ML20035F364
| ML20035F364 | |
| Person / Time | |
|---|---|
| Issue date: | 03/25/1993 |
| From: | De Planque E NRC COMMISSION (OCM) |
| To: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| NUDOCS 9304210196 | |
| Download: ML20035F364 (7) | |
Text
........................
RELEASED TO THE PDR
- l NOTATION V O T E-i a2:e in RESPONSE SHEET
........'.........gts fi
.......q l
T0:
SAMUEL J. CHILK, SECRETARY OF THE COMMISSION FROM:
C0m ISSIONER DE PLANQUE j
i
SUBJECT:
SECY-93-006 - PROPOSED AMENDMENTS TO 10 CFR l
PART 72 TO ESTABLISH THE EMERGENCY PREPAREDNESS LICENSING REGULATIONS FOR INDEPENDENT SPENT FUEL STORAGE FACILITIES (ISFSI) AND MONITORED RETRIEVABLE STORAGE FACILITIES (MRS)
APPROVED x
DISAPPROVED ABSTAIN f
NOT PARTICIPATING REQUEST DISCUSSION l
C0lHENTS:
See attached comments.
f 1
l i
210033 e A s.4 & -
SIGNATURE RELEASE VOTE
/ xx /
xarch 25,1993 DATE WITHHOLD VOTE
/
/
]
t NO zg ENTERED ON "AS" YES x
1 IQ ESE*" css 75!8S""
T CORRESPONDENCE PDR
a Commissioner de Planque's comments on SECY-93-006 1
I approve publication for public comment of the proposed rule on emergency preparedness for ISFSI and MRS facilities with the editorial corrections noted on the attached pages.
I also agree with the comments of my fellow Commissioners.
Further, I note an area of possible confusion concerning an ISFSI located at the site of a power reactor that is no longer operating.
Existing section 72.32 (c) refers to an ISFSI
" located on.the site of a nuclear power reactor licensed for operation.
Proposed section 72.32 (a). addresses applications for an ISFSI "(that is not located on the site of a nuclear power reactor)".
I suggest clarifying language to address situations where the reactor is no longer licensed for i
operation.
One approach might be to modify the proposed rule to read:, 72.32 (a) " Each application for an ISFSI (that is not located on the site of a nuclear power reactor,
'or that is located on the site of a nuclear power reactor which does not i
have an operating license) l At the final rule stage, I will be particularly interested in comments and staff resolution relating to whether the emergency preparedness requirements (and how they would be implemented) are reasonable, and commensurate with the' nature of the possible i
hazards posed by facility operation.
f i
k I
t 7
1 r
I i
i
{
i
\\
1 117(a), 141(h), Pub.
L.97-425, 96 Stat. 2202, 2203, 2204, 2222, l
2244 (42 U.S.C. 10101, 10137(a), 10161(h), Subparts K and L are also issued under sec. 133, 96 Stat. 2230 (42 U.S.C. 10153) and 218(a), 96 Stat. 2252 (42 U.S.C.
10198).
2.
In S 72.32 paragraphs (a) and (b) are revised to read as follows:
1 S 72.32 EMERGENCY PLAN (a)
Each application for an ISFSI (that is not located on the site of a nuclear power reactor) that is licensed under this part must be accompanied by an Emergency Plan that includes the following information:
(1)
Facility description.
A brief description of the licensee's facility and area near the site.
(2)
Types of accidents.
An identification of each type of radioactive materials accident for which protective actions may be needed.
(3)
Classification of accidents.
A classification system for classifying accidents up to an alert gg
- ;_. e g ~ g.
l 21
'70kR_
Detection of accidents.
Identificationk of.neans (4) 6 c\\Occ$h\\
[
for_detsordon@--of-apprhincF an accident y
/
condition.
A brief description (5)
Mitigation of consequences.
of the neans of nitigating the consequences of each type of accident, including those provided to and a description of the protect workers onsite, progran for naintaining the equipment.
A brief description of (6)
Assessment of releases.
the nethods and equipment to assess releases of radioactive materials.
(7)
Responsibilities.
A brief description of the responsibilities of licensee personnel should an including identification of accident occur, personnel responsible for promptly notifying also offsite response organizations and the NRC; and responsibilities for developing, naintaining, updating the plan.
Notification and coordination.
A connitment to (8) and a brief description of the means to promptly notify offsite response organizations and request offsite assistance, including nedical assistance for the treatment of contaninated injured onsite I
workers when appropriate.
A control point nust be 22
J A brief description of the means (11) Safe Condition.
of restoring the facility to a safe condition after an accident.
Provisions for conducting semiannual (12) Exercises.
communications checks with offsite response organizations and biennial onsite exercises to test response to simulated emergencies.
I~ Semiannual communications checks with offsite response organizations must include the check and 7 Lk ary telephone numbers.
L_ update of all necess hadiological/HealthPhysics, Medical,andFire yp k
The JDrill should be conducted semiannually.
licensee shall invite offsite response organizations to participate in the biennial exercises.
Participation of offsite response organizations in biennial exercises although recommended is not Exercises must use scenarios not known required.
The licensee shall to most exercise participants.
critique each exercise using individuals not having direct implementation responsibility for evaluate Critiques of exercises must the plan.
the appropriateness of the plan, emergency training of facilities, equipment, procedures, and overall effectiveness of the personnel, 24
1 organizations capable of augmenting the 4
planned onsite response have been identified.
I J
(16) Arrangements made for providing information to the i
1 j
public.
1 (b)
Each application for an MRS that is licensed under this I
part must be accompanied by an Emergency Plan that J
includes the following information:
4 l
t (1)
Facility description.
A brief description of the I
I 1
licensee's facility and area near the site.
l i
i 1
1 l
j (2)
Types of accidents.
An identification of each type of radioactive materials accident for which 1
q
(
l protective actions may be needed.
4 j
(3)
Classification of accidents.
A classification j
e system for classifying accidents as alerts or site i
area emergencies.'
I i
i (4)
Detection of accidents.
Identification of the 5
means -for detecting -cf appi-caMen accident
~'
condition.
1 l
I i
i l
1 I
j Site Area emergency means events may occur, are in progress, or have occurred that could 2
lead to significant release of radioactive material and that could require a response by effsite respnse crganizations to protect persrp.s effsite.
26 i
- - -. = _.
d of 1986, Title III, Public Law 99-499, if applicable to the applicant's activities at the proposed place of use of the special nuclear i
=aterial.
a j
l' 1
(14) The licensee shall allow the offsite response 9
5 organizations expected to respond in case of an I
t i
accident 60 days to comment on the licensee's l
emergency plan before submitting it to NRC.
The l
i licensee shall provide any comments received within the 60 days to the NRC with the emergency 4
[
plan.
1 (15) Review of applicant's emergency plans shall i
f include the following for potential offsite
)
assistance:
1 i
i (i)
Arrangements for requesting and effectively i
)
l using offsite assistance on site have been made, arrangements to accommodate State and local staff at the licensee's near-site l
l l
emergency facility have been made, and other
\\
l organizations capable of augmenting the i
j planned onsite response have been identified.
J l
la i
l (ii) Provisions exist for prompt commudcations i
among principal response organizations to i
i J
30 i
i
_.-