ML20217P024
| ML20217P024 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/06/1998 |
| From: | Donohew J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217N997 | List: |
| References | |
| NUDOCS 9804090291 | |
| Download: ML20217P024 (14) | |
Text
f nauq 7 p t UNITED STATES g
t j NUCLEAR REGULATORY COMMISSION WASHINGTON, o.C. soseHooi
- /
ENTERGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. INC.
I SOUTH MISSISSIPPl Fi FCTRIC POWER ASSOCIATION I
ENTERGY MISSISSIPPl. INC. l DOCKET NO, 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No NPF-29 1
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. 'N application for amendment by Entergy Operations, Inc. (the licensee) dated October 28,1997, as supplemented by the letter of January 9,1998, comply with the j 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 (1) that the activities authonzed 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 secunty 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 satisfed.
l 9804090291 980406 PDR ADOCK 05000416 P PDR
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- 2. Accordingh, the license is amended by changes to the Technic =t Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF 2g is hereby amended to l read as follows:
(2) Technical Specifications The Technical Specifications contairied in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.135 ,
are hereby incorporated into this license. Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and be Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
} , Q hMk b Jack N. Donohew, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical l Specifications Date of1ssuance: April 6.1998 1
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g ATTACHMENT TO LICENSE AMENDMENT NO.135 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 i
Replace the following pages of the Appendix A Technical Specifications and the Cases to the Technical Specifications with the attached pages! The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT vi vi 3.6-2 3.6-2 3.6-7 3.6-7 3.6-16 3.6-16 3.6-17 3.6-17 5.0-16 5.0-16 B 3.0-12 B 3.0-12 B 3.6-4 ,
B 3.6-4 B 3.6-11 B 3.6-11 B 3.6-24 B 3.6-24 B 3.6-25 B 3.6-25 l
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TABLE OF CONTENTS t
5.0 ADMINISTRATIVE CONTROLS (continued) 5.5.7 Ventilation Testing Program (VFTP) 5.0-12 5.5.8 Explosive Gas and Storage Tank 5.0-13 Radioactivity Monitoring Program 5.5.9 Diesel Fuel Testing Oil Program 5.0-14 l 5.5.10 Safety Function Determination Program 5.0-14 l (SFDP) {
l 5.5.11 Technical Specifications (TS) Bases 5.0-16 Control Program 5.5.12 10 CFR 50 Appendix J, Testing Program 5.0-16 5.6 Reporting Requirements 5.0-17 5.6.1 Occupational Radiation Exposure Report 5.0-17 i 5.6.2 Annual Radiological Environmental 5.0-17 Operating Report
'5.6.3 Radioactive Effluent Release Report 5.0-18 ;
5.6.4 Monthly Operating Reports 5.0-18 ;
5.6.5 Core Operating Limits Report (COLR) 5.0-19 5.7 High Radiation Area 5.0-22 ;
6.0 LIMITING CONDITION FOR OPERATION (LCO) 6.0-1 APPLICABILITY 6.1 REACTIVITY CONTROL SYSTEMS 6.1-1 l 6.1.1 Control Rod Drive Housing Support 6.1-1 6.2 FIRE SYSTEMS 6.2-1 6.2.1 Fire Detection Instrumentation 6.2-1 l 6.2.2 Fire Suppression Water System 6.2-14 l 6.2.3 Spray and Sprinkler Systems 6.2-18 6.2.4 CO2 Systems 6.2-21 l 6.2.5 Halon Systems 6.2-24 6.2.6 Fire Hose Stations 6.2-26 6.2.7 Yard Fire Hydrants and Hydrant Hose Houses 6.2-30 6.2.8 Fire Rated Assemblies 6.2-33 l 6.3 INSTRUMENTATION 6.3-1 6.3.1 Radiation Monitoring Instrumentation 6.3-1 6.3.2 Seismic Monitoring Instrumentation 6.3-6 6.3.3 Meteorological Monitoring Instrumentation 6.3-9 6.3.4 Traversing In-Core Probe System 6.3-11 6.3.5 Loose-Part Detection System 6.3-12 6.3.6 Main Condenser Offgas - Explosive Gas 6.3-13 Monitoring Instrumentation 6.3.7 Feedwater/ Main Turbine Trip 6.3-15 Instrumentation 6.3.8 Turbine Overspeed Protection System 6.3-17 GRAND GULF vi xx/xx/xx I
, 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance leakage rate testing except for primary with 10 CFR 50, containment air lock testing, in - Appendix J, accordance with 10 CFR 50, Appendix J, Testing Program as modified by approved exemptions.
The leakage rate acceptance criterion is s 1.0 La. However, during the first
' unit startup following testing performed in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, the leakage rate acceptance criteria are I < 0.6 La for the Type B and Type C tests, and < 0.75 La for the Type A test.
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l GRAND GULF 3.6-2 Amendment No. 440 135 1
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r i Prirary Containment Air Locks
, 3.6.1.2 i
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i
SR 3.6.1.2.1 ------------------NOTES------------------ l
- 1. An inoperable air lock door does not l invalidate the previous successful performance of the overall air lock leakage test. !
- 2. Results shall be evaluated against acceptance criteria of SR 3.6.1.1.1 i in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.
Perform required primary containment air In accordance lock leakage rate testing in accordance with 10 CFR 50, with 10 CFR 50, Appendix J, as modified Appendix J, by approved exemptions. Testing Program The acceptance criteria for air lock testing are:
- a. Overall air lock leakage rate is s 2 scfh when tested at a Pa-
- b. For each door, leakage rate is s 2 scfh when the gap between the door seals is pressurized to a Pa-SR 3.6.1.2.2 Verify primary containment air lock seal 7 days air flask pressure is a 90 psig. j l
(continued) l l
I GRAND GULF 3.6-7 Amendment No. 440 135
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PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.5 ------------------NOTE-------------------
Only required to be met in MODES 1, 2, and 3.
l Perform leakage rate testing for each 36 months with primary containment purge valve with at least 2 resilient seals, pairs of valves tested every 18 months AND In accordance with 10 CFR 50, Appendix J, Testing Program AND g
...... Note-----
Not applicable to valves tested within 92 days prior to any purge valve failing to meet its acceptance criteria Once within 92 days, test all remaining purge valves, if any purge valve fails to meet its acceptance criteria (continued) !
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GRAND GULF 3.6-16 Amendment No. MG MS 135 l t
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- f. PCIVs
, . 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance a 3 seconds and s 5 seconds. with the Inservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to 18 months the isolation position on an actual or simulated isolation signal.
SR 3.6.1.3.8 ------------------NOTE-------------------
Only required to be met in MODES 1, 2, and 3.
Verify leakage rate through all four main In accordance steam lines is s 100 scfh when tested at with 10 CFR 50, a Pa. Appendix J, Testing Program SR 3.6.1.3.9 ------------------NOTE-------------------
Only required to be met in MODES 1, 2, and 3.
Verify combined leakage rate of I gpm In accordance times the total number of PCIVs through with 10 CFR 50, hydrostatically tested lines that Appendix J, penetrate the primary containment is not Testing Program exceeded when these isolation valves are tested at a 1.1 Pa-l l
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I GRAND GULF 3.6-17 Amendment No. Mo MS 135 l
Programs and Manuals 5.5 i 5.5 Programs and Manuals (continued) 5.5.11 Technical Specifications (TS) Bases Control Proaram This program provides a means for processing changes to the Bases i of these Technical Specifications.
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- a. Changes to the Bases of the TS shall be made under ,
appropriate administrative controls and reviews. !
- b. Licensees may make changes to Bases without prior NRL ,
approval provided the changes do not involve either of the !
following:
- 1. A change in the TS incorporated in the license; or i
- 2. A change to the UFSAR or Bases that involves an <
unreviewed safety question as defined in 10 CFR 50.59. j
- c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
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- d. Proposed changes that do not meet the criteria of either Specification 5.5.11.b.1 or Specification 5.5.ll.b.2 above i shall be reviewed and approved by the NRC prior to )
implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
- 5.5.12 10 CFR 50. Appendix J. Testina Proaram This program establishes the leakage rate testing program of the I l containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be implemented in accordance with the Safety Evaluation issued by the Office of Nuclear Reactor Regulation dated April 26,
, 1995 (GNRI-95/00087) as modified by the Safety Evaluation issued l for Amendment No.135 to the Operating License. Consistent with standard scheduling practices for Technical Specifications required surviellances, intervals for the recommended surveillance frequency for Type A, B and C testing may be extended by up to 25 l
percent of the test interval, not to exceed 15 months.
r GRAND GULF 5.0-16 Amendment No. 440135
SR Applicability 7 -
B 3.f, r
BASES SR 3.0.2- :The'25% extension does not.significantly degrade the (continued) reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being perfomed is the verification of conformance with the
, SRs. The exceptions to SR 3.0.2 are those Surve111ances for i which the 25% extension of the interval specified in-the Frequency does not apply. These exceptions are stated in the individual Specifications. For example, the requirements of regulations take precedence over the TS. l The TS cannot in and of themselves extend a test interval !
specified in the regulations. Therefore, there is a Note in l
tne Frequency stating, "SR 3.0.2 is not applicable."
As stated in SR 3.0.2, the 25% extension also does not apply to the. initial portion of a periodic Completion Tame that requires performance on a "once per..." basis. The 25% i extension applies to each performance after the initial performance. The initial-performance of the E quired Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25%
extension to this Completion Time is that such an action )
usually verifies that no loss of function has occurred by J checking the status of redundant or diverse components or.
accomplishes the function of the inoperable equipment in an alternative manner.
The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.
SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less,. applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time (continued)
GRAND GULF B 3.0-12 LDC 98024
B.
- Prinary Containment
. B 3.6.1.1 BASES.(continued)
SURVEILLANCE SR 3.6.1.1.1 REQUIREMENTS Maintaining the primary containment OPERABLE requires compliance with the visual examinations and leakage rate
' test requirements of 10 CFR 50, Appendix J (Ref. 3), as modified by approved exemptions. Failure to meet air lock leakage testing (SR 3.6.1.2.1 and SR 3.6.1.2.4), resilient seal primary containment purge valve leakage testing (SR 3.6.1.3.5), main steam isolation valve leakage (SR 3.6.1.3.8), or hydrostatically tested valve leakage
-(SR 3.6.1.3.9) does not necessarily result in a failure of this SR. The impact of the failure to meet these SRs must 3 be evaluated against the Type A, B, and C acceptance '
l criteria of 10 CFR 50, Appendix J, as modified by approved I exemptions (Ref. 3). As left leakage prior to the first startup after performing'a required 10 CFR 50, Appendix J, leakage test is required to be < 0.6 La for combined Type B-and C leakage, and < 0.75 La for overall Type A leakage. At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of 51.0 La. At 1 1.0 La the offsite dose consequences are bounded by the assumptions of the safety analysis.
l REFERENCES 1. UFSAR, Section 6.2.
- 2. UFSAR, Section 15.6.5.
l l 3. 10 CFR 50, Appendix J.
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- 4. UFSAR, Section 6.2.6.
- 5. GNRI-95/00087, Exemption From the Requirements of 10 l CFR 50, Appendix J,Section III.D
- 6. GNRI-xx/xxx, Amendment 135 to the Operating License.
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GRAND GULF. B 3.6-4 LDC 98024 l
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Prinary Centainment Air Lecks.
. B 3.6.1.2 k BASES 1'
-ACTIONS D.1 and D.2 (continued) does.not apply.. To achieve this status, the plant must be I brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within' 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.. The allowed Completion Times are . l reasonable, based on operating experience,.to reach the required plant conditions from full power conditions'in an orderly manner and without challenging plant systems. -
SURVEILLANCE SR 3.6.1.2.1 REQUIREMENTS Maintaining primary containment air locks OPERABLE requires compliance with the leakage rate test requirements of I 10 CFR 50, Appendix J (Ref. 2), as modified by approved exemptions. This SR-reflects the leakage rate testing requirements with regard to air lock leakage (Type B leakage tests). The acceptance criteria were established during initial air lock and primary containment OPERABILITY I testing. The periodic testing requirements verify that the air lock leakage does not exceed the allowed fraction of the overall primary containment leakage rate.
l The SR has been modified by two Notes. Note I states that an inoperable air lock door does not invalidate the previous j successful performance of the overall air lock leakage test. ;
This is considered reasonable since either air lock door is !
capable of providing a fission product barrier in the event !
of a DBA. Note 2 has been added to this SR, requiring the results to be evaluated against the acceptance criteria of SR 3.6.1.1.1. This ensures that air lock leakage is properly accounted for in determining the overall primary containment leakage rate. Since the overall primary . !
containment leakage rate is only applicable in MODES 1, 2, and 3 operation, the Note 2 requirement is imposed only during these MODES.
SR 3.6.1.2.2 i The seal air flask pressure is verified to be at a: 90 psig every 7 days to ensure that the seal system remains viable.
It must be checked because it could bleed down during or (continued) l GRAND GULF- B 3.6-11 LDC 98024
. B 3.6.1.3 BASES SURVEILLANCE SR 3.6.1.3.5 REQUIREMENTS (continued) For primary containmc.nt purge valves with resilient seals, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J (Ref. 3), is required to ensure OPERABILI17. Operating experience has demonstrated that this type of seal has the potential to degrade in a shorter time period than do other seal types. Based on this observation, and the importance of maintaining this penetration leak tight (due to the direct path between primary containment and the environment), a Frequency of 36 months, with consideration given to operational experience and safety significance. Additionally, this SR must be performed for all purge valves within 92 days following any purge valve failing to meet it's acceptance criteria. This ensures that any common mode seal degradation is identified.
The Frequency for this SR is modified by a note that indicates that all valves do not have to be retested due to l the failure of another valve, provided they have been tested within 92 days prior to any valve failing to meet it's acceptance criteria.
The SR is modified by a Note stating that the primary containment purge valves are only required to meet leakage rate testing requirements in MODES 1, 2, and 3. If a LOCA inside primary containment occurs in these MODES, purge valve leakage must be minimized to ensure offsite radiological release is within limits. At other times when the purge valves are required to be capable of closing (e.g., during handling of irradiated fuel), pressurization concerns are not present and the purge valves are not required to meet any specific leakage criteria.
SR 3.6.1.3.6 Verifying that the full closure isolation time of each MSIV is within the specified limits is required to demonstrate OPERABILITY. The full closure isolation time test ensures that the MSIV will isolate in a time period that does not (continued)
GRAND GULF- B 3.6-24 LDC 98024
' i PCIVs e . B 3.6.1.3 l
l BASES SURVEILLANCE SR 3.6.1.3.7 (continued) l REQUIREMENTS
! each automatic PCIV will actuate to its isolation position l on a primary containment isolation signal. The LOGIC SYSTEM f FUNCTIONAL TEST in SR 3.3.6.1.7 overlaps this SR to provide complete testing of the safety function. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown that these components usually pass this Surveillance when performed at the-18 month Frequency.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint. i l
I i The analyses in Reference 2 is based on leakage that is less than the specified leakage rate. Leakage through all four steam lines must be s 100 scfhjwhen tested at Pt (11.5 psig). The MSIV leaka~ge rate must be verified to be in accordance with the leakage test requirements of Reference 3, as modified by approved exemptions. A Note is added to this SR which states that these valves are only required to meet this leakage limit in MODES 1, 2 and 3. In the other conditions, the Reactor Coolant System is not pressurized and specific primary containment leakage limits are not required.
l SR 3.6.1.3.9 l Surveillance of hydrostatically tested lines provides assurance that the calculation assumptions of Reference 2 is met.
l This SR is modified by a Note that states these valves are only required to meet the combined leakage rate in MODES 1, 2, and 3 since this is when the Reactor Coolant System is l
(continued) l GRAND GULF B 3.6-25 LDC 98024