ML100331631
| ML100331631 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/11/1991 |
| From: | Basile J Consolidated Edison Co of New York |
| To: | NRC/IRM |
| Shared Package | |
| ML100331633 | List: |
| References | |
| NUDOCS 9101170245 | |
| Download: ML100331631 (4) | |
Text
Stephen B. Brain Vice PresidentO 7
Consolidated Edison Company of New York, Inc.
Indian Point Station Broadway & Bleakley Avenue January 11, 1991 Buchanan, NY 10511 Telephone (914) 737-8116 Re:
Indian Point Unit No. 2 Docket No. 50-247 Document Control Desk US Nuclear Regulatory Commission Mail Station P1-137 Washington, DC 20555
SUBJECT:
Revision to Emergency Action Level Tables!
Emergency Plan Enclosed are two tables revising the Emergency Action Levels of the station's Emergency Plan which are currently being processed for implementation approximately thirty days from the date of this letter.
One table concerns the conditions calling for the declaration of "Site Area Emergency" while the other table pertains to "General Emergency".
A common change affects both tables and reflects that the declaration of the specific emergency action level is appropriate for the conditions set forth only when the Reactor Coolant System temperature is greater than 350'F. This revision makes the revised tables consistent with the Technical Specifications and the Emergency Operating Procedures.
The need for the revisions stems from an inadvertent omission of the "greater than 350*F"1 qualifier at the time the tables were last revised.
If left unchanged an inappropriate emergency action level declaration could result from normal maintenance activities occurring during cold shutdown.
These revisions have been evaluated per the requirements of 10 CFR 50.54(q) and were found to result in an increase rather than a decrease in the effectiveness of the Emergency Plan.
Should you or your staff have any questions, please contact Mr.
Charles W. Jackson, Manager, Nuclear Safety and Licensing.
Very truly yours, 9101170)245 910111
~
FDR ADOCK 05000247 F
PDR Y
cc:
Mr. Thomas T. Martin Regional Administrator -
Region I US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Francis J. Williams, Jr., Project Manager Project Directorate I-1 Division of Reactor Projects I/II US Nuclear Regulatory Commission Mail Stop 14B-2 Washington, DC 20555 Senior Resident Inspector US Nuc *lear Regulatory Commission P0 Box 38 Buchanan, NY 10511
TABLE 4-3 Indian Point 2 Event Based SITE AREA EMERGENCY Table 1. Power Loss
- 4. Operational (One of the following)
- f. Turbine missile or other equipment (One of the followin )
4 Loss of all Unit 2 A.C. AND loss of missile causing loss of all auxiliary
- a. ATWS
- Pe nce of FR.S.1 to final Qt Light and Power Bus Section 3 feedwater WITH loss of either of the check for gative rate; expected results (A
ate Safe Shutdown System power following: all High Head SIS pumps M1 ill obtained.
capabily for more than 15 minutes.
all primary PORVs needed for feed and
- b.
ss of physical control of the plant for
- b. Loss of all it 2 D.C. AND loss of bleed.
/
I more than 15 minutes (Alert Category Unit I Light anaPower Bus Section 3
- g. Explosion causing loss of all auxiliary 4B declared and in effect for more than S
(Alternate Safe Shuqwn System feedwater WITH loss of either of 15 minutes).
power capability) for m than 15 following: all High Head SIS ps
- c. Known damage to fuel in the fuel minutes.
OR all primary PORVs ne for storage building with valid R-27 reading
- c. Loss of offsite power WITH S feed and bleed.
of> 2.7 x 105 uCi/sec.
tube rupture with actual SI and SG
- d. Loss of auxiliary feedwater control not obtained (exit from E-3,
- 3. Natural Phe imena AND loss of either of the following:
ES-3.l, ES-3.2 or ES-3.3 to an lant above c shutdown High Head SIS pumps OR all primary ECA procedure).
oPORVs needed for feed and bleed.
- a. E uake causing loss of all auxiliary
- 2. Fire, Security, Hazards eewa loss of either of the control not obtained (exit from E-3, ES Plant above cold shutdown following: a h Head SIS pumps 3.1, ES-3.2 or ES-3.3 to an ECA (One of the following)
ORall primary Vs needed for feed procedure) Y4THi loss of offsite power.
- a. Fire causing loss of all auxiliary feed-and bleed.
water WITH loss of either of the follo g:
- b. Hurricane causing loss of_
iary
- 5. Radiological Releases all High Head SIS pumps OR all p feedwater WITH loss of either of (One of the following)
- PORV's needed for feed and ble following: all High Head SIS pumps
- a. Valid sustained R-27 reading of one of b b. Security level 4D event fol by a level OR all primary PORVs needed for the following for more than fifteen 7 event as determined by urity.
feed and bleed.
nts
- c. Toxic gases in the CC AND any Alternate
- c. Tornado causing loss of of all auxiliary
- x 107 uCi/sec for A Pasquill Safe Shutdown S em (AS SS) area at the feedwater WITH loss of either of the
> 2.6 x 6 uCi/sec for B Pasquill following c entrations: chlorine> 3 ppm; following: all High Head SIS pumps
> 1.1 x106 u sec for C Pasquill Hy n Cyanide > 10 ppm; Ammonia >
OR allprimary PORVs needed for feed
> 3.8 1 05 uCi/se r D Pasquill 35 ppm.
and bleed.
> 2.4 x 105 uCi/sec for asquill
- d. Flammable gases at an explosive level in the
- d. Flood causing loss of all auxiliary
> 1.4 x 105 uCi/sec for F Pasquill CCR AND any Alternative Safe Shutdown feedwater WITH loss of either of the
- b. Field monitoring teams report site bound area as determined by the plant chemist.
following: all High Head SIS pumps ary readings of> 50 mR/hr W.B. OR>
CD
- e. Aircraft crash causing loss of all auxiliary OR all, primary PORVs needed for 250 mR/hr thyroid for more than 1/2 Q0 feedwater WITH loss of either of the fol-feed and bleed.
hour, OR 500 mR/hr W.B. instant lowing: all High Head SIS pumps OR all aneous.
primary PORVs needed for feed and bleed.
4-11
IndiaE
- BE Indian Point 2 Event Based GENERAL EMERGENCY Table I. Power Loss
- a. Loss of all Unit 2 A.C. AND loss of Unit 1 Light and Power Bus Section 3 (Alternate Safe Shutdown System power capability) AND failure of steam driven auxiliary feedwater pump occurs AND none are returned to service within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 2. Fire, Security, Hazards Plant above cold shutdown (One of the following)
- a. Fire causing plant transient WITH loss of all main AND auxiliary feedwater AND loss of either of the following: all High Head SIS pumps OR all primary PORV's needed for feed and bleed.
- b. Security level 4D event followed by a level 7 event as determined by security leading to loss of all main AND auxiliary feed water AND loss of either of the following:
,all High Head SIS pumps OR al primary PORVs needed for feed and bleed.
- 3. Natural Phenomena Plant above cold shutdown (One of the following)
- a. Earthquake causing plant transient WITH loss of all main AND auxiliary feedwater AND loss of either of the following: all High Head SIS pumps OR all primary PORVs needed for feed and bleed.
- b. Hurricane causing plant transient WITH loss of all main AND auxiliary feedwater AND loss of either of the following: all High Head SIS pumps OR all primary PORVs needed for feed and bleed.
- c. Tornado causing plant transient WITH loss of all main AND auxiliary feedwater AND loss of either of the following: all High Head SIS pumps OR all primary PORVs needed for feed and bleed.
- d. Flood causing plant transient WITH loss of all main AND auxiliary feedwater AND loss of either of the following: all High Head SIS pumps OR all primary PORVs nedded for feed and bleed.
- 4. Operational (One of the following)
- a. ATWS - Performance of FR-S.I to final check for negative rate; expected results still not obtained AND incore thermo couples are greater than 1200"F.
- b. Loss of physical control of the plant AND incore thermocouples are greater than 1200"F (SAE Category 4b declared and incore thermocouples are greater than 1200"F).
- c. Incore thermocouples are greater than 1200'F and no ECCS is available.
- d. Loss of Rl main AND auxiliary feedwater AND loss of either of the following: all High Head SIS pumps OR all primary PORVs needed for feed and bleed.
- 5. Radiological Releases (One of the following)
- a. Valid sustained R-27 reading of one of the following for more than 15 minutes.
> 2.4 x 108 uCi/sec for A Pasquill
> 5.2 x 107 uCi/sec for B Pasquill
> 2.1 x 107 uCi/sec for C Pasquill
> 7.5 x 106 uCi/sec for D Pasquill
> 4.7 x 106 uCi/sec for E Pasquill
> 2.8 x 106 uCi/sec for F Pasquill
- b. Field monitoring teams report site boundary readings of > 1 R/hr W.B.
OR 5 R/hr thyroid.
4-12
-1 0.