ML20205Q604
| ML20205Q604 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/31/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205Q605 | List: |
| References | |
| TAC-61607, TAC-64095, NUDOCS 8704030579 | |
| Download: ML20205Q604 (10) | |
Text
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,(f arsg'c UNITED STATES
,,.(f'g NUCLEAR REGULATORY COMMISSION 2
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MISSISSIPPI POVER & LIGHT COMPANY SYSTEM ENERGY RESOURCES. INC.
SOUTH MI55155IFP1 ELECTRIC POWER ASSOCIATION DOCKET 00. 50 416 GRAND GULF NUCLEAR STATION, UNIT 1 AFENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No NPF-29 l
1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by Mississippi Power & Light Company, System Energy Resources, Inc. (formerly Middle South Energy, Inc.)
and South Mississippi Electric Power Association, (the licensees) dated May 28, 1986 as amended November 11, 1986 and February 13, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1987, complies with the standards and re
, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The fecility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 if this amendment will not be inimical to the common defense and se:urity 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'; regulations and all applicable requirements have been 3atisfied.
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:
_ Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, is tsvised through Amendment No. 31, are hereby incorporated into thh license.
System Energy Resources. Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8704030579 870331 PDR ADOCK 05000416 P
' 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director BWR Project Directorate No..4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of' Issuance: March 31, 1987 4
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (L
Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technicel Specifications Date cf Issuancc:
March 31, 1987 l
l i
I ATTACHMENT TO LICENSE ANENDMENT NO. 31 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. Overleaf page(s) provided to maintain document completeness.*
Remove Insert 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 8 3/4 6-3 e 3/4 6-3 8 3/4 6-4 B 3/4 6-4*
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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.
ACTION:
Without DRYWELL INTEGRITY, restore DRYWELL 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 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 during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.4-1 of Specification 3.6.4.
b.
By verifying the drywell air lock is in compliance with the l
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.
"See Special Test Exception 3.10.1.
nnExcept 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 l
CONTAINMENT SYSTEMS-DRYWELL BYPASS' LEAKAGE-
. LIMITING CONDITION r0R OPERATION 3.6.2.2 Drywell bypass leakage lshall be less than or equal to 10% of the acceptable A/Jk design value of 0.90 fts,-
t APPLICABILITY: When DRYWELL INTEGRITY is required per Specification 3.6.2.1.
l ACTION:
With the drywell bypass leakage greater than 10% of the acceptable A/Jii design value of 0.90 ft, restore the drywell bypass leakage.to within the limit 2
prior to increasing reactor coolant system temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The drywell bypass leakage rate test shall be conducted at least.once per 18 months at an initial differential pressure of 3.0 psid and the A/Jk shall be calculated from the measured leakage. One drywell airlock door shall remain open during the drywell-leakage test such that each drywell door is leak tested during at least every other drywell leakage rate test.
If any drywell bypass leakage rate test fails to meet the specified a.
limit, the test schedule for subsequent tests shall be reviewed and approved by the-Commission. If two consecutive tests fail to meet the limit, a test shall be performed at least once every 9 months until two consecutive tests meet the limit, at which time the above test schedule may be resumed.
b.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.2.3.
c.
The provisions of Specification 4.0.2 are not applicable.
i GRAND GULF-
'T 1 3/4 6-14
4 CONTAINMENT SYSTEMS DRYWELL AIR LOCK l
LIMITING CONDITION FOR OPERATION 3.6.2.3 The drywell air lock shall be OPERABLE with:
l a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the drywell, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than or equal to 2 scf per hour at P,, 11.5 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.
ACTION:
a.
With one drywell air lock door inoperable:
1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed. Operation may then continue provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days. Otherwise, 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 />.
2.
The provisions of Specification 3.0.4 are not applicable.
b.
With the drywell air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 />.
c.
With one drywell air lock door inflatable seal system seal pressure instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 7 days or verify the associated inflatable seal pressure to be > 60 psig at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
See Special Test Exception 3.10.1.
GRAND GULF-UNIT 1 3/4 6-15 Amendment No. 31 l
i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS l
l 4.6.2.3 The drywell air lock shall be demonstrated OPERABLE:
l Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> # after each closing, except when the air lock is being a.
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 seal leakage rate less than or equal to 2 scf per hour when the gap between the door seals is pressurized to P,, 11.5 psig.
b.
By conducting an overall air lock leakage test at P,,11.5 psig and verifying that the overall air lock leakage rate is within its limit:
1.
Each COLD SHUTDOWN if not performed within the previous 6 months #
l 2.
Prior to establishing DRYWELL INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.
c.
At least once per 18 months by verifying that only one door in the l
air lock can be opened at a time.
d.
By verifying each airlock door inflatable seal system OPERABLE by:
1.
Demonstrating each of the two inflatable seal pressure instrumentation channels per airlock door OPERABLE by performance of a:
a)
CHANNEL FUNCTIONAL TEST at least once per 18 months, and l
b)
CHANNEL CALIBRATION at least once per 18 months, with a low pressure setpoint of > 60 psig.
l 2.
At least once per 7 days verifying seal air flask pressure to be greater than or equal to 90 psig.
3.
At least once per 18 months, conducting a seal pneumatic system l
leak test and verifying that system pressure does not decay more than 2 psig from 90 psig within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- The provisions of Specification 4.0.2 are not applicable.
GRAND GULF-UNIT 1 3/4 6-16 Amendment No. 31 l
t I
I CONTAINMENT SYSTEMS BASES f
CONTAINMENT PURGE SYSTEM (Continued) i 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 1
j gross leakage failures develop. The 0.60 L, leaking limit shall not be j'
exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and i
l penetrations subject to Type B and C tests.
[
3/4.6.2 DRWELL
{
3/4.6.2.1 DRWELL INTEGRITY l
Drywell integrity ensures that the steam released for the full spectrum l
of drywell pipe breaks is condensed inside the primary containment either by i
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 DRWELL BYPASS LEAKAGE The limitation on drywell bypass leakage rate ensures that the maximum leakage l
which could bypass the suppression pool during an accident would not result in the containment exceeding its design pressure of 15.0 psig. The desi n drywell leakage rate is expressed a A/# and has a value of 0.90 ft2 A/
is dependent only on the geometr of drywell leakage paths where A = flow area of leakage paths in ft2 and 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 A/ 4 of 0.90 ft2 has an equivalent mass flow of 35,000 scfm. The integrated drywell leakage value is i
limited to 10% of the allowable drywell leakage capability, which is equivalent to 3500 scfm at 3 psid drywell to containment.
The A/8 value of 0.90 ft2 is derived from the analysis of " bypass capability 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 i
not automatically result in a reactor depressurization. The long term differen-tial pressure created between the drywell and containment will result in a signi-
{
ficant pressure buildup in the containment due to this bypass leakage.
l 3/4.6.2.3 DRWELL AIR LOCK
)
The limitations on closure for the drywell air lock are required to meet the restrictions on DRWELL INTEGRITY and the drywell leakage rate given in i
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 I
1 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.
l l
Verification that each air lock door inflatable seal system is OPERABLE i
by the performance of a local leak-detection test for a period of less than l
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is permissible if it can be demonstrated that the leakage rate can be accurately determined for this shorter period. This is in accordance with Sections 6.4 and 7.6 of ANSI N45.4-1972.
GRAND GULF-UNIT 1 B 3/4 6-3 Amendment No. 31 i
..,._ __. _ _,_.~ _,..,- _._..-,_..- _.
CONTAINMENT SYSTEMS BASES 3/4.6.2.4 DRYWELL 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 DRYWELL INTERNAL PRESSURE 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 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that peak f
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 DRYWELL 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 OPERATIONAL 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 drywell pressure remains below the GRAND GULF-UNIT 1 B 3/4 6-4
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