ML20129E665

Amend 175 to License NPF-6,revising TS Operating Criteria & Requirements Associated W/Containment Personnel Air Locks

ML20129E665
Person / Time
Site:	Arkansas Nuclear  (NPF-06-A-175)
Issue date:	09/26/1996
From:	Alexion T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20129E670	List: ML20129E665 ML20129E729
References
NUDOCS 9610010139
Download: ML20129E665 (6)

Text

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4 UNITED STATES

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,, j NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20666 4001

'$9.....,o ENTERGY OPERATIONS. INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.175 License No. NPF-6 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated April 4,1995, as supplemented on April 25 and August 19, 1996, 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 license 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.

9610010139 960926' PDR ADOCK 05000368 P

PDR

, 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-6 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.175, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective within 30 days of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 3

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M4bM L@

x Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 26, 1996 I

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ATTACHMENT TO LICENSE AMENDMENT NO.175 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise 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 overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAGES 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 8 3/4 6-1 B 3/4 6-1 l

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

If any periodic Type A test fails to meet either.75 L or

.75 L, the test schedule for subsequent Type A tests $ hall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet either.75 L or.75 L, a Type A a

t test shall be performed at least every 18 months until two at which consecutive Type A tests meet either.75 Ltime the above test schedule m t

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 L

• t 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 25 percent of the total i

measured leakage at P, (54 psig) or Pt (27 psig).

(54 Type B and C tests shall be conducted with gas at P,for tests t

d.

psig) at intervals no greater than 24 months except involving air locks.

}

e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

f.

All test leakage rates shall be calculated using observed data 1

converted to absolute values. Error analyses shall be per-formed to select a balanced integrated leakage measurement system.

g.

The provisions of Specification 4.0.2 are not applicable.

i ARKANSAS-UNIT 2 3/4 6-3 l

CONTA8NMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION l

3.6.1.3 Each containment air lock shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one containment air lock door inoperable in one oi more containment a.

air locks,2, i

Verify that at least the OPERABLE air lock door is closed in the 1.

affected air lock within one hour 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 2.

door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT STANDBY within the next six hours 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 />.

b.

With the containment air lock interlock inoperable in one or more l

centainment air locks :

Verify that at least one OPERABLE air lock door is closed in the 1.

affected air lock within one hour and restore the inoperable air lock interlock 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 an d

OPERABLE air lock door closed.

Operation may then continue provided that the OPERABLE air lock 2.

door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT STANDBY within the next six hours 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 />.

With one or more air locks inoperable for reasons other than those c.

addressed in ACTION a. or b.:

l 1.

Immediately initiate action to evaluate overall containment leakage per LCO 3.6.1.2.

2.

Verify that at least one door in the affected air lock is closed within one hour and restore the affected 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 />.

3.

Otherwise, be in at least HOT STANDBY within the next six hours 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 />.

' Separate ACTION entry is allowed for each air lock.

2 With both air locks inoperable, entry and exit it permissible for seven days under administrative controls.

Entry and exit is permissible to perform repairs on the affected air lock 8

components.

• Entry and exit is permissible under the control of a dedicated individual.

ARKANSAS - UNIT 2 3/4 6-4 Amendment No.175

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS l

4.6.1.3.1 Each containment air lock shall be demonstrated OPERABLE as specified in 10 CFR 50, Appendix J, or as modified by approved exemption':

By conducting a door seal leak test with a seal leakage rate i

a.

of 5 0.01 La when tested at 2 10 psig*,

b.

By conducting an overall air lock leak test with an overall air lock leakage rate of 5 0.05 La when tested at 2 Ps, and The provisions of Specification 4.0.2 are not applicable.

c.

4.6.1.3.2 Each containment air lock interlock shall be demonstrated OPERABLE by testing the air lock interlock mechanism at least once per 184 days'.

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' Leakrate results shall also be evaluated against the acceptance criteria of specification 3.6.1.2.

• An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

' If this surveillance comes due when the containment is not open, it may be deferred until the next entry into containment.

2 ARKANSAS - UNIT 2 3/4 6-5 Amendment No. 175 i

CONTAINMENT SYSTEMS INTERNAL PRESSURE, AIR TEMPERATURE AND RELATIVE HUMIDITY J

LIMITING CONDITION FOR OPERATION 1

3.6.1.4 The combination of containment internal pressure, average air temperature and relative humidity shall be naintained within the region of acceptable operation shown on Figure 3.6-1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the point defined by the combination of containment internal pressure, average air temperature and relative humidity outside the region of acceptable operation shown on Figure 3.6-1, restore the combination of containment internal pressure, average air temperature and relative humidity to within the above limits 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 REQUIREMENTS 4.6.1.4 The primary containment internal pressure, average air temperature J

and relative humidity shall be determined to within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The containment average air temperature shall be the temperature of the air in the containment HVAC common return air duct upstream of the fan / cooler units.

ARKANSAS-UNIT 2 3/46-6

3/4.6 CONTMNMENT SYSTDIS EASES i

r 3/4.6.1 PRIMARY CONTMNMENT i

3/4.6.1.1 CONTMNMENT INTEGRITY Primary CONTMNMENT INTEGR.ITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those i

leakage paths and associated leak rates assumed in the accident analyses.

j This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTMNMENT LEAXAGE The limitations on containment leakage rates ensure that the total i

containment leakage volume will not exceed the value assumed in the i

accident analyses at the peak accident pressure, Pa. As an added j

conservatism, the measured overall integrated leakage rate is further (as applicable) during the performance of i

limited to 50.75 L. or 50.75Lt the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent I

with the requirements of Appendix "J" of 10 CFR 50.

1 3/4.6.1.3 CONTAINMENT AIR LOCKS The lindtations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

Action statement "a" has been modified by a note. Note 2 allows use of the air lock for entry and exit for 7 days under administrative controls if both air locks have an inoperable door. This 7 day restriction begins when the second air lock is discovered inoperable. Containment entry may be required to perform Technical Specification (TS) surveillances and actions, as well as other i

activities on equipment inside containment that are required by TS or activities on equipment that support TS required equipment. An example of such an activity would be the isolation of a containment penetration by at least one OPERABLE valve, and the subsequent repair and post maintenance TS surveillance testing on j

the inoperable valve.

In addition, containment entry may be required to perform repairs on vital plant equipment, which if not repaired, could lead to a plant j

transient or reactor trip. This note is not intended to preclude performing 1

other activities (i.e., non-TS required activities or repairs on non-vital plant equipment) if the containment is entered, using the inoperable air lock, to perform an allowed activity listed above. This allowance is acceptable due to the low probability of an event that could pressurize the containment during the J

i short time that the OPERABLE door is expected to be open.

ror the purposes of this specification, the vertical end plates of the air lock barrel, on which the doors themselves are mounted, shall be considered part of the door.

4 ARKANSAS - UNIT 2 8 3/4 6-1 Amendment No. 175 w

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p0NTAINMENT SYSTEMS mARM 3/4.6.1.4 INTERNAL PESSURE. AIR TEMPERATURE AND RELATIVE EUMIDITY The limitations os contaissent internal pressure, average air temperature and relative busidity assere that 1) the containeemt structure is prevented free exceeding its desfas negative pressure differential with respect to the outside atmosphere of 5.0 pois, 2) the containment peak pressure does not escoed the design pressure of 54 psig during design basis conditions, and 3) the ECC8 analysis assumptions are maintained.

The limitation on containment average air temperature ensures that the containment liner plate temperature does not exceed the design temperature of 300'T during LOCA conditions. The containment temperature limit is consistent with the accident analyses. Figure 3.6-1 represents l

analysis limits and does not account for instrveent error.

3/4.6.1.5 CONTAINMENT STRUCTUnat INTTARITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 53.4 psig in the event of a LOCA. The visual amasination of tendons, anchorages and containment surfaces and the Type A leakage tests of the Unit 2 containment in conjunction with the required surveillance activities of the Unit I containment are sufficient to demonstrate this capability.

The surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in i

l Prestrassed Concrete Containment Structures", January 1976.

3/4.6.1.6 CONTAINMENT VENTILATION SYSTEM i

The containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not l

been demonstrated capable of closing during a LOCA. Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

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l ARKANSAS - UNIT 2 3 3/4 6-2 Amendment No. 139 00T 8 Fi'

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