ML19253B602
| ML19253B602 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/10/1979 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML19253B593 | List: |
| References | |
| NUDOCS 7910160464 | |
| Download: ML19253B602 (6) | |
Text
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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO SPENT FUEL STORAGE MODIFICATION POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OCTOBER 10, 1979 llS4 276 7910160
'4
3.5 (cont'd)
- 4. 5 (cont ' d) b.
From the time that the b.
When it is determined that r%,
LPCI mode is made or found the LPCI mode is inoper-rs,
to be inoperable for any able, both Core Spray rNJ reason, continued reactor Systems, the containment operation is permissible spray subsystem, and the
'9F fl during the succeeding 7 emergency diesel gene-
~~~
days unless the LPCI mode rators shall be
'-~
is made operable earlier demonstrated to be provided that during these operable immediately and 7 days all active daily thereafter.
components of both Core Spray Systems, the containment spray sub-c.
The power source disconnect system (including two RHR and chain lock to motor pumps) and the emergency operated RHR cross-tie valve, diesel generators shall be and lock on manually operated operable.
gate valve shall be inspected once each operating cycle to c.
When the reactor water verify that both valves are temperature is greater than closed and locked.
212 F the motor operator for the RHR cross-tie valve shall be maintained disconnected from its power source.
It shall be main-tained chain-locked in the closed position. The manually operated gate valve in the cross-tie line, in series with the motor operated valve, shall be maintained locked in the closed position.
l 4.
a.
The reactor shall not be started up with the RHR System supplying cooling to the fuel pool.
b.
The RHR System can supply cooling to the spent fuel only when the reactor coolant temperature is below 2120 Amendment No.
115
JArt:PI}
5.0 DESIGN FEATURES B.
The reactor core contains 137 cruciform-shaped control rods 5.1 SITE as described in Section 3.4 of the FSAR.
A.
The James A.
FitzPatrick Nuclear Power Plent is located on the PASNY 5.3 REACTOR PRESSURE VESSEL CC}
portion of the Nine Mile Point site,
[d approximately 3,000 ft. cast of the The reactor pressure vessel is as Nine Mile Point Nuclear Station.
described in Tables 4.2-1 and 4.2-2 The NMP-JAP site is on Lake Ontario of the USAR, The applicable design in Oswego County, New York, approxi-codes are described in Section 4.2 34 mately 7 miles northeast of Oswego.
of the PSAR.
The plant is located at coordinates north 4,819,545.012 m, east 386,968.945 m, 5.4 CONTAINMENT on the Universal Transverse Mercator System.
A.
The principal design parameters and characteristics for the B.
The nearest point on the property primary containment are given in line from the reactor building and Table 5.2-1 of the PSAR.
any points of potential gaseous effluents, with the exception of the B.
The secondary containment is as lake shoreline, is located at the described in Section 5.3 and the northeast corner of the property.
applicable codes are as described This distance is approximately in Section 12.4 of the PSAR.
3,200 ft. and is the radius of the exclusion area ar defined in 10 CPR C.
Penetrations to the primary con-100.3.
tainment and piping passing through such penetrations are designed in 5.2 REACTOR accordance with standards set forth in Section 5.2 of the PSAR.
A.
The reactor core consists of not more than 560 fuel assemblies.
For 5.5 FUEL STORAGE the current cycle three fuel types I
are present in the core:
7x 7, A.
The new fuel stcrage facility design i
8x 8,
and 8x 8R.
These fuel types criteria are to maintain a Kerr dry are described in Section 3.2 of the
<0.90 and flooded <0.95.
Compliance FSAR, NEDO-20360, and NEDO-2401),
shall be verified prior to introduction respectively.
The 7 x 7 f.el has 49 of any new fuel design to this facility.
fuel rods, the 8x8 fuel has 63 fuel rods and 1 water rod, and the 8 x 8R i
fuel has 62 fuel rods and 2 water rods.
i e
245
)dI, 4 3 Arend-ent ':o.
5.5 (cont'd)
JAFNPP B.
The spent fuel storage pool is designed to maintain Kegg
<0.95 under all conditions as described in the Authority's application for spent fuel storage modification transmitted to NRC July 26, 1978.
In order to assure that the criteria is met, new fuel average enrichment will be limited to < 3.3 w/o U-235.
5.6 SEISMIC DESIGN CP' o s I\\l The reactor building and all engineered safeguards are designed on basis of dy-namic analysis using acceleration re-cf sponse spectrum curves which are nor-malized to a ground motion of 0.08 g.
for the Operating Basis Earquake, and 0.15 g, for the Design Baais Earthquake.
Amendment No. 38 246
ATTACHMENT II SUPPORTING INFORMATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES SPENT FUEL STORAGE MODIFICATION POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OCTOBER 10, 1979 IlS4 280
Supporting Information for Proposed Technical Specification Changes Related to Spent Fuel Storage Modifications I.
Requested Change and Bases A.
Section 3.5.A This change is made to provide added assurance that use of the RHR System for spent fuel cooling will not affect the LPCI mode of operation.
B.
Section 5.5 This change is made to reflect reactivity conditions in the new fuel storage area and the spent fuel pool as modified and to provide the basis for establishing compliance.
II.
Safety Evaluation The changes proposed to Technical Specification Sections 3.5.A and 5.5 do not increase the probability of occurance or the consequences of an accident or malfunction of equipment important to safety.
The margin of safety for reactivity in the spent fuel storage pool has not been significantly reduced.
III. References 1.
Letter of July 26, 1978 from P.
J.
Early (Power Authority) to T. A.
Ippolito (NRC) 1154 281
.