ML17222A617
| ML17222A617 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/16/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17222A618 | List: |
| References | |
| NUDOCS 8812220258 | |
| Download: ML17222A617 (9) | |
Text
ggS RICI
~4 io C0 C
O CO 3
0
+n gO
+a*++
~ 0 UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 FLORIDA POMER 5 LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POMER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.36 License No.
NPF-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 8 Light Company, et al. (the licensee),
dated September 7, 1988, 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 COIMIIission; 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. 'he 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.
88i2220258 881216" PDR ADOCK 05000389 PDC
2.
Accordingly, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amendina paragraph 2.C.2 to read as follows:
2.
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
36, are 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 NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 16, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.
36 TO FACILITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pa es 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-9 3/4 6-10 Insert Pa es 3/4. 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-9 3/4 6-10
3/4. 6'ONTAINMENT 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 1", 2", 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, 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 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 RE UIREMENTS
- 4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
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 3.6.4.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6. 1.3.
C.
After each closing of each penetration subject to Type B testing, except containment air locks, if opened following a Tyoe A or B
'est, by leak rate testing the seal with gas at P ','41.8 psig and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specifica" tion 4.6. 1.2d. for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L.
In MODES 1 and 2, the RCB polar crane shall be rendered inoperable by locking the power supply breaker open.
Except valves, blind flanges, and deactivated 'automatic valves which are located inside the containment 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.
ST.
LUCIE - UNIT 2 3/4 6-1 Amendment No.
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6. 1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
Less than or equal to L
, 0.50 percent by weight of the a'ontainment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P
, 41.8 psig, or a'.
C.
2.
Less than or equal to Lt, 0.35 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of Pt, 20.9 psig; A combined leakage rate of less than or equal to 0.60 L for all a
penetrations and valves subject to Type B and C tests, when pressurized to P
A combined bypass. leakage rate of less of than or equal 0.12 L for a
all penetrations identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P
a'PPIICABILITY:
NODES 1, 2, 3, and 4.
ACTION:
f With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L
or 0.75 Lt, as applicable, or (b) with the measured combined a
leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L
, or (c) with the combined bypass leakage rate exceeding a'.12 L, restore the overall integrated leakage rate to less than or equal to 0.75 L
or less than or equal to 0.75 Lt, as applicable, and the combined leakage rate for all-penetrations and valves subject to Type B and C tests to less than or equal to 0.60 L, and the bypass leakage rate to less than or equal to 0. 12 L prior to increasing the Reactor Coolant System temperature a
above 200F.
SURVEILLANCE RE UIREMENTS 4.6. 1.2 The containment leakage, rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50: Using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during ST.
LUCIE - UNIT 2 3/4 6-2 Amendment No. 36
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued) shutdown at either P
, 41.8 psig or at Pt, 2'0.9 psig during each 10-year. service period.
The third test of'ach set shall be conducted during the. shutdown for the 10-year plant inservice inspection.
b.
If any periodic Type A test fails to meet either.75 L
or.75 Lt, a
the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet either.75 L
or.75 Lt, a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet either
.75 L
or.75 Lt at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L
or 0.25 Lt.
2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25K of the total measured leakage rate at Pa, 41.8 psig or Pt, 20.9 psig.
d.
Type B and C tests shall be conducted with gas at P
, 41.8 psig at intervals no greater than 24 months except for tests involving:
1.
Air locks, e.
2.
Purge supply and exhaust isolation valves with resilient material seals.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4.6.1.7.3 and 4.6.1.7.4.
ST.
LUCIE - UNIT 2 3/4 6-3 Amendment No.
36
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued g.
The combined bypass leakage rate shall be determined to be less than or equal to 0. 12 L
by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P
, 41.8 psig during each Type A
test.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
h.
The provisions of Specification 4.0.2 are not applicable.
ST.
LUCIE " UNIT 2 3/4 6-4 Amendment No. 36
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal transit hntry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than or equal to 0.05 L at P
, 44.8 psig.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
a 0 b.
With one containment 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.
2.
Oper ation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.
3.
Otherwise, 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 />.
4.
The provisions of Specification 3.0.4 are not applicable.
With the containment air lock inoperable, except as the 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 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 />.
If the inner air lock door is inoperable, passage through the OPERABLE outer air lock door is permitted to effect repairs to the inoperable inner air lock door.
No more than one airlock door shall be open at any time.
ST.
LUCIE - UNIT 2 3/4 6"9 Amendment No. 36
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS 4.6. 1.3 Each containment air lock shall be demonstrated OPERABLE:
ao 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 the seal leakage is
< 0.01 L
as determined by precision flow measurement when the volume between the door seals is pres-surized to greater than or equal to:
1.
For the personnel air lock, greater than or equal to P
41.8 psig for at least 15 minutes if not tested with t3e automatic tester.
2.
For the emergency air lock, greater than or equal to 41.8 psig for at least 15 minutes.
b.
By conducting overall air lock leakage tests at not less than P
41.8 psig, and verifying the overall air lock leakage rate is wfthin its limit:
C.
l.
At least once per 6 months, and 2.
Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air'ock sealing capability."
At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
The provisions of Specification 4.0.2 are not applicable.
This constitutes an exemption to Appendix J of 10 CFR 50.
ST.
LUCIE - UNIT 2 3/4 6-10 Amendment No. 36