ML17054B715
| ML17054B715 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/11/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054B716 | List: |
| References | |
| DPR-63-A-073 NUDOCS 8506240205 | |
| Download: ML17054B715 (42) | |
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l UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAMK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No'.
73 License No. DPR-63 1.
The Nuclear Regulatory Commission !the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated October 1, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-63 is hereby amended to read as follows:
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(2) Technical S ecifications The Technical Specifications contained in Appendix A as revised through Amendment No.
73
, is hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NU EAR REGULATORY COMMISSION
Attachment:
Chances to the Technical Specifications Date of Issuance:
June ll, 1985 Domeni c B. Vassal lo, Chi ef Operating Reactors Branch k2 Division of Licensing
4
ATTACHMENT TO LICENSE AMENDMENT NO.
73 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing and inserting the following pages:
Existing
~Pa e
173 174 175 176 177 178 178a 178b 178c 188 190 Revised
~Pa e
173 174 175 176 177 178 178a 178b 178c 188 190 19Oa 232d 232e
LIMITING CONOITION FOR OPERATION SURVEILLANCE REQUIREMENT EMERGENCY VENTILATION SYSTEM
~Ap 1 ic ab i 1 ity:
Applies to the operating status of the emergency ventilation system.
Objective:
To assure the capability of the emergency ventilation system to minimize the release of radioactivity to the environment in the event of an incident within the primary containment or reactor building.
Specification:
a.
Except as specified in Specification 3.4.4e below, both circuits of the emergency ventilation system and the diesel generators required for operation of such circuits shall be operable at all times when secondary containment irrtegrity is required.
b.
The results of the in-place cold 00P and halogenated hydrocarbon tests at design flows on HEPA filters and charcoal adsorber banks shall showh99X 00P removal and>99K halogenated hydrocarbon removal when tested in accordance with ANSI N.510-1980.
4.4.4 EMERGENCY VENTILATION SYSTEM Applicability:
Applies to the testing of the emergency ventilation system.
Ob)ective:
To assure the operability of the emergency ven tilation system.
Specification:
Emergency ventilation system survei 1 1 ance shall be performed as indicated below:
a.
At least once per operating cycle, not to exceed 24 months, the following conditions shall be demonstrated:
('l)
Pressure drop across the combined HEPA filters and charcoal adsorber banks is.less than 6 inches of water at the system rated flow rate
(+ 10K).
(2)
Operability of inlet heater at rated power when tested in accordance with ANSI N.510-1980.
Amendment No. 73 173
LIMITING CONDITION FOR OPERATION SURVEILLANCE RE UIREMENT c.
The results of laboratory carbon sample analysis shall show ~90% radioactive methyl iodide removal when tested in accordance with ANSI N.510-1980 at 80'C and 9M R.H.
d.
Fans shall be shown to operate within
+ 10K design flow.
e.
From and after the date that one circuit of the emergency ventilation system is made or found to be inoperable for any reason, reactor operation and fuel handling is permissible only during the succeeding seven days unless such circuit is sooner made operable, provided that during such seven days all active components of the other emergency ventilation circuit shall be operable.
- f..If these conditions cannot be met,-
within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, the reactor shall be placed in a condition for which the emergency ventilation system is not required.
b.
C.
d.
e.
The tests and sample analysis of Specification 3.4.4b, c and d shall be performed at least once per operating cycle or once every 24 months, or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation, whichever occurs first or following significant painting, fire or chemical release in any ventilation zone coomunicating with the.system.
Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing.
Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.
Each circuit shall be operated with the inlet heater on at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
Test sealing of gaskets for housing doors downstream of the HEPA filters and charcoal adsorbers shall be performed at and in conformance with each test performed for compliance with Specification 4.4.4b and Specification Amendment No. 73 174
LIMITING CONDITION FOR OPERATION SURVEILLANCE RE UIREHENT g.
At least once per operating cycle, not to exceed 24 months, automatic initiation of each branch of the emergency ventilation system shall be demonstrated.
h.
At least once per operating cycle, not to exceed 24 months, manual operability of the bypass valve for filter cooling shall be demonstrated.
i/hen one circuit of the emergency ventilation system becomes inoperable all active components in the other emergency ventilation circuit shall be demonstrated to be operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and daily thereafter.
Amendment No. 73 175
0
BASES FOR 3.4.4 AND 4.4.4 EMERGENCY VENTILATION SYSTEM The emergency ventilation system is designed to filter and exhaust the reactor building atmosphere to the stack durin secondary containment isolation conditions.
Both emergency ventilation system fans are designed to automaticall start upon high radiation ln the reactor building ventilation duct or at th f li 1 tf' y
reactor building pressure to the design negative pressure so as to minimize i -1 k
Sh ld e re ue ng p a
orm and to maintain the
- start, the redundant system is designed to start automatically.
Each of the two fans has 100 percent capacity
'n-ea age.
ou one system fail to High efficiency particulate absolute (HEPA) filters 'are installed before and ft th h
1 p
ential release of particulates to the environment and to prevent clogging of th d'
b ot n
a er e c arcoa adsorbers to minimize adsorbers are installed to reduce the potential release of radioiodine to th environment.
The in-place test results gging o e io ine adsorbers.
The charcoal efficienc of at least should indicate a system leak tightness of less than 1 percent bypass leaka e for th h
1 d
y eas 99 percent remomval of OOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the HEPA filters and charcoal adsorbers are as specified th lt d
the 10 1
CFR 00 guidelines for the accidents analyzed.
Operation of the fans significantly different from the desi n
flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
Only one of the two emergency ventilation systems is needed to cleanup the reactor building atmosphere upon containoent isolation.
If one system is found to be inoperable, there is no iomediate threat to the containment system performance and r eactor operation or refueling operation may contin e
h 1
u w
s e repairs are e)ng made.
If neither c rcuit ss operable, the plant is brought to a condition where the emergency ventilation system is not required desi n flow rate will i di Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6
f t
t h
g i
in icate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
e an inc es o
water at the system capability.
Heater capability and pressure drop should be determined at least once per operati 1
t h
t p
pera ing cyc e
o s ow system performance The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated.
The charcoal adsorber efficiency test procedures should ll f
th 1
tra a
ow or e remova of one adsorber sam 1y, emptying of one bed from the tray, mixing the adsorbent thoroughly and obta 1
t t ain>ng a
eas two samples.
Each unacce table all ad o b p e should be at least two inches in diameter and a lenqth equal to the thickne f th b
d If p
dsorbent in the system shall be replaced with an adsorbent qualified in Table 5-1 of ANSI 509-1980 ness o
e e
I test results are Amendment No.
73 176
BASES FOR 3.4.4 AND 4.4.4 EMERGENCY VENTILATION SYSTEM The replacement charcoal for the adsorber tray removed for the test should meet the same adsorbent quality.
Any HEPA filters found defective shall be replaced with filters qualified pursuant to ANSI 509-1980.
All elements of the heater should be demonstrated to be functional and operable during the test of heater capacity.
Operation of the inlet heater will prevent moisture buildup in the filters and adsorber system.
With doors closed and fan in operation, 00P aerosol shall be sprayed externally along the full linear periphery of each respective door to check the gasket seal.
Any detection of DOP in the fan exhaust shall be considered an unacceptable test result and the gaskets repairs and test repeated.
If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational use.
The determination of significant shall be made by the operator on duty at the time of the incident.
Knowledgeable staff members should be consulted prior to making this determination.
Demonstration of the automatic initiation capability and operability of filter cooling is necessary to assure system performance capability.
If one emergency ventilation system is inoperable, the other system must be tested daily.
This substantiates the availability of the operable system and thus reactor operation or refueling operation may continue during this period of time.
Amendment No. 73 177
LIMITING CONnr TION FOR OPERATION SURVEILLANCE RE UIREMENT 3.4.5 CONTROL ROOM AIR TREATMENT SYSTEM 4.4.5 CONTROL ROOM AIR TREATMENT SYSTEM
. Applies to the operating status of the control room air treatment system.
Objective:
To assure the capability of the control room air treatment system to minimize the amount of radioactivity or other gases entering the control room in the event of an incident.
Applicability:
Applies to the testing of the control r oom air treatment system.
Objective:
To assure the operability of the control room air treatment system.
Specification:
a.
Except as specified in Specification 3.4.5e below, the control room air treatment system and the diesel generators required for operation of this system shall be operable at all times when containment integrity is required.
b.
The results of the in-place cold DOP and halogenated hydrocarbon test desiqn flows on NEPA filters and charcoal adsorber banks shall show>99K DOP removal and Z 99K halogenated hydrocarbon removal when tested in accordance with ANSI N.510-1980.
Specification:
a.
At least once per operating cycle, or once every 24 months, whichever occurs first, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow rate
(+10%).
b.
The tests and sample analysis of Specification 3.4.5b, c
and d shall be performed at least once per operating cycle or once every 24 months, or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation, whichever occurs first or following siqnificant painting, fire or chemical release in any ventilation zone communicating with the system.
Amendment No. 73 178
0
LIMITING CONOITION FOR OPERATION SURVEILLANCE RE UIREHENT Specification:
c.
The results of laboratory carbon sample analysis shall show ~ 90K radioactive methyl iodide removal when tested in accordance with ANSI N.510-1980 at 80'C and 95K R.H.
d.
Fans shall be shown to operate within + 10K design flow.
e.
From and after the date that the control room air treatment system is made or found to be inoperable for any reason, reactor operation or refueling operations is permissible only during the succeeding seven days unless the system is sooner made operable.
f.
If these conditions cannot be met, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for reactor operations and refueling operations shall be terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Specification:
c.
Cold DOP testing shall be performed after each complete or partial replacement of the IlEPA filter bank or after any structural maintenance on the system housing.
d.
Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal absorber bank or after any structural maintenance on the system housing.
e.
The system shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
f.
At least once per operating cycle, not to exceed 24 months, automatic initiation of the control room air treatment system shall be demonstrated.
Amendment No. 73 178a
BASES FOR 3.4.5 AND 4.4.5 CONTROL ROOM AIR TREATMENT SYSTEM The control room air treatment system is designed to filter the control room atmosphere for intake air.
A roughing filter is used for recirculation flow during normal control room air treatment operation.
The control room air treatment system is designed to automatically start upon receipt of a high radiation signal from one of the two radiation monitors located on the ventilation intake and to maintain the control room pressure to the design positive pressure so that all leakage should be out leakage.
High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room.
The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorber s
and a HEPA efficiency of at least 99 percent removal of DOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, adequate radiation protection will be provided such that resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10CFR Part 50.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, there is no ieoediate threat to the control room and reactor oper ation or refueling operation may continue for a limited period of time while repairs are being made.
If the makeup system cannot be repaired within seven
- days, the reactor is shutdown and brought to cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or refueling operations are terminated.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
In addition, air intake radiation monitors will be calibrated and functionally tested each operating cycle, not to exceed 24 months, to verify system performance.
The frequency of tests and sample analysis are necessary to show the HEPA filters and charcoal adsorbers can perform as evaluated.
The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thorouqhly and obtaining at least two samples.
Each sample should be at least two inches in diameter and a length equal to the thickness of the bed.
If test results are unacceptable, all adsorbent in the system shall be replaced with an absorbent qualified according to Table 5-1 of ANSI 509-1980.
The replacement charcoal for the adsorber tray removed for the test should Amendment No. 73 178b
I
BASES FOR 3.4.5 AND 4.4.5 CONTROL ROOM AIR TREATMENT SYSTEM (Continued) meet the same adsorbent quality.
Any HEPA filters found defectiv
-pursuant to ANSI 509-1980.
oun efective shall be replaced with filters qualified t
Operation of the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month will demonstrate o erabilit and remove excessive moisture built up on the adsorber If significant painting, fire or chemical release occurs such that the H
P b
o ot tdf th f h
i 1
f f
d df e t 1
Th dt c
em ca s or oreign materials, the same t f tI d
t K
1 d
bl t ff b
q
""'e made 'y the op<<a<<<<n d<<y use.
e e ermination of si nificant shal e s a
mern ers should be consulted prior to making this determination Amendment No.
73 178c
l
LIMITING CONDITION FOR OPERATION 3.6.2 PROTECTIVE INSTRUMENTATION Appl icab i 1 ity:
Applies to the operability of the plant instrumentation that performs a safety function.
SURVEILLANCE RE(UIREMENT 4.6.2 PROTECTI VE INSTRUMENTATION App 1 icab i 1 ity:
Applies to the surveillance of the instrumentation that performs a safety function.
Objective:
To assure the operability of the instrumentation required for safe operation.
Specification:
The set points, minimum number of trip
- systems, and minimum number of instrument channels that rmst be operable for each position of the reactor mode switch shall be as given in Tables 3.6.2a to 3.6.2m.
Objective:
To verify the operability of protective instrumentation.
Specification:
a.
Sensors and instrument channels shall be checked, tested and calibrated at least as frequently as listed in Tables 4.6.2a to 4.6.2m.
If the requirements of a table are not
- met, the actions listed below for the respective type of instrumentation shall be taken.
(1)
Instrumentation that initiates scram - control rods shall be
- inserted, unless there is no fuel in the reactor vessel.
Amendment No. P7, 73 188
LIMITING CONDITION FOR OPERATION SURVEILLANCE RE UIREMENT (8)
Off-Gas and Vacuum Pump Isolation The respective system shall be isolated or the instrument channel shall be considered inoperable and Specification 3.6.1 shall be applied.
(9)
Diesel Generator Initiation - The diesel generator shall be considered inoperable and Specification 3.6.3 shall be applied.
(10) Emergency Ventilation Initiation - The emerqency ventilation system shall be considered inoperable and Specification 3.4.4 shall be applied.
(ll) High Pressure Coolant Injection Initiation - The high pressure coolant injection system shall be considered inoperable and Specification 3.1.8.c shall be applied.
(12) Primary Containment Monitoring - The primary containment monitoring instrumentation shall be considered inoperable and Specification 3.3.8 shall be applied.
( 13) Control Room Ventilation - The control room ventilation system shall be considered inoperable and Specification 3.4.5 shall he applied.
b.
During operation with a Maximum Total Peaking Factor (MTPF) greater than the design value, either:
Amendment No. 73 190
LIMITING CONOITION FOR OPERATION SURVEILLANCE REQUIREMENT (1}
The APRM scr am and rod block settings shall be reduced to the values given by the equations in Specification 2.1.2.a; or (2}
The power distribution shall be changed such that the MTPF no longer exceeds the design value.
Amendment No. 73 lgOa
Table 3.6.2m CONTROL ROOM AIR TREATMENT SYSTEM INITIATION Limiting Condition for Operation Parameter Minimum No.
of Tripped or Operable Trip Systems Minimum No. of Operable Instrument Channels per Operable Trip System Set Point Reactor Mode Switch Position in Nhich Function Must Be Operable CL 0
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D QJ e
r Cl Cll C7:
Vl CY (1) High Radiation Yentilation Intake
<1000 CPM X
X X
Amendment No. 73
- 232d
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Table 4.6.2m CONTROL ROOM AIR TREATMENT SYSTEM INITIATION Surveillance Requirement Parameter (1) High Radiation Yenti lation Intake Sensor Check Once/shift Instrument Channel Test Once per quarter Instrument Channel Calibration Once each operating cycle not to exceed 24 months Amendment No.
73 232e
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE QF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
73 TO FACILITY OPERATING LICENSE NO.
DPR-63 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 DOCKET NO. 50-220
- 1. 0 INTRODUCTION By application dated October 1, 1984, Niagara Mohawk Power Corporation (the licensee) requested an amendment to Facility Operating License No.
DPR-63 for Nine Mile Point Nuclear Power Station, Unit No.
1.
The amendment request changes the section of the Technical Specifications pertaining to Limiting Conditions for Operations, surveillance requirements and supporting bases for the Emergency Ventilation and Control Room Air Treatment systems and their associated instrumentation.
The majority of the proposed changes are the result of modifications made to the Control Room Air Treatment System to resolve NUREG-0737, Item II.D.3.4, "Control Room Habitability."
2.0 EVALUATION This application for amendment to the operating license by Niagara Mohawk Power Corporation (Nine Mile Point Nuclear Station, Unit No.
- 1) requests that the Technical Specifications relating to the Control Room Air.Treatment System be revised to reflect recent modifications improving that system, to specify surveillance tests according to ANSI N.510-1980 rather than N.510-1975, and to adjust the test frequency to match the present refueling cycle.
These revisions are to be made to Sections 3/4.4.4, 3/4.4.5, and 3/4.6.2 of the Technical Specifications.
The proposed changes are consistent with the accident anlaysis described earlier in the May.21,.3.984 Safety Evaluation (SE) for TMI Item II.D.3.4.
A copy of that SE is attached.
Therefore, the staff finds the proposed revisions to the Nine Mile Point Unit No.
1 Technical Specifications acceptable.
However, during the course of the review a question arose regardiag an inconsistency-between the bases and section 3.4.5 of the Technical Specification.
In particular, the bases for Section 3.4.5 state that the Control Room Air Treatment System is to "maintain the control room pressure
Section 3.4.5 however to the design positive pressure so that all leakage sh ld b t-1 k
ou e ou - ea age."
- owever, does not contain any provision for assuring that the system is capable of achieving design pressure.
This matter was discussed with the licensee in a telecon on April 9, 1985.
The licensee's licensing to assur representative stated that Operational Test Procedur 210 f
e the control room maintains a positive pressure relative to the Further surrounding areas with the fans operating within +105 f th d
o eir esign flow.
the Control
, the licensee has committed to perform additional mod'f t'
rol Room Air Treatment System to enhance its operation at the Sprin i ica ions o
1986 refueling outage.
Following the modifications, the licensee has test with a u
committed to provide a revision to the Technical S
feci ica ion containing a
i a quantative provision for positive pressure relative to outside air with the fans operating within +105 of their design flow.
Considerin the test procedure and the licensee's commitment, the staff f' approach acceptable.
e s a
in s this
- 3. 0 ENVIRONMENTAL CONSIDERATIONS This amendment involves a change in the installati n o f
f 1'
ent located within the restricted area as defined in 10 CFR Part 20,
'o r use o
a aci ity and changes in surveillance requirements.
The staff has determined that the amendment involves no significant increase in the amou t f
ffl y
e released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
Th C
p issued a proposed finding that this amendment involves no significant hazards consideration and there has been n
bl ch finding.
According'ly, this amendment meets the eli~ibilitycriteria
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CFR 51.22 b
no env'r for categorical exclusion set forth in 10 CFR 51.22(c)(9>.
P
(
) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
Me have concluded, based on the considerations discussed above, that (I) there is reasonable assurance that the health and saf t f th bl't be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
J.
Read and R.
Hermann Dated:
June ll, 1985
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~*~S4 Docket No.'50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHWGTON, D. C. 20555 May Zl, 1984 ATTACHHENT Mr. B. G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
Dear Mr. Hooten:
SUBJECT:
SAFETY EYALUATION; NUREG-0?3?,
Item III.D.3.4.,
"Control Room Habitability" Re:
Nine Mile Point Nuclear Station, Unit No.
1 Enclosed is a Safety Evaluation related to the subject it C
d the inclusion of o
the modsficatsons committed to by you, we conclude that the ec i em.
onset ering design meets the criteria for TMI III.D.3.4. set forth in NUREG-0?3?
and is acceptable.
Therefore, this item is considered closed.
Sincerely,
Enclosure:
As stated Domenic B. Vassallo, Chief Operating Reactor Branch 2
Division of Licensing cc w/enclosure See next page
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Nr. B.
G. Hooten Niagara Mohawk Power Corporation Nine Mile Poin. nuclear Station, Unit Ho.
1 CC:
Troy B. Conner, Jr.,
Esquire Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.
W.
Washington, D.
C.
20006 Robert P. Jones, Supervisor Town of Scriba R, D,5'4
- Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:
Nr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 U. S. Environmental Protection Aaency Region II Office Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126
- Lycoming, New York 13093 Jonn W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Thomas A. Murley Regional Administrator Region I Office U. S. Nuclear Regulatory Comnission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223