ML20106C841
| ML20106C841 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/05/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20106C845 | List: |
| References | |
| TAC-52178, TAC-52179, TAC-52327, TAC-52330, NUDOCS 8410240361 | |
| Download: ML20106C841 (19) | |
Text
"
oq#o ma ato UNITED STATES g
NUCLEAR REGULATORY COMMISSION r
o h'
WASHINGTON, D. C. 20555
\\...../
DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
's-Amendment No. 36 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF 9 filed by the Duke Power Company (licensee) dated August 2, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amer.dment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
P I
~
2-
~
(2)TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 36, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s.
U
-84 &
Elinor G. Adensam, Chief
,\\-
Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: October 5, 1984 4
l S
e 4.
e se e
-~
m
._,.m,
--._m
o nee:
'/
o,,
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION c.
h E
WASHINGTON, D. C. 20555
\\*.../
DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
\\-
Amendment No,17 License No. NPF-17
~
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amehdment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated August 2, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as aniended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's reg'ulations set.forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied, 2.
Accordingly, the li' cense is hereby amended by page changes to the Technical i
l Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.17, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Yee =
Elinor G. Adensam, Chief Licensing Branch No. 4 Y
Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: October 5, 1984 k
e
ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO.17 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 N.
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendrent number and contain a vertical line indicating the area of change. The corresponding over-leaf pages are also provided to' maintain document completeness.
Amended Overleaf Page Page 3/4 6-1 3/4 6-7 3/4 6-8 3/4 6-9 3/4 6-9a 3/4 6-11 3/4 6-12 3/4 6-33 3/4 6-34 3/4 6-37 3/4 6-38 9 %
1 i
l l
l
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES l', 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INT'EGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3; b.
By verifying.that each containment air lock is in compliance with Specification 3.6.1.3; and c.
After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P,these seals is, 14.8 psig, and verifying that when the measured leakage rate for added to the leakage rates determined pursuant to Specification 4.6.1.2d.
for all other Type B and C penetrations, the combined leakage rate is less than 0.60 L,.
m Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and the annulus and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
Amendment No.17 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-1 Amendment No.36 (Unit 1)
=
l TABLE 3.6'1 (Continued) 2 "g
SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS E
m PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE C
h M390 Containment Ventilation Cooling m
Water Out Turbine Building Type C w
M279 Containment Ventilation Cooling E
. Water Out Turbine Building f
Type C i
ro M220 Instrument Air Auxiliary Building Type C M219 Station Air Auxiliary Building Type C M215 Breathing Air Auxiliary Building Type C M378 Containment Sample Out Auxiliary Building
~ Type C m
M325 Containment Sample In Auxiliary Building Type C M358 Refueling Cavity to RW Pump Auxiliary Building Type C M377 Refueling Cavity From RW Tank Auxiliary Building Type C M331 Hydrogen Purge In Atmosphere Type C M326 RCP Motor Drain Tank Pump to Waste Oil Storage Auxiliary Building Type C M221 Containment Ventilation Units Condenser Drains to Condenser Drain Tank Auxiliary Building Type C M359 Instrument Air Auxiliary Building Type.C M386 Instrument Air Auxiliary Building Type C
~
TABLE 3.6-1 (Continued) y E
SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS E
PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE E
]
M317 Instrurcent Air Auxiliary Building Type C M243 Containment Air Release Auxiliary Building Type C 9" -
M384 Containment Air, Addition Auxiliary Building f-Type C
~
M361 Reactor Coolant Pump Motor Oil Supply Auxiliary Building '
Type C M353 Fire Protection Header Auxiliary Byi'iding Type C M376 Component Cooling Water to Auxiliary Building Type C if Reactor Coolant Drain Tank Heat Exchanger T*
M355 Component Cooling Water from Auxiliary Building Type C Reactor Coolant Drain Tank Heat Exchanger M327 Component Cooling Water to Auxiliary Building Type C Reactor Vessel Support Coolers and RCP Coolers 32 EE M320 Component Cooling Water from Auxiliary Building Type C 22 Reactor Vessel Support 55 Coolers and RCP Coolers zz
??
Flued Head to Guard Pipe Atmosphere, or we Welds on all Hot Auxiliary Building, A2 Penetrations or Turbine Building EE l
M412 Equipment Hatch Atmosphere Type C
==
- Pursuant to Specification 4.6.1.2f.
TABLE 3.6-1(Continued)
~
2 g
5 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS A
PENETRATION TEST NUMBER SERVICE RELEASE LOCATION TYPE 3
M280 Sample from Accumulator Auxiliary Building Type C
[
M342 Auxiliary Seal Injection Auxiliary Building Type C g
Line from Annulus to Reactor. Coolant Pumps
~
f y
M394 Ice froin Rotary Valve Auxiliary Building Type C Assembly to Ice Condenser Cyclone Receiver
-r '
M255 ILRT Pressure Impulse Line Auxiliary Building Type C
{
M323
- Cont. Rad. Monitors Auxiliary Building Type C EMF-38, 39, 40 M118 Cont. Press Monitors Auxiliary Building Type C M118 ILRT Press Impulse Line (Unit 2)
Auxiliary Building Type C
~
,M239 Cont. Press Monitors Auxiliary Building Type C pp M239 Cont. Hydrogen Monitor "A" Train Auxiliary Building Type C M313 Cont. Press Monitors ' ;
Auxiliary Building Type C S5 M402 Cont. Press Monitors Auxiliary Building Type C zz
?-
Cont. Hydrogen Monitor "B" Train Auxiliary Building Type C MC
+
t gg M392 Air to Upper PAL Aux Bldg #
Auxiliary Building Type C Side Door Seals gg
. f ','
ee
~
~m-M152 Air to Lower PAL Aux Bldg Auxiliary Building Type C e
. Side Door Seals s
r 7
i
/
TABLE 3.d(Continued)
~
i 4
2 J
- g r, j, g 5 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS
/
PENETRATION TEST
/,
NUMBER SERVICE RELEASE LOCATION TYPE 5
'd Cont. Press. Monitor -
Auxiliary Building Type C Narrow Range o.g M354 Fuel Transfer Tube Auxiliary Building Type B ro f
?
C1 C.
22 aa EE S6 22 E. S.
ee
/
'CONTA"INMENT SYSTEMS SURVEILLANCE REQUIREMENTS-s 4.6.1.3 Each containment air lock shall be demon' trated OPERABLE:
s a.
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when-the air lock is being used for_ multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that the seal leakage is 1ess than 0.01 L as determined by precision flow measurements when near,ured for at le$st 30 seconds
~
with the volume between tne seals at a constant pressure of 14.8 psig, b.
By conductihg overall air lock leakage tests at not less than P,,
14.8 psig, and verifying the overall air lock leakage rate is within its limit:
- 1) At least once pek6 months, # anc '
- 2) Prior to establishing CONTAINMENT INTEORITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.*
c.
At least cnce per 6 months by verifying that only one door in each air lock can be opened at a time, and d.
At least once per 6 months by conducting a pressure test to verify door seal integrity, with a measured leak rate of less than
+
15 standard cubic centimeters per minute.
The provisions of Specification 4.0.2 are not applicable.
- This constitutes an exemption to Appendix J of 10 CFR 50.
I Amendment No.17(Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-11 Amendment No.36(Unit 1) l
' CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between
-0.3 and +0.3 psig.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hpd in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i-SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 McGUIRE - UNITS 1 and 2 3/4 6-12
' CONTAINMENT SYSTEMS HYDPOGEN CONTROL DISTRIBUTED IGNITION SYSTEM'
. LIMITING CONDITION FOR OPERATION 3.6.4.3 Both trains of the Hydrogen Mitigation System shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one train of the' Hydrogen Mitigation System inoperable, restore the inoperable system to OPERABLE status within 7 drys or increase the surveillance interval of Specification 4.6.4.3.a from 92 days to 7 days on the OPERABLE train until the inoperable train is returned to OPERABLE status.
\\-
SURVEILLANCE REQUIREMENTS 4.6.4.3 Each train of the Hydrogen Mitigation System shall be demonstrated OPERABLE:
a.
At least once per 92 days by energizing the supply breakers and verifying that at least 32 of 33 igniters are energized,* and b.
At least once per 18 months by verifying the temperature of each igniter is a minimum of 1700*F.
A Inoperable igniters must not be on corresponding redundant circuits which provide coverage for the same region.
Amendment No.17 (Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-33 Amendment No.36(Unit 1)
CONTAINMENT SYSTEMS 3/4.5.5 ICE CONDENSER ICE BED LIMITING CONDITION FOR OPERATION 3.6.5.1 The ice bed shall be OPERABLE with:
The stored ice having a boron ecocentration of at least 1800 ppm a.
boron as sodium tetraborate and a pH of 9.0 to 9.5, b.
Flow channels through the ice condenser, A maximum ice bed temperature of less than or equal to 27"F, c.
\\-
d.
A total ice weight of at least 2,466,420 pounds at a 95% level of confidence, and e.
1944 ice baskets.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT-00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.1 The ice condenser shall be determined OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using the Ice Bed Temperature a.
Monitoring System to verify that the maximum ice bed temperature is less than or equal to 27*F, b.
At least once per 9 months by:
1)
Chemical analyses which verify that at least nine representative samples of stored ice have a boron concentration of at least 1800 ppm as sodium tetraborate and a pH of 9.0 to 9.5 at 20*C; 2)
Weighing a. representative sample of at least 144 ice baskets and verifying that each basket contains at least 1269 lbs of ice.
The representative sample shall include 6 baskets from each of the 24 ice condenser bays and shall be constituted of i
McGUIRE - UNITS 1 and 2 3/4 6-34
CONTAINMENT SYSTEMS l
ICE CONDENSER DOORS LIMITING CONDITION FOR OPERATION 3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
N, With one or more ice condenser doors open or otherwise inoperable, POWER OPERATION may continue for up to 14 days provided the ice bed temperature is monitored at least r;nce per 4 hpurs and the maximum ice bed temperature is maintained less than or. equal to.27*F; otherwise, restore the doors to their s
closed positions or OPERABLE status (as applicable) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.3.1 Inlet Doors - Ice condenser inlet doors shall be:
a.
Continuously monitored and determined closed by the inlet door position monitoring system, and b.
Demonstrated OPERABLE during shutdown at least once per 9 months by:
1)
Verifying that the torque required to initially open each door is less than or equal to 675 inch pounds; 2)
Verifying that opening of each door is not impaired by ice, frost or debris; 3)
Testing a sample of at least 50% of the doors and verifying that.the torque required to open each door is less than 195 inch pounds when the door is 40 degrees open.
This torque is defined as the " door opening torque" and is equal to the nominal door torque plus a frictional torque component.
The doors selected for determination of the " door opening torque" shall be selected to ensure that all doors are tested at least once during two test intervals; i
Amendment No.17(Unit 2)
McGUIRE - UNITS 1 and 2 3/4 6-37 Amendment No.36(Unit 1)
' CONTNINMENTSYSTEMS SURVEILLANCE REQUIREMENTS'(Continued) 4)
Testing a sample of at least 50% of the doors and verifying that the torque required to keep each door from closing is greater than 78 inch pounds when the door is 40 degrees open.
This torque is defined as the " door closing torque" and is equal to the nominal door torque minus a frictional torque component.
The doors selected for determination of the " door closing torque" shall be selected to ensure that all doors are tested At least once during two test intervals; and 5)
Calculation of the frictional torque of each door tested in accordance with 3) and 4), above.
The calculated frictional torque shall be,less than or equal to 40 inch pounds.
\\-
4.6.5.3.1 Intermediate Deck Doors - Each ice condenser intermediate deck door shall be:
a.
Verified closed and free of frost accumulation by a visual inspection at least once per 7 days, and b.
Demonstrated OPERABLE at least once per 3 months during the first year after the ice bed is fully loaded and at least once per 18 months thereafter by visually verifying no structural deterioration, by verifying free movement of the vent assemblies, and by ascertain-ing free movement when lifted with the applicable force shown below:
Door Lifting Force 1)
Adjacent to crane wall Equal to or less than 37.4 lbs, 2)
Paired with door adjacent to crane wall Equal to or less than 33.8 lbs, 3)
Adjacent to containment wall Equal to or less than 31.8 lbs,
~.
and 4)
Paired with door adjacent to containment wall Equal to or less than 31.0 lbs.
4.6.5.3.3 Top Deck Doors - Each ice cor. denser top deck door shall be deter-mined closed and OPERABLE at least once per 92 days by visually verifying:
a.
.That the doors are in place.,'and b.
That no condensation, frost, or ice has formed on the doors or blankets which would restrict their lifting and opening if required.
Amendment No.17(Unit 2)
McGUIRE - UNIT 5 1 and 2 3/4 6-38 Amendment No. 36(Unit 1) l
7590-01 0
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of DUKE POWER COMPANY Docket Nos. 50-369 and 50-370 (McGuire Nuclear Station, Units 1 and 2)
EXEMPTION I.
Duke Power Company (the ligensee) is the holder of Facility Operating Licenses NPF-9 and NPF-17 which authorize the operation of the McGuire Nuclear Station, Units 1 and 2 (the facilities). The licenses provide, among other things, that they are subject to all rules, regulations, and Orders of the Nuclear Regulatory Commission (the Commission). The facilities comprise two pressurized water reactors at the licensee's site in Mecklenburg County, North Carolina.
II.
10 CFR 50, Appendix J, paragraph III.D.2(b)(ii) of the Commission's regula-tions requires overall containment airlock tests to be performed if an airlock is opened during Modes 5 or 6.
An overall airlock leakage test at not less than P, must be conducted prior to plant heatup and startup (i.e., entering Mode 4).
l III.
By letter dated August 2, 1983, the licensee requested a change in the McGuire Nuclear Station Technical Specification 4.6.1.3.b which currently requires overall containment airlock leakage tests to be performed "...if opened when CONTAINMENT INTEGRITY was not required...." The proposed change 9
~
\\
would be to require the overall airlock leakage test to be performed "... when maintenance has been performed on the airlock that could affect the airlock sealing capability." This change requires an exemption from the requirements of Appendix J, to 10 CFR 50.
The existing airlock doors are so designed that a full pressure, i.e.,
(14.8 psig), test of in entire airlock can only be performed after strong backs (structural bracing) have been installed on the inner door.
Strong backs are neededsincethepressureexertgdontheinnerdoorduringthetestisina direction opposite to that of the accident pressure direction.
Installing strong backs, performing the test, and removing strong backs requires at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per airlock (there are 2 airlocks) during which access through the airlock is prohibited.
If the periodic 6-month test of paragraph III.D.2(b)(i) of Appendix J and the test required by paragraph III.D.2(b)(iii) of Appendix J are current, no maintenance has been performed on the airlock, and the airlock is properly sealed, there should be no reason to expect the airlock to leak excessively just because it has been opened in Mode 5 or Mode 6.
Accordingly, the staff
,f.inds that the licensee's proposed approach of relying on the seal leakage test of paragraph III.D.2(b)(iii) of Appendix J is acceptable when no mainte-nance has been performed on an airlock, and will.not adversely affect maintaining containment integrity. Whenever mair.tenance has been performed on an airlock, the test requirement of paragraph III.D.2(b)(ii) of Appendix J must still be met.
IV.
Accordingly, the Commission has determined that an exemption in accordance with 10 CFR 50.12 is authorized by law, will mot endanger life or property or
O
- the common defense and security and is otherwise in the public interest. There-fore, the requested exemption from the containment airlock test requirements of 10 CFR Part 50, Appendix J Section III.D.2(b)(ii) is hereby granted.
Pursuant to 10 CFR 51.32, the Commission has determined that the issuance of this exemption will have no significant impact on the environment (49 FR 38425),
This exemption ii effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'\\-
,p s
r s'enhu,
i r o
Division of icensing Office of Nuclear Reactor Regulation i
Dated at Bethesda, Marvland this 5th day of October 1984 o
9
_ _. _ _ _ _ _ _ _ _ _. _ _ _ _.. _... _ _. _ _