ML18011A836
| ML18011A836 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/10/1995 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18011A837 | List: |
| References | |
| NPF-63-A-054 NUDOCS 9503170257 | |
| Download: ML18011A836 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CARO I A POWER 5 IG COHPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCL AR POWER PLANT, UNIT 1
AMENDMENT TO FACI ITY OPERATING LICENSE Amendment No. 54 License No.
NPF-63 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power
- 8. Light Company, (the licensee),
dated December 19,
- 1994, 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; 2.
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 l.
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.
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-63 is hereby amended to read as follows:
q505170257 06000400 q50310 PDP ADOCK PDR P
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No.
are hereby incorporated into this license.
Carolina Power
& Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 10, 1995 W lliam H.
B
- ema, Director Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
TTACHMENT TO LICE SE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pa es 3/4 6-3 B 3/4 6-1 Insert Pa es 3/4 6-3 B 3/4 6-1
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE SURVEILLANCE REQUIREMENTS (Continued) b.
C.
d.
e.
period.
The third test of each set shall be conducted guring the shutdown for the 10-year plant inservice inspection; A one time extension of the test interval is allowed for performance of the third Type A test of the first 10-year service period during Refueling Outage No. 7.
If any periodic Type A test fails to meet 0.75 L 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 0.75 L.. a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed; The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the supplemental test result, L is in accordance with the following equation:
IL, - (L
+ L,)( s 0.25 L.. where L
is the measured Type A test leakage and L. is the superimposed leak; 2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; and 3.
Requires that the rate at which gas is injected into the containment or bled from the containment during the supplemental test is between'0.75 L, and 1.25 L..
Type B and C tests shall be conducted with gas at a pressure not less than P,. at intervals no greater than 24 months except for tests involving:
1.
Air locks.
2.
Containment purge makeup and exhaust isolation valves with resilient material seals, Air locks shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.3; Purge makeup and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.7.2; The provisions of Specification 4.0.2 are not applicable.
SHEARON HARRIS - UNIT 1 3/4 6-3 Amendment No.
34
3/4.6 CONTAINHENT SYSTEHS BASES 3/4.6.1 PRIHARY CONTAINMENT 3/4.6.1. 1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be r'estricted to those leakage paths and associated leak rates assumed in the safety analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 CONTAINHENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P..
As an added conservatism.
the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic test, to account for possible degradation of the containment leakage barriers between leakage tests..
The surveillance testing fot measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50.
A one time extension of the test interval specified in Surveillance Requirement 4.6.1.2.a is allowed for performance of the third Type A test of the first 10-year service period during Refueling Outage No. 7.
3/4.6.1.3 CONTAINHENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINHENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that:
(1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of -2 psig.
and (2) the containment peak pressure does not exceed the design pressure of 45 psig.
The maximum peak pressure expected to be obtained from a postulated main steam line break event is 40.9 psig using a value of 1.9 psig for initial positive containment pressure.
However, since the instrument tolerance for containment e
ressure is 1.32 psig and the high-one setpoint is 3.0 psig, the pressure imit was r educed from the high-one setpoint by slightly more than the tolerance and was set 'at 1.6 psig.
This value will prevent spurious safety injection signals caused by instrument drift during normal operation.
The
-1" wg was chosen to be consistent with the initial assumptions of the accident analyses.
SHEARON HARRIS
- UNIT 1 B 3/4 6-1 Amendment No.
54
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