ML20080L066
| ML20080L066 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/16/1995 |
| From: | Oconnor P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20080L067 | List: |
| References | |
| NUDOCS 9503020055 | |
| Download: ML20080L066 (7) | |
Text
.
O.
UNITED STATES I
o
.. U
.I NUCLEAR REGULATORY COMMISSION
[%...../
WASHINGTON, D.C. 20585 ENTERGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION MISSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-4I6
. GMND GULF NUCLEAR STATION. UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendmont No.119 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated October 22, 1993, as supplemented by letters dated February 10, and 14, 1995, 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; B.
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.
9503020055 950216 PDR ADOCK 05000416 P
r
-2.
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. NPF-29 is hereby amended to read as follows:
l (2). Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.119, are hereby incorperated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of.its date of. issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION Paul W. O'Connor, Senior Project Director Project' Directorate IV-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 16, 1995 i
4 l
l I
l i
i
\\
l ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding 1
overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 1-2a 1-2a 3/4 6-13 3/4 6-13 3/4 6-14 3/4 6-14 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 B 3/4 6-3 B 3/4 6-3 2
t
DEFINITIONS I
DRYWELL INTEGRITY 1.10 DRYWELL INTEGRITY shall exist when:
All drywell penetrations required to be closed during accident a.
conditions are either:
1.
Capable of being closed by an OPERABLE drywell automatic isolation system, or 2.
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as provided in Table 3.6.4-1 of Specification 3.6.4.
b.
The drywell equipment hatch is closed and sealed.
c.
The drywell airlock is in compliance with the requirements of Specification 3.6.2.3.
d.
The drywell leakage rates are within the limits of Specification 3.6.2.1.
l The suppression pool is in compliance with the requirements of e.
Specification 3.6.3.1.
f.
The sealing mechanism associated with each drywell penetration; e.g., welds, bellows or 0-rings, is OPERABLE.
GRAND GULF-UNIT 1 1-2a Amendment No. 106 119 7
CONTAINMENT SYSTEMS 3/4.6.2 DRYWELL DRYWELL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.2.1 DRYWELL INTEGRITY shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
l KJ.IfE:
Without DRYWELL INTEGRITY, restore DRYWELL INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 DRYWELL INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all drywell penetrations **
not capable of being closed by OPERABLE drywell automatic isolation valves and required to be closed :turing accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except for valves that are opened under administrative control as permitted by Specification 3.6.4.
b.
By verifying the drywell air lock is in compliance with the requirements of Specification 3.6.2.3.
c.
By verifying the suppression pool is in compliance with the requirements of Specification 3.6.3.1.
d.
By verifying drywell bypass leakage is less than or equal to 10% of the bypass leakage limit at least once per 18 months.
(Not required to be performed until entry into MODE 2 on the first plant startup from the eighth refueling outage.)
Except valves, blind flanges, and deactivated automatic valves which are located inside the drywell or containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days.
GRAND GULF-UNIT 1 3/4 6-13 Amendment No. 31,102,119 j
CONTAINMENT SYSTEMS DRYWELL BYPASS LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.2.2 Deleted SURVEILLANCE REQUIREMENTS 4.6.2.2 Deleted GRAND GULF-UNIT 1 3/4 6-14 Amendment No.119
=
~
q CONTAINMENT SYSTEM DRYWELL AIR LOCK
}
LIMITING CONDITION FOR OPERATION
~ '
s 3.6.2.3 The drywell airlock shall be OPERABLE.
r APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.
ACTION:
NOTES
]
1.
Entry and exit is permissible to perform repairs of the affected j
atriock components.
2.
Required ACTION a is not applicable if both doors in the airlock are l
inoperable and ACTION c or d is entered.
1 3.
Entry and exit is permissible for 7 days under administrative controls.
l With u.a drywell airlock door inoperable, within I hour, verify the a.
OPERABLE door is closed, and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verified by administrative
)
means to be locked closed at least once per 31 days. Otherwise, enter ACTION d.
s NOTES i
1.
Required ACTION b is not applicable if both doors of the airlock are i
inoperable and ACTION c or d is entered.
2.
Entry and exit is permissible under the control of a dedicated individual.
b.
With the drywell airlock interlock mechanism inoperable, within I hour, verify an OPERABLE door is closed, And within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> lock an OPERABLE door closed. Operation may continue provided that an OPERABLE door is verified by administrative means to be locked closed at least once per 31 days. Otherwise, enter ACTION d.
c.
With the drywell airlock inoperable for reasons other than ACTIONS a or b, immediately initiate action to evaluate drywell overall leakage rate per LCO 3.6.2.1, "Drywell Integrity," using current airlock test results, And within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify a door is closed, And restore airlock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, enter ACTION d.
d.
With the required ACTIONS a, b, or c (including the associated completion times) not met, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and j
in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j
,[
l GRAND GULF-UNIT 3/4 6-15 Amendment No. 69r119 i
-~
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.2.3 The drywell airlock shall be demonstrated OPERABLE:
a.
Deleted b.
By conducting an overall airlock leakage test at 211.5 psig and verifying that the overall airlock leakage rate is s 2 scfh at least once per 18 months.
NOTE Only required to be performed upon entry into drywell.
}
l c.
At least once per 18 months by verifying that only one door in the airlock can be opened at a time.
d.
Deleted 1
1 l
l l
l l
l l
1 I
i l
l l
GRAND GULF-UNIT 1 3/4 6-16 Amendment No. Mil 19 l
l
)
i.
_m
CONTAINMENT SYSTEMS
~
BASES CONTAINMENT PURGE SYSTEM (Continued)
Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failures develop. The 0.60 L leaking limit shall not be exceeded when theleakageratesdeterminedbythelItakageintegritytestsofthesevalvesare added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DRYWELL 3/4.6.2.1 DRYWELL INTEGRITY Drywell integrity ensures that the steam released for the full spectrum of drywell pipe breaks is condensed inside the primary containment either by the suppression pool or by containment spray. By utilizing the suppression pool as a heat sink, energy released to the containment is minimized and the severity of the transient is reduced.
3/4.6.2.2 ORYWELL BYPASS LEAKAGE The limitation on drywell bypass leakage rate ensures that the maximum leakage which could bypass the suppression pool during an accident would not result in the containment exceeding its design pressure of 15.0 psig. The z
design drywell leakage rate is expressed a ANk and has a value of 0.90 ft,
ANk is dependent only on the geometry of drywell leakage paths where A - flow 2
area of leakage paths in ft andVk is a lumped constant which considers geometric and friction loss coefficients such as discontinuities and Reynolds number. At a 3 psid differential pressure from drywell to containment an ANk 2
of 0.90 ft has an equivalent mass flow of 35,000 scfm. The integrated drywell leakage value is limited to 10% of the allowable drywell leakage capability, which is equivaient to 3500 scfm at 3 psid drywell to containment.
The ANk value of 0.90 fta is derived from the analysis of " bypass capabi-lity with containment spray and heat sinks" (FSAR 6.2.1.1.5.5).
The limiting case accident is a very small reactor coolant system break which will not automatically result in a reactor depressurization. The long term differential pressure created between the drywell and containment will result in a signi-ficant pressure buildup in the containment due to this bypass leakage.
3/4.6.2.3 DRYWELL AIR LOCK The limitations on closure for the drywell air lock are required to meet the restrictions on DRYWELL INTEGRITY and the drywell leakage rate given in Specifications 3.6.2.1 and 3.6.2.2.
The specification makes allowances for the fact that there may be long periods of time when the air lock will be in a closed and secured position during reactor operation. Only one closed door in the air lock is required to maintain the integrity of the drywell.
GRAND GULF-UNIT 1 B 3/4 6-3 Amendment No. 3 b119
)
CONTAINMENT SYSTEMS SASES 3/4.6.2.4 ORYWELL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the drywell will be maintained comparable to the original design specification for the life of the unit. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.2.5 DRWELL INTERNAL PRES $URE The limitations on drywell-to-containment differential pressure ensure that the drywell peak pressure of 22.0 psig does not exceed the design pressure of 30.0 psig and that the containment peak pressure of 11.5 psig does not exceed the design pressure of 15.0 psig during LOCA conditions. The maximum external drywell pressure differential is limited to +0.26 psid, well below the 2.3 psid
'at which suppression pool water will be forced over the weir wall and into the drywell. The limit of 2.0 psid for initial positive drywell to containment pressure will not allow clearing of the top vent which is consistent with the safety analysis.
.3/4.6.2.6 DRWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that peak l
drywell temperature does not exceed the design temperature of 330*F during LOCA conditions and is consistent with the safety analysis.
3/4.6.2.7 DRWELL VENT AND PURGE The drywell vent and purge system must be normally maintained closed to eliminate a potential challenge to containment structural integrity due to a steam bypass of the suppression pool.
Intermittent venting of the drywell is allowed for pressure control during OPERATIONAL CONDITIONS.1 and 2, but the cumulative time of venting is limited to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per year. Venting of the drywell is prohibited when either a 6-inch containment supply or exhaust valve or a 20-inch containment purge supply or exhaust valve is open, thus eliminating any resultant direct leakage path from the drywell to the environment..
Intermittent drywell venting and use of the drywell purge mode of the containment cooling system is allowed during 0PERATIONAL CONDITION 3 to reduce the drywell airborne activity levels prior to and during personnel entry periods and to control drywell pressure, but is limited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> of use per 365 days.
3/4.6.3 DEPRESSURIZATION SYSTEMS The specifications of this section ensure that the drywell and containment pressure will not exceed the design pressure of 30 psig and 15 psig, respectively, during primary system blowdown from full operating pressure.
The suppression pool water volume must absorb the associated decay and structural sensible heat released during a reactor blowdown from 1060 psia.
Using conservative parameter inputs, the maximum calculated containment pressure during and following a design basis accident is below the containment design pressure of 15 psig. Similarly the dryvell pressure remains below the GRAND GULF-UNIT 1 8 3/4 6-4
-~
~
~ ' '
-