>:ecuting the f ol lowing steps.
o Boron Injection is required. and s 0 The main condenser is available, and s o There has been no indication of gross fuel fai lure or steam line break, open MSIVs to re-establi shed the main condenser s ¹11 s as a heat. sink.
RC/P-2 Control RPV pressure below 1090 psig with the main turbine bypass valves.
RPV pressure control may be augmented by one or more of the f ol lowing systems.
o EC o SRVs, only when suppressi on pool water 1 evel i s above 6 f t. 0 in. (ref erenced s ¹10 3 to the bottom of the torus.: channels 11 and 12 of Torus Nater Level meters on "K" panel) o Main steam line drains o RNCU (recirculation mode) if no boron has been injected into the RPV.
Revision 0
NNP1 EPBs RPV Control If while e.:ecuting the following steps the reactor is not.
shutdown, return to CStep RC/P-23.
RC/P-3 When either.
o All control rods are inserted beyond position 00, or o 291.5 pounds of boron have been injected into the RPV, or o The reactor is shutdown and no boron has been injected into the RPV, II Depressuri "e the RPV and maintain cooldown r ate bel ow 100~F/hr s ¹12 RC/P-4 When the shutdown cooling interlocks clear, i ni t i ate the shutdown cool i ng system.
If the shutdown cooling system cannot be estab-lished and further cooldown is required. continue to cool down using one or more of the systems used for depressurization.
If RPV cooldown is required but cannot be accom-plished and al) control rods are inserted beyond position 00, ALTERNATE SHUTDOWN COOLING IS RE-QUIRED.. enter Eprocedure developed from CONTIN-GENCY ¹53.
RC/P-5 Proceed to cold shutdown in accordance with OP-43, "Startup and Shutdown Procedure."
Revision 0
NMP1 EPGs RPV Control RC/9 Monitor and control reactor power..
If while e):ecuting the following steps.
I All control rods are inserted beyond position 00, I
I terminate boron injection and enter SOP-16 "Scram I
I I
Procedure."
1 s o The reactor is shutdown and no boron has been injec-ted into the RPV, enter SOP-16, "Scram Procedure. "
RC/Q-l Confirm or place the reactor mode switch in SHUTDOWN.
RC/9-2 If the main turbine-generator is on-line, confirm or initiate recirculation flow runback to minimum.
RC/9-3 If reactor power is above 3/ or cannot be deter-mined, trip the recirculation pumps.
E>:ecute CSteps RC/9-4 and RC/9-53 concurrently.
RC/9-4 If the reactor cannot be shutdown before suppression pool temperature reaches 110 ~F, BORON INJECTION IS REQUIRED.: inject. boron I 01~ s into the RPV with SLC and prevent automatic initiation of ADS.
If boron cannot be injected with SLC, inject boron into the RPV using a hydro pump.
RC/9-4. 1 Conf irm automatic i sol at i on of or manual l y i sol ate RPJCU.
RC/9-4.2 Continue to inject boron until 291. 5 pounds of boron has been injected into the RPV.
RC/9-4.~ Enter SOP-16, "Scram Procedure."
Revision 0
NMP1 EPGs RPV Control RC/9-5 Insert control rods as follows:
RC/9-5. 1 If any scram valve is not open.'
Remove.
Fuse CKT 8 in cabinet 15-5i and Fuse CKT 8 in cabinet 15-55 in relay I oom o Close IA-207 <scram air header supply valve) and remove vent pipe cap at IA-207.
When control rods are not moving inward:
o Replace.
Fuse CKT 8 in cabinet 15-53 and Fuse CKT 8 in cabinet, 15-55 in relay room o Replace the vent cap at IA-207 <scram air header supply valve) and open IA-207.
RC/9-5.2 Reset the reactor scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, con-tinue in this procedure at LStep RC/9-5.6.13.
Close HCU accumulator charging water header val ve 301-6'P.
Rapidly insert control rods manually until the reactor scram can be reset.
- 4. Reset the reactor scram.
5e Open HCU accumulator charging water>
header val ve ~01-69.
Revision 0
NMPi EPGs RPV Control RC/9-5.3 If the scram discharge volume vent and drain valves are open, initiate a manual reactor scram.
- 1. If control rods moved inward, return to CStep RC/9-5.23.
- 2. Reset the reactor scram.
If the reactor scram cannot be reset, continue in this procedure at LStep RC/9-5.5.13.
Open the scram discharge volume vent and drain valves.
RC/9-5.4 Individually open the scram test switches for control rods not inserted beyond position 00.
When a control rod is not moving inward, close its scram test switch.
RC/9-5.5 Reset the reactor scram.
If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, con-tinue in this procedure at CStep RC/9-5.6 '3.
- 2. Close HCU accumulator charging water header val ve ~01-69.
Revision 0 RC-10
NNPl EPGs RPV Control RC/9-5.6 Rapidly invert control rods manually until all control rods are inserted beyond posit,ion 00.
If any control rod cannot be inserted beyond position 00:
Indi vidual 1 y direct the ef f luent f rom the CRD withdraw line vent valve (located at the HCU) to a contained radwaste drain and open the CRD with-draw line vent. valve for each control rod not inserted beyond position 00.
When a control rod is not moving inward close its CRD withdraw line vent valve.
Revision 0
NMP1 EPGs Primary Containment Control PRIMARY CONTAINMENT CONTROL GUIDELINE PURPOSE The purpose of this guideline is to.
o Maintain primary containment. integri tyand o Protect equipment in the primary containment.
ENTRY CONDITIONS The entry conditions for this guideline are any of the following.'
Suppression pool temperature above 80~F o Drywell temperature above 125~F o Drywell pressure above ~.5 psig o Suppression pool water level above 4 ft. 6 in.
o Suppression pool water level below ~ ft. 0 in.
OPERATOR ACTIONS Irrespective of the entry condition, evecute CSteps SP/T, DN/T CN/T, PC/P, and SP/L3 concurrently.
Revision 0 PC-1
NMP1 EPGs Primary Containment Control SP/T Monitor and control suppression pool temperature.
SP/T-1 Close all SORVs.
SP/T-2 Nhen suppression pool temperature e>:ceeds 80pF operate available suppression pool cooling.
SP/T-c Be%ore suppression pool temperature reaches 110pF scram the reactor.
SP/T-4 'W suppression pool temperature cannot be main-tained below the Heat Capacity Temperature Limit, maintain RPV pressure below the Limit.'nter Cprocedure developed +rom the RPV Control Guide-lines at LStep RC-13 and e>:ecute with this procedure.
it concurrently 0 Ir.
8////
0 0 Q
C 8 0 L IP4 lA 5
Gl N
tg Gl 1 56+
Heat Cap ac i t y Temper ature I 1 mi t lg Q CL l-I cL s N
120 1000 RPV Pressure (psig)
IW suppression pool temperature and RPV pressure cannot be restored and maintained below the Heat Capacity Temperature Limit EMERGENCy RPV DEPRES-SUR I 7ATION IS REQUIRED.
"Revision 0
N!1P1 EPGs Primary Containment Control DW/T Monitor and control drywell temperature.
DW/T-1 When drywell temperature e>:ceeds 135~F, operate available drywell cooling.
E>:ecute CSteps DW/T-2 and DW/T-33 concurrently.
DW/T-2 IW drywell temperature at Elev. 3i0 +t. (Drywell Temperature meter located on "L" panel) reaches the RPV Saturation Temperature, RPV FLOODINS IS RE-QUIRED.: enter Cprocedure developed from the RPV Control Buideline3 at CStep RC-13 and e>:ecute it concurrently with this procedure.
550+
8 4 L 0 4 W L. v 8
ao C Yr 8 Y)
I-RPV Saturation 8 w Q Temperature Z Ul L W A 4 21>
0 1000 RPV Pressure (psig)
Revision 0 PC-a
NNP1 EPGs Primary Containment Control DN/T- i Before drywell temperature reaches '01~F, but only i5 suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit, shut down recirculation pumps and drywell cooling f.ans and initiate drywell sprays.
CLater 3 If drywel l temperature cannot be maintained below
>01~F, EMERGENCY RPV DEPRESSURIZATION IS Cprocedure developed from the RPV Control REQUIRED'nter Guideline3 at CStep RC-13 and e);ecute rentl y wi th thi s procedure.
it concur-Revision 0 PC-4
NNP1 EPGs Primary Containment Control PC/P Nonitor and control primary containment pressure-PC/P-1 Operate EVS, only when the temperature in the space being evacuated is below 2l2~F. Use Ni-OP-9, "Dry-well and Torus Inerting and Venting Procedure,"
Sections G and H.
PC/P-2 If suppression chamber pressure e>:ceeds CLater3 but only if suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit, shut down recircu-lation pumps and drywell cooling fans and initiate drywell sprays.
CLater3 Revi sion 0 PC-5
N. IP 1 EPGs Pr i mar y Containment Contr o l PC/P-~ If suppression chamber pressure cannot be mai.n-tained below the Pressure Suppression Pressure.
EMERGENCY RPV DEPRESSUR I ZATION IS REQUIRED.
CLater 3 PC/P-4 If suppression chamber pressure cannot be main-tained below the Primary Containment Design Pl" essure, RPV FLOODING IS REQUIRED.
8
&5+ //// r E CP /
L 0
Ul o.
////
c 0 8
//
~ w Ul 3i. 4+
Ul Gl Ul Ul ><<++I Y Conte'ment I
CL l Dews gn Prrssure
- o. Q.
3 tA
- 14. 5 Pri. mary Containment Mat er Level ( ft )
Revision 0 PC-6
NMP1 EPGs Primary Containment Control PC/P-5 IW suppression chamber pressure cannot be main-tained below the Primary Containment, Pressure Limit, then irrespective o$ whether adequate core cooling is assured:
L I I
GJ Jj ~ I I
6 Cn I I
I lA I U a 4O+'
c
~
0 rt I 1 1
I I
lA I Ul lA I Ql Ul L 8 38. 4+
I CL L I an. I
',Pr a mary Cantai nment M
I I
I I reasur e Lf mf t I
I I I
I
- 14. 75 Primary Containment Water Level (5 t) o If suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit, shutdown recirculation pumps and drywell cooling fans and initiate drywell sprays.
L Later 3 Revision 0 PC-7
NNPi EPGs Primal y Containment Control PC/P-6 If suppression chamber pressure e>:ceeds the Primary Containment Pressure Limit, vent the primary containment in accordance with l 814 i N1-0P-P, "Drywell and Torus Inerting and Venting Procedure," Sections G and K, to reduce and maintain pressure below the Primary Containment Pressure Limit.
L lll C CP 40+
SU C Ul D cL c
0 8 >8. 4+
~ rt Ul I
Ul Ul Ul P"r S. mary ContaS. nmrnt L.
CL Q
lU L
Q.
S reaaurr LS. mi t Ul
- 14. 75 Prinary Containment Water Level (ft>
Revision 0 PC-8
~ NKP 1 EPGs Pr i mary l 'ont a i nment Control SP/L Nonitor and control suppression pool water level.
BP/L-1 Naintain suppression pool water level between 4 ft.
6 in. and 3 f t. 0 in. Refer to Nl-PBP-1~, "Post LOCA Sampling Procedure," prior to discharging water ~
If suppression pool water level cannot be main-tained above i f t. 0 in. e>:ecute CBtep SP/L-23.
If suppression pool water level cannot be main-tained below 4 f t. 6 in. e>;ecute CStep BP/L-33.
Revision 0
I NNP1 EPGs I
Primary Containment Control SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW a ft. 0 in.
Naintain suppression pool water level above the Heat Capacity Level Limits 12+
I I
11+
I I
10+
C 0
w Mal% Capacity I evil l hei 5
~ w 8
)
Cl OJ lA U Gl CL Ql aw4 U) Z
+ + + + + +
5 10 15 20 25 30 M5 40 iI
~c" <~F) f Where 4T+< = Heat Capacity Temperature Limit suppression pool temperature. 'inus lf suppression pool water level cannot be main-tained above the Heat Capacity Level Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED, enter Cprocedure devel oped %rom the RPV Control Gui de-line3 at wi th CStep RC-13 thi s procedure.
and e>:ecute it concurrently Revision 0 PC-10
I NNP1 EPGs Primary Containment Control I
SP/L-3 SUPPRESSION POOL MATER LEVEL ABOVE 4 ft. 6 in.
E>;ecute CSteps SP/L-3. 1 and SP/L-3.23 concurrently.
SP/L-~. 1 Na'intain suppression pool water level below the Suppression Pool Load Limit.
CLater 3 If suppression pool water level cannot be maintained below the I Suppression Pool Load Limit, maintain RPV pressure below the Limit.:
enter Cprocedure developed from the RPV Control Guideline3 at [Step RC-13 and e>:ecute pl ocedul e ~
it concurrently with this Revision 0
0 NMP1 EPGs Primary Containment Control If suppression pool water level and RPV pressure cannot be maintained below the Suppression Pool Load Limit but only if adequate core cooling is assured. termi-nate injection into the RPV from sources e>:ternal to the primary containment e>:cept from boron injection systems and CRD.
If suppression pool water level and RPV pressure cannot be restored and main-tained below the Suppression Pool Load Limit, EMERGENCy RPV DEPRESSURIZATIQN IS REQUIRED.
SP/L-Z.2 Before suppression pool water level reaches 100. 5 f t., but onl y i f adequate core cooling is assure. terminate injection into the RPV from sources e>:ternal to the primary containment e>:cept from boron injection systems and CRD.
SP/L- ~.3 Nhen primary containment water level reaches 100.5 ft., terminate injection into the RPV from sources e>;ternal to the primary containment irrespective of whether adequate core cooling is assured.
Revision 0 PC-12
NPP1 EPGs Secondary Containment Control SECONDARY CONTAINMENT CONTROL GUIDELINE PURPOSE The purpose of this guideline is to.
o Protect equipment in the secondary containment, o Limit radioactivity release to the secondary containment, and either:
o Maintain secondary containment integrity, or o Limit radioactivity release from the secondary containment.
ENTRY CONDITIONS The entry conditions for this guideline are any of the following secondary containment conditions.
o Differential pressure at or above 0.0 in. of water o An area temperature above the high temperature alarm setpoint o Reactor Building HVAC e>:haust radiation level above 5 mr/hr o An area radiation level above the high radiation level alarm setpoint o A floor drain sump water level above the high water level alarm setpoint Revision 0
NMP1 EPGs Secondary Containment Control If while executing the following steps Reactor Building HVAC I
exhaust radiation level exceeds 5 mr/hr.
I o Confirm or manual ly initiate isolation of Reactor Building I
I HVAC, and 1 I
I I
o Confirm initiation of or manually initiate EVS.
I If whi le executing the f ol lowing steps.
I I
o Reactor Building HVAC isolates and I
o Reactor Building HVAC exhaust radiation level is below 5 mr/hrs I
1 restart Reactor Building HVAC.
Irrespective of the entry condition, execute CSteps SC/T, SC/R, and SC/L3 concurrently.
SC/T Monitor and control secondary containment temperatures.
SC/T-1 Operate available area coolers.
SC/T-2 If reactor building HVAC exhaust radiation level is belo~ 5 mr/hr, operate available reactor building HVAC.
SC/T-3 If any area temperature exceeds its high tempera-ture alarm setpoint, isolate all systems'hat are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire.
SC/T-4 If a primary system is discharging into an area and any area temperature exceeds its high tempera-ture alarm setpoint, enter Cprocedure developed from the RPV Control Guidelines at, CStep RC-13 and execute it concurrently with this procedure.
SC/T-5 If a primary system is discharging into an area and the high temperature alarm setpoint is exceeded in more than one area ENERGENCY RPV DEPRESSURIZATI~
IS REQUIRED.
Revision O SC-2
NNP1 EPGs Secondary Containmerit Control SC/R Monitor and control secondary containment radiation levels.
SC/R-i If any area radiation level exceeds its high radia-tion level alarm setpoint, isolate all systems that are discharging into the area e>:cept systems re-quired to shut down the reactor assure adequate core cooling, or suppress a working fire.
SC/R-2 If a primary system is discharging into an area and any area radiation level e>:ceeds its high radiation level alarm setpoint, enter Cprocedure developed from the RPV Control Guideline3 at. CStep RC-13 and e>:ecute it concurrently with this procedure.
If a primary system is discharging into an area and the high radiation level alarm setpoint is e>:ceeded in more than one area, EMERGENCY RPV DEPRESSURIZA-TION IS REQUIRED.
Revi si on 0
NMPi EPGs Secondary Containment Control SC/L Monitor and control secondary containment water levels.
SC/L-1 If any floor drain sump exceeds its high water level alarm setpoint, operate available sump pumps to restore and maintain it bel ow i ts high water level alarm setpoint-I f any floor drain sump cannot be restored and maintained below its high water level alarm set-point, isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire.
SC/L-2 If a primary system is discharging into an area, and any floor drain sump cannot be restored and maintained below its high water level alarm set-point, enter Cprocedure developed from the RPV Control Guideline3 at CStep RC-13 and evecute it concurrently with this procedure.
SC/L-3 If a primary system is discharging into an area and more then one f 1 oar drain sump water level e>:ceeds it high water level alarm setpoint, EMERGENCy RPV DEPRESSURI ZAT ION IS REQUIRED.
Revision 0 SC-4
NMP1 EPGs Secondary Containment Control TABLE I OPERATINB VALUES OF SECONDARY CONTAINMENT PARAMETERS Secondary Containment Alarm Parameter/Location Setpoint o Floor Drain Sum Wtr Lvls 11-Sump Pump (N.W.Corner) +3 ina 12-Sump Pump (S.W.Corner) +3 in.
13-Sump Pump (N.E.Corner) +3 in.
14-Sump Pump (S.E.Corner) +3 in.
15-Sump Pump (N.W.Corner) l+1 f t. 6in.
16-Sump Pump (N. E. Corner ) i+1 f t. 6in.
o H. V.A.C. Exhaust Radiation mr /hr Reactor Building o Reactor Buildin Area /hr Radiation Monitars Fresh Fuel Storage Vault 10 T~ I. P. Room 300 Fuel Pool Bridge Hi Range 1000 Fuel Pool Bridge Lo Range 50 Reactor Operating Floor El. 340'atch Area 5 Equipment Drain Tank Area 20 R. B. C. L. C. Area 20 Reactor Water C.U. Pump Areal 20 El. 281'ear Fuel Pool Control Area 237'r Fi 1 ters Rod Drive Module Spent Fuel Pool Area (East End)
Containment Spray Heat E):changer Area North Instrument Room 15 5
El.
Revision SC-5
NMP1 EPGs Secondary Containment Control TABLE I (Continued)
OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS Secondary Containment Al arm i Parameter/Location Setpoint o Area Tem eratures I oF I
I I I I I I
I CLater3 CLater3 Revision 0 SC-6
I NMP1 EPGs Radioactivity Release RADIOACTIVITY RELEASE CONTROL GUIDELINE PURPOSE The purpose of this guideline is to limit radioactivity release into areas outside the primary and secondary containments.
ENTRY CONDITIONS The entry condition for this guideline is.
o Offsite radioactivity release rate above the off-site release rate which requires an Alert.
OPERATOR ACTIONS RR-1 Isolate all primary systems that are discharging into areas outside the primary and secondary containments except systems required to assure adequate core cooling or shut down the reactor.
RR-2 If offsite radioactivity release rate approaches or e>:ceeds the off-site release rate which requires a General Emer-gency and a prim'ary system is discharging into an area outside the primary and secondary containments, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED:. enter Cprocedure de-veloped from the RPV Control Guideline3 at. CStep RC-13 and e>:ecute it concurrently with this procedure.
Revision 0 RR-1
NNPi EPGs Contingency 01 CONTINGENCY ¹1 LEVEL RESTORATION I
If while executing the following steps.
I i o Boron Injection is required, enter Cprocedure developed I
I I
f rom CONTINGENCY 073.
I o RPV water level cannot be determined, RPV FLOODING IS I I
I I
REQUIRED~ enter Cprocedure developed f rom CONTINGENCY 063.
I i o RPV Flooding is required, enter Cprocedure developed from I
I CONTINGENCY ¹63.
Ci-1 Initiate EC.
Ci-2 Line up f or injection and start pumps in 2 or more of the following injection subsystems.
o Condensate and feedwater o LPCS LOOP ¹li o LPCS LOOP 012 If less than 2 of the injection subsystems can be lined up, commence lining up for injection into the RPV as many of the following alternate injection subsystems as possible.
o Containment Spray Raw Water valved to Core Spray (Use Ni-OP-2 "Core Spray System Procedure," Section G.)
o Fire system (Use Ni-OP-16, "Feedwater System Procedure,"
Section g.)
Revision 0 Ci-1
NMP1 EPGs Contingency ¹1 Ci- Monitor RPV pressure and water level. Continue in this procedure at the step indicated in the following table.
RPV PRESSURE REGION 365 psig HIGH LOW RPV l INCREASING C1-4 C1-5 I
WATER LEVEL t DECREASING s Ci-6 C1-7 I f while e>:ecuting the f ol lowing steps.'
I O The RPV water level trend reverses or RPV pressure changes I
I I
region return to CStep C1-33.
I s o RPV water level drops below -10 in., prevent automatic I
I initiation of ADS.
C1-4 RPV WATER LEVEL INCREASING, RPV PRESSURE HIGH Enter Cprocedure developed from the RPV Control Guideline3 at Step RC/L3.
C Ci-5 RPV WATER LEVEL INCREASING, RPV PRESSURE LOW If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED ~ When RPV pressure is decreasing, enter Cprocedure developed from the RPV Control Guideline3 at CStep RC/L3.
Otherwise, enter Cprocedure developed from the RPV Control Guideline3 at CStep RC/L3.
QW'evision 0 Ci-2
NMP1 EPGs Contingency ¹1 C1-6 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE If no injection system is lined up for injection with at least one pump runningstart pumps in alternate injection subsystems which are lined up for injection.
When RPV water level drops to -86 4 in.
~
o If no system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, STEAM COOLING IS REQUIRED. When any system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, return to CStep Ci-33.
o OtherwiseEMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
When RPV water level is increasing return to CStep C1-33.
Ci-7 RPV WATER LEVEL DECREASING~ RPV PRESSURE LOW If no LPCS subsystem is operating, start pumps in alternate injection subsystems which are lined up for injection.
If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
When RPV water l evel drops to -86. 4 in., enter Epro-cedure developed from CONTINGENCY ¹43. I Revision 0
'I Contingency ¹2 CONTINGENCY ¹2 EMERGENCY RPV DEPRESSUR I ZATION C2-1 When either.
¹9 o Boron Injection is requied and all injection into the RPV e):cept from boron injection systems and CRD has been terminated and prevented, or o Boron Injection is not required, C2-1. 1 In i ti ate EC.
C2-1. 2 If suppression pool water level is above 6 ft. 0 in.
(referenced to the bottom of the torus~ channels 11 and 12 of Torus Water Level meters on "K" panel) o Open all ADS valves.
o If any ADS valve cannot be opened. open other SRVs until 3 valves are open.
C2-1.3 If less than 2 SRVs are open and RPV pressure is at least 50 psig above sup- ¹14 i pression chamber pressure, rapidly depres-surize the RPV using one or more of the following systems (use in order which will minimi"e radioactive release to the environment.):
o Main condenser o Main steam line drains o Head vent o EC tube side vent If RPV Flooding is required enter Cprocedure developed f rom CONTINGENCY ¹63.
C2-2 Enter Cprocedure developed from the RPV Control Guideline) at CStep RC/P-43.
Revision 0 C2-1
0 NMP1 EPGs Contingency ¹ CONTINGENCY ¹3 STEAM COOLING C3-1 Confirm initiation of EC.
If while executing the f ol lowing steps Emergency RPV l, Depressuri-ation is required or any system, injection subsystem, or alternate injection subsystem is lined up for injection with at least one pump running, enter Lprocedure developed from CONTINGENCY ¹23. 1 If EC cannot be initiated:
When RPV water level drops to -174 in or ~ 1 f RPV water level cannot be determined, open one SRV.
When RPV pressure drops below 700 psig, enter Lpro-cedure developed from CONTINGENCY ¹23.
Revision A DRAFT
0 NNP1 EPGs Contingency 44 1'
CONTINGENCY 04 CORE COOLING WITHOUT LEVEL RESTORATION C4-1 Open a l I ADS va l ves.
If any ADB valve cannot be opened, open other SRVs until ~ valves are open.
C4-2 Operate LPCS subsystems wi th sucti on f rom the suppressi on pool .
When at least one core spray subsystem is operating with suction from the suppression pool and RPV pressure is below 110 psig, terminate injection into the RPV from sources external to the primary containtment.
When RPV water level is restored to -86.4 in., enter Cprocedure developed from the RPV Control Guideline3 at CStep RC/L3.
Revision 0 C4-1
CONTINGENCY ¹5 ALTERNATE SHUTDONN COOLING C5-1 Ini ti ate suppressi on pool cool ing.
C5-2 Close the RPV head vents, MSIVs, EC steam line isolation valves, and main steam line drain valves.
C5-3 Place the control switch for CLater3 SRVCs3 in the OPEN position.
C5-4 Slowly raise the RPV water level to establish a flow path through the open SRV back to the suppression pool.
C5-5 Start one LPCS pump with suction from the suppression poo).
C5-6 Slowly increase LPCS injection into the RPV to the maximum.
C5-6.1 If RPV pressure does not stabilize at least CLater3 psig above suppression chamber pressure, start another LPCS pump.
C5-6.2 If RPV pressure does not stabilize below CLaterl psig, open another SRV.
C5-6. 3 If the cooldown rate exceeds 100 F/hr, reduce LPCS injection into the RPV until the cooldown rate decreases below 100 F/hr or RPV pressure decreases to within 50 psig of suppression chamber pressure, whichever occurs f irst.
C5-7 Control suppressi'on pool temperature to maintain RPV water temperature above 125~F.
C5-8 Proceed to cold shutdown in accordance with OP-43, "Startup and Shutdown Procedure."
Revision 0
NNPl EPGs Contingency
.1
¹6 CONT INGENCY ¹6 RPV FLOODING C6-1 If at least 2 SRVs can be opened water pumps are or available for injection, if motor driven feed-close the NSIVs, main steam line drain valves, and emergency condenser steam line isolation valves.
C6-2 If any control rod is not inserted beyond position 00:
C6-2. 1 Terminate and prevent all injection into the RPV e>:cept from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure.
Minimum Alternate RPV Number of open SRVs l Flooding Pressue (psig>
325 950 I f no SRV can be opened, continue in thi s pro-cedure.
If while e>:ecuting the following step. RPV water level can be determined and RPV Flooding is not required, enter Cprocedure developed from CONTINGENCY ¹73 and Cprocedure developed from the RPV Control Guideline3 at CStep RC/P-43 and e>,'ecute these procedures concurrently.
c~~
~)i Revision O C6-1
\
NMP1 EPGs Contingency C6-2. 2 Commence and slowly incr ease injection into the RPV with the following systems until at least 1 SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure.
o Motor driven feedwater pumps o Condensate booster pumps o Condensate pumps o CRD If at least 1 SRV is not open or RPV pressure cannot be increased to above the Minimum Alternate RPV Flooding Pressure, commence and slowly increase injection into the RPV with the following systems until at least 1 SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure.
o LPCS o Containment Spray Raw Water valved to Core Spray (Use Ni-QP-2, "Core Spray System Procedure,"
Section G.)
o Fire System (Use N1-QP-16, "Feedwater System Procedure," Section G.)
C6-2.~ Maintain at least 1 SRV open and RPV pressure above the Minimum Alternate RPV Flooding Pressure by throttling injection.
Revision Q
I NNPi EPGs Contingency 06 I
C6-2.4 Mhen.
o All control rods are inserted beyond position OO, or o The reactor is shutdown and no boron has been injected into the RPV, continue in this procedure.
C6-~ If RPV water level cannot be determined:
C6-2.1 Commence and increase injection into the RPV with the following systems until at least 2 SRVs are open and RPV pressure is not decreasing and is at.
least CLater3 psig above suppression chamber pressure.
o Motor driven feedwater pumps o LPCS o Condensate booster pumps o Condensate pumps o CRD o Containment Spray Raw Mater valved to Core Spray (Use Ni-QP-2 "Core Spray System Procedure,"
Section G.)
o Fire System (Use Ni-OP-i6, "Feedwater System Procedure," Section G.)
C6-3.2 Maintain at least 2 SRVs open and RPV pressure at least CLater3 psig above suppression chamber pressure by throttling injection.
Revision 0
I NMPl EPGs Contingency 56 C6-4 If RPV water level cannot be determined. commence and increase injection into the RPV with the following systems until RPV water level is increasing.
o Motor driven feedwater pumps o LPCS o Condensate booster pumps o Condensate pumps o CRD o Containment Spray Raw Water valved to Core Spray (Use Nl-OP-2, "Core Spray System Procedure," Section G.)
o Fire System (Use NI-OP-16, "Feedwater System Procedure," Section G.)
C6-55 If RPV water level cannot be determined:
C6-5.
5 Continue in'ectin g water into he RPV until drywell 1 J temperatur e at El ev. '0 f t. (Drywel 1 Temperature meter on "L" panel) is below 212 F,and RPV water 1 evel instrumentation i s avai 1 able.'
i I I I
If while e>:ecuting the following'teps, RWV water level can be determined, continue in this procedure at CStep C6-63.
C6-5 i If it can be determined that the RPV is filled or
~
if RPV pressure is at least CLater3 psig above suppression chamber pressure, terminate all injec-tion into the RPV and reduce RPV water level.
Revision 0
"(
NMP1 EPGs Contingency N6 I I C6-5. 4 If RPV water level indication is not restored within the Maximum Core Uncovery Time Limit af ter commencing termination of injection into the RPV return to CStep C6- i3.
40+,
)Q ~c Qj r
U c C Sw Q C U ~0+
I C I Ql I C I
'Pl 'pl x I-ig 10+
0+
1 min 10 min 1 hr 10 hr 100 hr Time After Reactor Shutdown Revision 0 CH)-5
NNP1 EPGs Contingency O6 When suppression chamber pressure can be maintained below the Primary Containment Design Pressure, enter Cprocedure developed %rom the RPV Control Guideline] at CSteps RC/L and RC/P-43 and execute these steps concurrently.
'I I I I
I I
E CP f5 E Ul I U Q I c
0 Gl Ul Ul 8 Ul Ul
~v. 4+
8 P'rimary Contaf nment Q l
- o. iL Desi gn I ressure R
- 14. 5 Primary Containment Water Level ($ t)
Revision (3 C6-*
0 NNPi EPGs Contingency ¹7 CONTINGENCY ¹7 LEVEL/POWER CONTROL If while executing the following steps:
0 RPV water level cannot be determined, RPV FLOODING IS REQUIRED.. enter Cprocedure developed from CONTINGENCY
¹63.
o RPV Flooding i s required, enter Cprocedure devel oped f rom I
I CONTINGENCY ¹63 ~
C7-1 I f:
o Reactor power is above 3% or cannot be determined, and o Suppression pool temperature is above 110 F and o Either an SRV is open or opens or drywel) pressure is either'16 above 3.5 psig, lower RPV water level by terminating and preventing all injection into the RPV e>;cept from boron injection systems and CRD until o Reactor power drops below 3/ or o RPV water l evel reaches -86. 4 in., or o Al l SRVs remain closed and drywel l pressure remains below 3.5 psig Revision 0 C7-1
0 NNP1 EPGs Contingency ¹7 I'f while executing the f ol lowing steps Emergency RPV Depres-I sur i z at i on i s required, continue in thi s procedure at s CStep C7-2. 1 l. I If while executing the following step.
o Reactor power is above 3/ or cannot be determined and o RPV water level is above -86.4 in. and o Suppression pool temperature is above 110 F, and I
o Either an SRV is open or opens or drywell pressure is 9
above '.5 psig, I
return to Step C7-13.
C C7-2 Naintain RPV water level ei ther. ¹7, ¹8, ¹15 s o If RPV water level was deliberately lowered in CStep C7-13, at the level to which it was lowered, or o If RPV water level was not deliberately lowered in CStep C7-13. between +53 in'nd +95 in.,
with the following systems.
o Condensate/feedwater (1110 0 psig) o CRD (1110 0 psig)
If RPV water level cannot be so maintained, maintain RPV water level above -86.4 in.
If RPV water level cannot be maintained above -86.4 in.
ENERGENCY RPV DEPRESSUR I ZAT I ON IS REQUIRED:
Revi si on 0
NNP1 EPGs Contingency ¹7 C7-2.1 'Terminate and prevent al l injection into the RPV e>:cept from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure.
Minimum Alternate RPV Number of open SRVs l Flooding Pressure (psig)1 465 If no SRV can be opened continue in this procedure.
C7-2. 2 Commence and slowly increase injection into the RPV wi th the f ol l owing systems to ¹15 restore and maintain RPV water level above
-86.4 in' o Condensate/f eedwater o CRD If RPV water level cannot be resored and maintained above -86 ' in., commence and slowly increase in-jection into the RPV with the following systems to restore and maintain RPV water level above -86 '
in o LPCS o Containment Spray Raw Water valved to Core Spray (Use Nl-OP-2 "Core Spray System Procedure,"
Section G.)
o Fire System (Use N}-OP-16, "Feedwater System Procedure," Section G.)
Revision O C7-7
NMP1 EPGs Contingency ¹7 If while e>:ecuting the following step reactor power commences and continues to increase, return to CStep C7-13. 1 C7-a When 16> pounds of boron have been injected or all control rods are inserted beyond position 00, restore and maintain RPV water level between +53 in. and +95 in.
If RPV water level cannot be restored and maintained above
+52 in., maintain RPV water level above -86.4 in.
If RPV water level cannot be maintained above -86.4 in.
ENERGENCY RPV DEPRESSURIZATION IS REQUIRED.: return to CStep C7-2. 13.
If Alternate Shutdown Cooling is required, enter Cprocedure developed f rom CONTINGENCY ¹53.
C7-4 When OP-4~, "Startup and Shutdown Procedure," is entered from CStep RC/P-53, 5 proceed to cold shutdown in accordance wi th OP-4~, "Startup and Shutdown Procedure. "
f~
4(
(gP Revision 0
ATTACHMENT 2 Writer's Guide
NINE NIl E POINT 1 EMERGENCY OPERAT I NG PROCEDURE WRITER S GUIDE DOCUMENT NQ. 8309-1 REVISION 0 February, 1984 PREPARED FQR NIAGARA NQHANK PONER CORPORATION BY OPERATIONS ENGINEERING, INC.
39273 Liberty Street, Suite N Fremont, California 94538
document No. 8309-1, NNP-1 EOP Writer's Guide TABLE OF CONTENTS INTRODUCT 1 ON 1 e 1 Purpose ~ ~ s ~ ~ ~ ~ ~ ~ s ~ ~
.2 Scope
- 2. 0 PROCEDURE IDENTIFICATION Tl tie Paqe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
Procedure Numbering
- 2. 2 Procedure Ti tl e 2 4 ~ Revision Identif ication
- 3. 0
~ F'ROCEDURE FORt'1AT
~ ~
~ ~ ~ ~
- i. ~ 1 Procedure Organi "ation Instruct i onal Step Format Step Numberino Condi ti anal Statements Paae Identif ication and Layout Override Statements l ~ 7 Cautions and Notes
' Pl F'igures and lables Use of Emphasis Techniques
- 3. 10 Typing instructions Remi sion 0
Document No. 8309-1, NNP-1 EOP Writer's Guide TABLE OF CONTENTS (CONTINUED) 4.0 PROCEDURE CONTENT ~ 20 Genera) 20 4 Level of Detail 21 4 ~ Step Construct i on 21
- 4. 4 Condi ti onal Statements
- 4. 5 Cauti ons and Notes 24 4.6 Branching Instructions and Cross-References 4.7 Component Identif ication gC 4.8 Spel 1 ina, Grammar, and Punctuation Nomenc l at ur e, Vocabul ary, and Abbrevi at i ons 26
- 4. 10 Numerical Values ~ ~7 LIST OF TABLES Tabl e 1 Application of Logic Terms Tab 1 e 2 Standard Nomenclature and Def ini ti ons 28 Table Standard Abbreviations >0 Revi si on 0
Document No. 8309'-1, NMP-1 EOP Writer 's Guide
- 1. 0 INTRODUCTION 1.1 P~ur ese This document specifies the conventions to be employed in the preparation of NMP-1 Emergency Operating Procedures (EOPs). These conventions are established to ensure consis-tenry in the organi=.ation, format, style. and content of the EQPs.
1.2 S~co e The guidelines contained herein address the speci,f ics of procedure i dentif i cati on. format, and content, and are app l i c ab l e to al l Nl'iP-1 EOPs.
This document is not intended to supplant existing NMP administrative procedures governing procedure preparation, revision. and control.
Revision Page 1 of 30
Document No. 8309-1, NMP-1 EOP Writer's Guide
- 2. 0 PROCEDURE IDENTIFICATION Each EOP shall be clearly and uniquely identified to facili-tate the location and use of the procedure by the operator.
Identification shall consist of a procedure title, procedure number. and revision number as described below.
Each EQP shall have a title page which supplies the follow-title ing information (refer to the sample page in Figure 1):
- 1. Company name Station name and unit designation 3 ~ Procedur e cl assif ication (Emergency Operating Procedure>
- 4. Procedure number Procedure ti tie 0 ~ Approval signatures
/ ~ Date and initial blanks for revision approvals 4 tabulation of the paqes included and their publication dates Fates date through which the procedure remains effec-t i ve 2.2 Procedure Numberin Each EOP shall be assigned an identification number havinq the foilowinq form:
N1-EOP-1
~ Unique sequential Procedure number classif ication Uni t desi gnati on Rpvl si on 0 Page 2 of 30
Document No. 8309-1, NMP-1 EOP Writer ss Guide MzME MIRE POINP MDCASAR SPAEEON Q2 SERE ADMINISISASIPE PROCEDIIRES Q3 PRoczDURE No. APM z Q4 PROCEDIIIIE POR ADIISMISERAEIPE CDIIIROIN Q5 Q2 Q5 DATE AND INITIALS APPROVALS SIGNATURES REVISION 8 REVISION 9 REVISION 10 Station Superintend NHPHS Unit I T. M. Roaan Station Superintendent NHPHS Unit 2 R. B. Abbott General Superintendent Huclear Generation Chaitnan of S.O.R.C, vfrP>
T. J. Perkins I Quality Assurance Concurrence Supervisor, QA HHP tl D. R. Feiner Sunnar of Pa es Effective Re vision 8
~pa e Date 1-3, 5,7-10 Novenber 1981 fz Septenber 1982 4 June 1983 NEAOAIIA MOEAIIK POIIER CORPORATION Q3 THIS PROCEDURE NOT TO BE Q9 USED ASSER June ISSS, SUBJECT TO PERIODIC REVIVI~
Fi gure 1. EOP Ti tl e Page Revi si on 0 Page 3 of .~O
Document No. 8309-1, NNP-1 EOP Writer's Guide
- 2. 2 Procedure Numberin (Continued)
The procedure identification number shall be typed in bold-face print within the title block on each page of the EOP as speci f i ed in Secti on 3. 5.
- 2. 3 Procedure Title Each EOP shall be assigned a unique title which is descrip-tive of the procedure content. The title shall be typed in boldface print within the title block on each page of the EOP as specified in Section 3 5.
2.4 Revision Identification Procedure revisions shall be distinguished through use of sequential revision numbers.
lhe procedure title page shall list all pages included in the current revision and indicate the date each page was issued. The date of issue shall also be placed in the bottom lef t. corner of each page of the EOP as specif ied in Sect i on = 5.
~
Whenever the content of any page i s changed for any reason.
thc nevi i ssue date shal be shown on the revi sed page and 1
the "Summary of Pages Effective" on the ti tl e page shal 1 be updated. Revised te;<t on the page shall be identi fied with verti cal bar s in the page mar gin ad.iacent to the change.
Change bars from pr erious revisions shall be deleted.
Revi si on 0 Page 4 of 3v
f4 Pocument No. 8309'-1, NMP-1 EOP Writer's Guide 3.0 PROCEDURE FORMAT The EOPs shall be formatted in accordance with the conven-tions outlined below. Standards for step numbering. spacing, and page layout are illustrated in Figure 2.
- 3. 1 Procedure Or anization Each EQP shall contain the following sections:
A. ENTRY CONDITIONS B. OPERATOR ACTIONS Section titles shall be typed in upper-case letters and underlined. Alphabetic designations "A" and "B" shall be used to designate section headings as indicated above.
3.2 Instructional Ste Format Instructional steps shall be complete sentences presented in a single column format. Footnotes shall not be used.
Division of the te::t of a step between two pages should be avoided. If a step must be divided, the step number shall be repeated at the top of the ne::t page. followed by the word "Continued" placed in parentheses.
Ep;ample:
5.2 (Continued>
3.3 Ste Numberin Instructional steps shall be numbered as follows (see e:<ample in Fioure i:
- 1. Steps shall be desionated by sequential Arabic numerals.
Revision 0 Page 5 of 3( )
Document No. 8309-1, NMP-1 EOP Writer's Guide TITLE: RPV FLOODINS NO. 1-EOP-7 A. ENTRY CONDITIONS CText of Entry Conditions3 B. 0 erator Actions
- 1. CText of step3 CText of step3
- 2. 1 CTevt of substep3
- 2. 2 CTex t of substep 3
- 1. CText of substep3
- 2. CTex t of substep 3 2.3 CText of substep3 o CItem3 o C Item3 o CItem3
'Etc.3 Date 2/30/84 Page 1 of 31 F'ure 2. EOP Format Revision 0 Page 6 of 30
l k Pocument No. 8309-1, NMP-1 EOP Writer 's Guide
- 3. 3 Ste Numberin (Continued)
- 2. Substeps shall be designated by sequential decimal numbers (3. 1. 3.2, 3.3, etc.). If further subdivision is necessary, single digit numbers or "bullets" shall be used. In general, numbers shall be used for action statements, bullets for conditional statements. (Refer to Section 3.4 below for a discussion of conditional statements. )
Example 2'=-uhdi vi=-ion of an action .=tatement):
WHEN .... boron in.jection has been initiated, THEN .... 1. Confirm automatic isolation of or manual l y i sol ate RWCU.
Continue to in ject boron into the RPV until 640 pounds of boron have been in.jected.
Exam pie 2 (svho'i vi si on of a con ii ti onal statement ):
Start pumps in alternate injection subsystems which are lined up for in.jection into the RPV. I I
I THEN .... Et'1ERGENCY RPV DEPRESSURI ZATI014 I IS REQUIRED.
I I
o WHEN .... RPV water l evel drops to O. 0 in.,
THEN .... continue in this procedure at Step 3. 11.
Revision Page 7 of 30
Document No. 8309-1, NNP-1 EOP Writer's Guide 3.3 Ste Numberin (Continued) 3s Lists appearing as part of an instructional step shall have entries designated as follows:
Lists of systems or components shall be itemi "ed with bullets.
ixampIe:
C M~ a Commence and slowly increase injection into the RPV with the following systems:
o Condensate booster pumps o Condensate pumps o CRD Lists of conditions or step numbers shall be itemi"ed with lower-case letters.
ExamoI e I (Ii=-t ot cordi ti orI.=):
IF .... any one or more of the f ol lowing conditions occur:
Off-site whole body dose rate is projected to exceed 1 Rem OR
- b. Off-site child thyroid dose is projected to exceed 5 Rem OR Cs Site boundary whole body dose rate approaches or exceeds 50 mR/hr for 1/2 hour Revision 0 Page 8 of 30
0 Document No. 8309-1, NMP-1 EOP Writer's Guide Ste Numberin (Continued)
- 3. (Continued)
Example 2 (list Ot step numbers):
Execute the following steps concurrently:
- c. Step 5 ~ ... reactor power control Bullets and letter desionators shall be indented two spaces to the right of the lef t margin of the main text of the associated step (see examples above) .
- 3. 4 Condi ti onal Statements Nhen an operator action is contingent upon the existence of certain plant conditions, the step shall be presented in the form of a conditional statement incorporating highlighted logic terms to clarify the distinction between conditions and actions. The following conventions shall be followed (ref er to the examples presented in Table 1 and to Section
- 4. 4 be] ow):
The conditional part of the step shall be stated first, followed by the contingent action.
Logic terms shall be typed in upper-case letters and vertically aligned, separated from the remainder of their respective clauses by a series of periods.
The ends of clauses shall be punctuated with commas.
4~ Conditional statements provided as contingency actions shall be indented so that the logic terms are aligned with the left margin of the text of the preceding step (see Example 5 below).
Revision 0 Page 9 of 30
0
'ocument No. 8309-1, NNP-1 EOP Writer's Guide 3.4 Conditional Statements (Continued)
- 5. If an action prescribed in a step is to be performed until certain specified conditions occur, the conditions shall be prefaced by the word "UNTIL" ty'ped in capital letters and shall be listed separately following the action statement (see Example 5 below>.
Example l:
IF ...... a reactor scram has not been initiated, THEN .... initiate a reactor scram.
Example 2:
IF ...... the main turbine-generator is on-line, AND IF .. the NSIVs are open, THEN .... confirm or initiate recirculation flow runback to minimum.
Example 3:
IF ...... reactor power is above 2.5%,
OR IF ... reactor power cannot be determined, THEN .... trip all recirculation pumos.
Revision 0 Page 10 of 30
Document No. 8309-1, NNP-1 EOP Writer's Guide
- 3. 4 Conditional Statements (Continued)
Example WHEN .... RPV water 1 evel drops to O. 0 in.,
THEN .... continue in this procedure at Step 3. 11.
Example S:
I IF ...... suppressi on pool water 1 evel i s above 5. 5 f t.,
I l
I I
THEN .... open all ADS valves.
IF ...... any ADS valve cannot be opened, THEN .... open other SRVs UNTIL ... 7 valves are open.
3.5 Pa e La out and Identification Each page of each EQP shall contain the following informa-tion (see example in Figure 2 on Page 6):
- 1. A title block e:ctending from margin to margin across the top of the page containing:
Procedure ti tie (upper 1 ef t corner)
Procedure number (upper right corner>
Issue date (lower left corner)
Rpvision 0 Page 11 of 30
Document No. 8309-1, NNP-1 EOP Writer's Guide
- 3. 5 Pa e La out and Identification (Continued)
- 4. Page number and total number of pages in the procedure (lower right corner)
ExampIe:
Page 12'f 32 The following page layout conventions shall be observed:
- 1. Each EOP shall begin 'on a new page.
- 2. Both sides of the pages shall be used and numbered.
Entry conditions and instructional steps shall be located on the right hand pages. Override statements and figures shall be located on the left hand pages.
(Refer to Section 3.6 below for a discussion of override statements. )
Left hand pages containing no override statements shall contain the words, "THIS PAGE INTENTIONALLY BLANK,"
typed in upper-case letters and centered on the page.
- 4. Te>:t shall begin on the third line below the title block.
The section title, "OPERATOR ACTIONS," need not be repeated on each page of Section B. However, to enhance the organi"ation of the more comple< EOPs, major subsection headings (e.g., "Monitor and control RPV water level" ) shall be placed at the top of each page containing applicable steps.
- 6. Page rotation should be avoided. If page rotation is required to accommodate graphs, tables, or figures, page margins, headings, and footings sh'all not be rotated.
- 7. Foldouts and oversi "ed pages shall not be used.
Revision 0 Page 12 of 30
Document No. 8309-i, NNP-1 EOP 4friter's Guide 3.6 Override Statements Conditional statements applicable to a series of steps or actions are herein designated "override" statements. (e.g.,
"While e>:ecuting Steps 8.2 and 8.3, if RPV water level can be determined, then continue in this procedure at Step 9 ") ~
The following conventions shall apply to the use of over-rides in the EOPs (refer to the illustration in Figure 3):
Override statements shal 1 be bo.ed and placed on the 1 ef t hand pages, even with the f irst steps to which they apply.
Override statements shall be repeated on subsequent left hand pages if the steps to which they apply continue on a ~
f ol 1 owi ng pages.
4+ ~ Arrows pointing to the 1 ef t shal 1 be pl aced immedi atel y to the left of the step numbers of steps having associa-ted override statements.
The top of the box where an override statement first appears shall be a double line ending with an arrow aligned with the arrow adjacent to the number of the step to which it applies. The tevt of the override statement, the double line forming the top of the bo.:,
and the arrow adjacent to the associated step number shall be printed in boldface type. On subsequent pages, the te;:t and the arrows shall be in regular type and the top of the bo;; shall be a single line, also in regular type.
ba The te.;t of the override statement shall specify the evact steps to which it applies.
6 ~ An arrow e:;tending down from the lef t side. of the box containing an override statement shall be used to graphically identify the steps to which the statement is applicable. The arrow shall e;:tend from the top of the bo~ to a point even with the last. line of the last step to which the statement applies. The end point shall be marl ed with a hori".ontal double line.
3.7 Cautions and Notes Each caution applicable to the EOPs shall be identified with a number and succint content. The full title, te;:ts descriptive of the caution of all EOP cautions shall be separately listed in Ni-EOP-l, "EOP Cautions."
Revision 0 Page 13 of 30
Le% t Page Right Page IITCSg ~ CCpgTNS. Ibersn lngectlon Nst gtobuirsdg IO NI~2 I TITLSI ~ CCPITKL ISorsn lnlectlon Nsc Asougrodi IO NI~2 I
I ter control react<<pouvg I I&II ~ osocutinc tng ~ I S. hong and I procodurog I Il I tch In the IF borgn in I C S I Congire or place the reactor mode aug isation I ~ I I I&II~ ~ oocutlns Steps S I throuch I r
IO roeugrodl I I
I Sag I
I I
Sgaggcgbdg position.
IdCN. all control rode vs in-I9 In IF baron has bosn in I ot t od ~
I I
I Ot
'rte4 be/ond pool tlgn 00 I
I I
S.2 IF ... the main turbgne~onvatv I ~ on line I Id'..the reactv ls shut 4<<n I AND IF, the nSIVO are open ~
TICN,, aeter I ~ nd no borgn haa been ln- I F<CP 1. I 1ected into the IVV, I TIOI ... ccng \re or initiate recirculation glom I I I I TISN,ent<<MF I ~ sltoadtV I runbast to minimus,
~ cram s 0 I I
I m S.1 IF ~, reactor powr I ~ aboue 2.SC I ~
5 I I CR IF ~ . reactor pouer cannot be detvsinad, I
I MN, trip all recirculation pumps, I
Q.
l9 I
I I S.a tsadute F O'a, alternate Central nsd Ineertlg<<S I
I %II Cont<<'root lr ul th thl ~ procedure III I rt goe S IF ...... the react<<c~t be sist dgmn bego ~
I rt I suppression geol mater temperature roaches 8 I I I l~s 9
8 3
I I CION, Sgpupg WECTIOI IS nfgbJInSDI enter F~S ~
nrv CentrOI IPVgn lngOCtisn naeulredg ~
s 0 I I \ II Date 2/IT/sa Date 2/11/Pa 0
GI G
Document No. 8309-1, NNP-1 EOP Writer's Guide 3.7 Cautions and Notes (Continued)
Within an EOP, the number and title of cautions applicable to a particular step shall be typed in upper-case letters in a box to the right of that step.
Example:
IF ~ ~ ~ ~ ~ ~ suppression pool CAUTION ¹ 8 OBSERVE temperature cannot NPSH L I HI TS I I
I I
I I I I I I be maintained below CAUTION ¹13 I I
I I
RAPID I I
I I
the Heat Capacity I NAY BE REQD I I
I I
I I
I I Temperature Limit, CAUTiON ¹14 I I
I 1
I I
CHECK I I
'THEN .. ~ ~ maintain RPV pres- NOTOR DRIVEN II I I
PUt'1PS AVAIL II I I
sure below the Limit.
Notes, where appropriate. shall be typed in italics. between the margins of the associated step. The word "NOTE" shall be typed in upper-case letters centered over the te.':t of the note.
Example:
NOTE Des eati ng RSCS interlocks may be required to ac=ompli sh the gaol l o<<i ng st ep:
Revi si on 0 Page 15 of 30
'ocument No. 8309-1, NMP-1 EOP Writer's Guide 3.8 Fi ures and Tables Figures and tables referenced within an EOP shall be grouped together and placed at the end of the EOP as an attachment.
The following conventions shall be observed:
- l. A table of contents shall be included on the attachment cover sheet.
Tables shal 1 be placed before figures.
Tables and f igures shall each be numbered sequential ly, in the order ref erenced, using a pref i;; corresponding to the number of the applicable procedure followed by a decimal numeral. The symbol "0" and the abbreviation "No." shal 1 not be used. E:<ample: Figure Ni-EOP-1.2 4, Each f igure and table shal have a title. Figure titles 1
shall be capitali"ed and centered below the figures, together with the figure numbers. Table titles shall be typed in upper-case letters and centered above the tables. together with the table numbers.
A reference to a f igure or table within the te:-:t of a procedure shall specify the page on which the figure or tabl e may be f ound.
6 ~ Figures should be clear, simple, and easily readable.
- 7. Graphs shall incorporate the following features:
A::es shall be labeled with parameters, units, and numerical values.
Grid lines shall be provided: numbered lines shall be bolder than unnumbered lines.
A:;es shall be scaled so as to match the scales of the corresponding control room instruments.
As a supplement to the f ul 1 si "e f igures provided in the attachment, small reproductions of each graph shall be placed within the body of the EOP on the lef t hand page opposite the associated step. These repro-ductions shall be labeled with the figure title, typed in boldface, upper-case letters, and the figure number, enclosed in parentheses. Only major scale divisions need be shown.
Revision 0 Page 16 of 30
Document No. 830'P-l, NMP-1 EOP Writer's Guide 3.8 Fi urea and Tables (Continued)
- 8. Tables shall incorporate the following features:
Tables shall be placed within boxes.
A heading shall be provided for each column.
Headings shall be in upper-case letters centered over the columns.
hori".ontal line shall be placed below the column headings.
Columns shall be divided by vertical lines.
Entries shall be separated by blank lines.
3.9 Use of Em hasis Techi ues Boldface print, upper-case letters, and underlines shall, be used for emphasis throughout the EOPs. The following conventions shall be observed:
Boldface print shall be used in the f ol lowing applications:
Procedure numbers and titles in title blocks Figure titles on lef t hand pages First occurrences of override statements Upper-case letters shall be used in the following applications:
Logic terms Caution titles Note headings Identification of as-labeled component designations and annunciator engravings Tabl, and figure titles and headings Revision Page 17 of 30
Document No. 8309-1, NMP-1 EOP Writer's Guide
- 3. 9 Use of Em hasis Techi ues (Continued)
(Continued)
Acronyms Section headings Identification of a requirement for Emergency RPV
Dearessuri"ation,
Steam Caolina, RPV Flooding, Alter-nate Shutdown Cooling, or Boron Injection.
Example:
a IF ...... suppression pool temperature and RPV pressure cannot be re-stared and maintained below the I
I Heat Capacity Temperature Limit.I THEN .... EMERGENCY RPV DEPRESSURI ZATION IS REQUIRED.
Underlining shall be used in the following applications:
Caution titles Section titles Emphasis of individual words, where appropriate, within procedure steps.
- 3. 10 T in Instructions The EOPs shall be typed in accordance with the following instructions (refer also to the EOP format illustrated in Fi gure 2 on Page 6):
- 1. Paper si=e shal 1 be S-1/2:< 11 inches.
Revision 0 Page 18 of 30
Document No.. 8309-1, NMP-1 EQP Writer's Guide
- 3. 10 T in Instructions (Continued)
Nargins shall be maintained as follows:
Left: l-l/4 inches Right: 1 inch Top: 1 inch Bottom 1/2 inch 3e Text shall begin on the third line below the title bl ock.
- 4. Double line spacing shal l be used. Two blank lines shall be inserted between steps and before and after section headings.
- 5. Section titles shall be typed in upper-case letters and underlined. The letter designations for section headings shall be aligned with the left margin. Two spaces shall be inserted between the period followina the letter designation and the section title.
0 Step numbers shall be vertically aligned under the first letter of the section title. Two spaces shall be
~
inserted between the period following the step number and the beginning of the text of the step. If the text of the step occupies more than one line. the first words of all lines shall be vertically aligned on the lef t ~
- 7. Substep numbers shal I be indented so as to be verti-cal ly aligned under the first letter in the text of the preceding step. Two spaces shall be inserted between the substep number and the beginning of the. text of the substep. If the substep occupies more than one line, the first words of all lines shall be vertically al i gned on, the 1 ef t.
- 8. Division of words at the ends of lines should be avoided. Division of words between pages is not allowed.
Excessive indentation should be avoided.
Revision 0 Page 19 of 30
Document No. 8309-1, NMP-1 EOP Writer's Guide 4.0 PRQCEDVRE CONTENT
- 4. 1 General Each EOP shall contain the following sections:
A. ENTRY CONDITIONS B. OPERATOR ACTIONS The ENTRY CONDITIONS section of an EOP shall contain a statement of the conditions requiring entry into that pl ocedure ~
Example:
A. ENTRY CONDITIONS I
I I
Entry into this procedure is required whenever I
any of the following conditions occur:
Parameter Condition
- 1. RPV water level ---> below 177 in.
4 ~ RPV pressure > above 1045 psig CEtc. 3 The OPERATOR ACTIONS section of an EOP shall contain the sequential steps of the procedure. Short, concise instruc-tions giving appropriate directions to the user shall be provided. Any required verification of automatic plant response shall be included as an instructional step. A mandatory step sequence shall be assumed unless otherwise stated.
Revision 0 Page 20 of 30
Document No. 8309-i, NMP-I EOP Writer's Guide 4.2 Level of Detail The level of detail presented in the EOPs shall be estab-lished in accordance with the following considerations:
The level of detail should be consistent with the knowledge and capabilities of the least experienced intended user.
The relative complexity and familiarity of the required evolutions should be considered.
Excessive detail should be avoided. Expected results of routine. actions need not be stated.
Where general instructions are specified, the user should be able to explain the step in detail.
C Where appropriate, the following information shall be included:
System response times Equipment limitations Instrument inaccuracies Alternate or backup instrumentation Contingency actions Manual override instructions Methods of verifying correct plant response 4.3 Ste Construction Instructional steps shall be written in accordance with the following considerations:
- i. The procedure shall be easily readable and interpretable.
- 2. Directions shall be written in the second person imperative mood with an implicit subject.
Instructions should be succint and precise. Short.
simple sentences should be used.
Revision 0 Page 2i of 30
Document No. 8309-i, NMP-1 EOP Writer's Guide 4.3 Ste Construction (Continued)
- 4. Generally, each step should address only one idea.
Comple., evolutions should be addressed in a series of steps.'.
The objects of actions should be specifically stated (i.e.. it should be obvious e>:actly what is to be done to what). !'Iultiple objects should be listed separately.
Exam'!e:
Commence and sl owl y increase in j ect i on i -
into the RPV with the following systems:
o CS o CS keep-full o'ondensate transf er
- 6. Actions which me<st be perf ormed concurrently shal 1 be specif ical ly identif ied.
- 7. Limi'ts should be e pressed quantitatively. Annunciator setpoints should be specified when appropriate.
- 8. Arithmentical calculations should be avoided.
Terminology should be consistent with the guideli'nes presented in Section 4.9 below.
4.4 Conditional Statements Logic terms in conditional statements shall be selected and applied consistent with the usage defined in Table i.
Revision 0 Page 22 of 30
Document No. 8309-i, NMP-1 EOP Mriter's Guide Table i APPLICATION OF LOGIC TERMS Conditional statement logic terms shall be selected and applied consistent with the usage defined below:
l~oi c Term Def ini ti on AND Indicates a combination of condi-ti ons. Ident i f i es the second and subsequent elements of a set of conditions.
Indicate~ that the action pre-scribed in the step is contingent upon the stated conditions. Iden-tifies the condition as possible, but not necessarily e>:pected.
ONLY IF Qualifies a conditional statement.
Emphasi"es that the action is not to be performed unless the stated condition occurs.
Designates an alternative condi-tion.. Indicates that the action is to be performed if eith'er of two conditions occur. (Always used in the inclusive sense.)
THEN Distinguishes the action portion of the step.
Indicates that the action pre-scribed in the step is contingent upon an expected condition.
Revision 0 Page 23 of 3(i
Dacument No. 8309-1, NMP-1 EOP Writer's Guide 4.5 Cautions and Nates Cautions shall be used to identify a potential ha"ard to personnel or equipment. Notes shall be used ta provide supplementary information related to a particular step.
Use of both cautions and notes shall be minimi=.ed. Neither shall contain instructional steps.
4.6 Branchin Instructions and Cross-Referances Branchina instructions shall be used to direct the operator to either e;:it a given step of a procedure and enter a new step or procedure, or to perfarm an additional step or pro-cedure concurrently with the given step. The instrurtions shall taLe one of the followinq forms, as appropriate:
(a) Enter Procedure X at Step Y Indicates that the operator must e::it the pro-cedure containina the instructions and enter the nevi procedure at the speci fed step.
(b) Enter Procedure X at Step Y and perform it concurrently Indicates that the operator must perform an additional series of steps concurrently with the procedure containing the instruction.
(c) Continue in this procedure at Step Y Indicates that the operator is to e>;it the step containing the instruction and proceed in accordance with the instructians contained in the specified step. Used to branch to a subsequent step.
(d) Return to Step Y of this procedure Indicates that the operator is to exit the step containing the instruction and proceed in accardance with the instructions contained in the specified step. Used to branch to a previous step.
Revision 0 Page 24 of 30
l Document No. 8309-i, NMP-1 EOP Writer's Guide 4.6 Branchin Instructions and Cross-References (Continued)
Forward and backward branching within the same procedure should be minimi"ed. When intra-procedure branching is necessary, the page numbers of the branch steps shall be specified. The section designation "8" is considered implicit in the step number for operator actions and need not be included in the reference.
Cross-ref erences shall be speci f i ed where additional proce-dur es or steps are to be used as a supplement to a particular step. Use of cross-references shall be minimi "ed; if only a few, relatively simple actions are involved, the referenced instructions shall be incorporated into the step itself.
When cross-references are appropriate. procedures shall be referenced by both number and title. with the title enclosed in quotation marks.
Figures and tables referenced within a procedure shall be identified by both number and title. The page on which the ref erence is found shall be specified.
4.7 Com anent Identification Components shall be clearly and completely identif ied within the procedures'he following conventions shall be observed:
If the tep refers to a specific panel control or instrument, the as-labeled designation shall be used, typed in upper-case letters. Otherwise, common-usage designations shall be used.
mr System titles shall be capitali=ed. The word "system" need not be 'included in the title.
Component locations shall be specified if the components are infrequently used or if there would otherwise be a possibility of confusion.
Revision 0 Page 25 of 30
Document No. 8309-1, NMP-1 EQP Writer's Guide 4.8 S ellin Grammar and Punctuation Spelling. grammar, and punctuation shall be consistent with standard rules and modern usage. In addition, the following specif ic guidelines shall be considered:
- 1. E,".cessive use of commas should be avoided.
- 2. Use of def inite articles should be minimi "ed.
3 ~ Use of pronouns should be minimi "ed. Personal pronouns shall not be used.
- 4. Use of adverbs should be minimi=.ed.
- 4. 9 Nomencl ature Vocabul ar and Abbreviations Words and abbreviations shall have consistent meanings throughout the EOPs. The following conventions shall be observed:
- f. Simple, common words shall be used.
- 2. Words shall have specifc, precise meanings. Ambiguous terms such as "slowly" should be avoided.
The standard definitions li.sted in Table 2 (Page 28) shall be adopted.
U..e of abbreviations shall be minimi"ed. Only those immediately recogni=able shall be used. (A list of approved abbreviations is provided in Table 3 on Page 30.)
A period shall be omitted from abbreviations e:<cept when such omission would introduce confusion (e.g., "inch" shall be abbreviated "in.").
- 6. Acronyms shall be typed in upper-case letters.
Revision 0 Page 26 of 30
Document No. 8309-1, NMP-1 EOP Writer's Guide
- 4. 10 Numer i ca 1 Values Limits and values of operating parameters shall be expressed quantitatively in the EOPs. The following conventions shall be observed:
- 1. Arabic numerals shall be used.
Parameter values shall include the units of measure-ment. Units shall be the same as those displayed on associated panel instrumentation.
Parameter values shall be expressed to a precision consistent with the intent. of the step and the accuracy and precision of associated instrumentation.
Acceptance values shall be expressed in terms of a range rather than a tolerance band to obviate the need for mental ari thmenti c.
Example: 20 in. to 30 in., rather than 25 in. +5 in.
5 ~ A virgule shall be used in place of the word "per."
- 6. Numbers between "ero and one shall be expressed in decimal form with a "ero preceding the decimal point.
Example: 0. 12 Revision 0 Page 27 of 30
e Document No. 8309-1, NMP-i EOP Nriter 's Guide Table 2 STANDARD NONENCLATURE AND DEFINITIONS Available: The state or condition of being ready to be placed into operati on.
Before! Prior to; does not imply any specific margin.
Cannot be determined! The value of the specified parameter cannot be defined using available indications.
Cannot be maintained! The value of the specified parameter cannot be kept above or below the applicable limit. Implies an evaluation based on system performance and availability considered in relation to parameter values and trends: does not necessarily imply that the parameter has actually exceeded the limit.
Cannot be restored: The value of the specified parameter cannot be returned to within the specified limit. Implies an evaluation based on system performance and availablility considered in relation to parameter values and trends. Does not imply any specific time limit, but does not permit prolonged operation in excess beyond the limit.
Close: lo position a valve or damper so as to prevent flow of the proress fluid.
Conf irm! Use available indications to verify that the specif i ed state exists or that the specified actions have occurred.
Does not imply an instruction to take action.
Control: Take action, as necessary, to maintain the value of the specified parameter within applicable limits.
Enter: Commence performing. in sequence, the steps of the identified procedure. Unless concurrent execution is specif ical ly directed, implies an instruction to exit the procedure containinq the statement.
Executec Perform the actions prescribed in the identified step.
Initiate! Operate the necessary controls so as to establish the specified syst: em or plant condition.
Revi si on 0 Page 2S of 30
0 Document No. 8309-1, NMP-1 EOP Writer's Guide Table 2 STANDARD NOMENCLATURE AND DEFINITIONS (Continued)
Line up: Establish the prerequisites necessary for system operation.
Maintain: Take action, as necessary, to keep the value of the specif ied parameter within the applicable limits.
Monitor! Observe and evaluate at a frequency sufficient to remain appraised of the value, trend, and rate of change of the specif ied parameter.
Open! To position a valve or damper so as to allow flow of the process f 1 ui d.
Operable: Capable of performing an intended function.
Operating: Performing an intended function.
Place: To align a switch to a specified position.
Prevent: Take action to forestall or avert the state, condition, or action addressed by the step.
Restore: Take action, as necessary, to return the value of the specified parameter to within applicable limits.
Set: To position a control to a specified scale value.
Shut: To position a breaker so as to permit the flow of current in the associated circuit.
Start: To energi=e a pump or fan motor.
Stop: To deenergi=e a pump or fan motor.
Terminate! Stop and prevent the stated action or evolution.
Throttle: To position a valve or damper so as to partially restrict flow of the process fluid.
Trip! To position a breaker so as to interrupt or prevent the flow of current in the associated circuit.
Vent: To reduce the pressure in an enclosed volume.
Revision 0 Page 29 of 30
Document No. 8309-1, NNP-1 EOP Writer's Guide Table 3 STANDARD ABBREVIATIONS The following abbreviations are approved for use in the NNP-1 EOPs:
Abbreviation Meanino ADS Automatic Depressuri"ation System CRD Control Rod Drive EC Emergency Condenser ECCS Emergency Core Cooling System EVS Emergency Ventilation System Feet HCU Hydraulic Control Unit HX Heat e:<changer in. Inch LPCS Low Pressure Core Spray t'I$ 1 V I'lain steam isolation valve Net positive suction head psl g Pounds per square inch (guage)
Revolutions per minute RPV Reactor Pressure Vessel Reactor Water Cleanup SLC Standby Liquid Control SORV Stuck open relief valve SRV Saf ety/rel i ef val ve Revision 0 Page 30 of 30
ATTACHMENT 3 Veri fi cation/Va1 i dati on Program Oescri pti on
0 Verification Pro ram Descri tion
- l. Overview Emergency Operating Procedure (EOP) verification is a comparative evaluation addressing the written correctness and technical accuracy of Emergency Operating Procedures. It is one of the activities which must be completed prior to implementation of revised EOPs.
The EOP Verification Program will include:
- l. An evaluation of the EOPs for consistency with applicable source documents
- 2. An evaluation of the EOPs with respect to accepted human factors criteria pertaining to the presentation of procedural information
- 3. An evaluation of the'EOPs for consistency with the controls and instrumentation provided in the control room The results of the evaluation will be documented. As appropriate, recommendations for correcting deficiencies and improving the procedures wi 11 be provided.
- 2. Pre aration of the EOP Verification Pro ram Plan and Im lementation Procedures An EOP Verification Program Plan and the necessary procedures for implementing the program and documenting the program and documenting the program results wi 11 be prepared in advance of conducting formal EOP verification. In combination, the Program Plan and the Implementation Procedures will provide the specific definitions, instructions, evaluation criteria, checklists, and documentation forms necessary for carrying out EOP verification.
The guidance provided in INPO Report 83-004, "Emergency Operating Procedures Verification Guideline" will be considered in the preparation of the Program Plan and Implementation Procedures. Both the Plan and the Procedures will be approved by the Nine Mile Point Unit 1 Operations Staff prior to use.
- l. An evaluation of the technical accuracy and adequacy of the EOPs (i.e., an assessment of the EOPs with respect to applicable source documentation, including that provided in the generic BWR Emergency Procedure Guidelines and the Nine Mile Point 1 plant-specific Emergency Procedure Guidelines Page 1 of 2
Verification Pro ram Descri tion
- 3. EOP Verification Pro ram Sco e (cont'd)
- 2. An assessment of the EOPs'dherence to the instructions contained in the EOP Writer 's Guide and additional plant administrative requirements applicable to procedure writing
- 3. A review of the EOPs for compliance with accepted human factors principles for writing emergency operating procedures; this review will include an evaluation of procedure characteristics relating to ease of reading and comprehension under their anticipated conditions of use
- 4. An evaluation of the EOPs compatibility with control room hardware {both instrumentation and controls)
Results of the evaluations and reviews will be documented, including the identification of procedural discrepancies and deficiencies, and forwarded to the Nine Nile Point Unit 1 operations staff for consideration. Where appropriate, recommendations for procedural improvements will be provided by those performing the verification.
Page 2 of 2
0 Validation Pro ram Oescri tion
- 1. Over vi ew Emergency Operating Procedures (EOP) validation is a performance evaluation addressing the usability and operational correctness of emergency operating procedures. The Validation Program objective is to assure that the emergency operating procedures provide adequate instructions for managing emergency conditions. As such, the full set of emergency operating procedures is evaluated in combination with each other, and with the other plant procedures which are used in concert with the emergency operating procedures. Validation is one of the activities which must be completed prior to imp'lementation of revised EOPs.
The EOP Validation Program will include:
- l. An assessment of the adequacy of the EOPs'evel of detail
- 2. An evaluation of the understandability of the EOPs
- 3. An evaluation of the EOPs with respect to their correctness and usability for mitigating the consequences of transient and accidents The results of the evaluations will be documented. As appropriate, recommendations for correcting deficiencies and improving the procedures will be provided.
- 2. Pre aration of the EOP Validation Pro ram Plan and Im lementation roce ures An EOP Validation Program Plan and the necessary procedures for implementing the program and documenting the program results will be prepared in advance of conducting formal EOP validation. In combination, the Program Plan and the Implementation Procedures will provide the specific defintions, instructions, evaluation criteria, checklists, and documentation forms necessary for carrying out EOP validation.
The guidance provided in INPO Report 83-006, "Emergency Operating Procedures Validation Guideline" will be considered in th'e preparation of the Program Plan and Implementation Procedures. Both the Plan and the Procedures will be approved by the Nine Mile Point Unit 1 Operations Staff prior to use.
Page 1 of 2
A 0
Validation Program Description
- 3. EOP Validation Pro ram Sco e The EOP Validation Program will employ two methods of validating procedures, both of which are described in INPO Report 83-006:
- 1. Table-Top
- 2. Walk-Through Station Shift Supervisors will participate in the Table-Top validation process. Operator actions for responding to various transient and accident scenarios will be discussed and the EOPs evaluated with respect to the adequacy of the instructions provided. An evaluation of the EOPs understandability and usability will also be performed.
Walk-throughs using the EOPs will be performed in either the Nine Mile Point Unit 1 control room or plant specific simulator to evaluate procedure, plant, and crew compatibility. EOP usability and operational correctness will also be evaluated as part of this EOP validation activity.
Feedback from licensed operators participating in EOP classroom and simulator training will also be incorporated into the EOP Validation Program.
Results of EOP validation evaluations and reviews wi 11 be documented, including the identification of procedural discrepancies and deficiencies, and forwarded to the Nine Mile Point Unit 1 operations staff for consideration. Whereappropriate, recommendations for procedural improvements wi 11 be provided by those performing the validation.
Page 2 of 2
ATTACHMENT 4 Training Program Oescription
u (1
Trainin Pro ram Descri tion The Training Program established to support implementation of the Emergency Operating Procedures will be based on the following goals:
to enable the operators to understand the structure of the Emergency Operating .Procedures, to enable the operators to understand the technical bases of the Emergency Operating Procedures, and to enable the operators to use the Emergency Operating Procedures under operational conditions.
To accomplish these goals a combination of self study, classroom, and plant specific simulator training will be used. Self study and classroom training will familiarize the operators with the historical development and technical bases behind the Emergency Operating Procedures. Simulator training will emphasize use of Emergency Operating Procedures during operational conditions.
As the Emergency Operating Procedures are developed and approved, they will be incorporated into Operator Requalification Training to provide preliminary familiarization with the concept and content of the Emergency Operating Procedures. When all of the Emergency Operating Procedures have been developed and verified, the Training Staff will be trained in the Emergency Operating Procedures. To accomplish this, a consultant familiar with the background of the Emergency Operating Procedures has been contracted to provide lesson plans, handout material and instructor training.
To accomplish the training of licensed staff and operators, the annual Simulator Requalification Program will be expanded from three to an anticipated five days. During this time a program of integrated classroom/simulator training will be conducted to train licensed staff and operators as a shift/crew/plant unit. It is anticipated 'that this can be completed in three days of each training week. Tentatively, the remaining two days would be utilized to complete requalification requirements. This projection will be firmed up as the Emergency Operating Procedures become available and lesson plans are developed.
Requalification training will be completed in a similar manner. Changes to Emergency Operating Procedures will be addressed in Operator Requalification and by routing. Annual Simulator Training will be integrated into the annual simulator requalification.
Operator Training on the Emergency Operating Procedures will be completed prior to actual implementation.
Page 1 of 1
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