Text

Amend 17 to License NPF-41,revising Tech Specs to Change Pressure Values for Testing Containment Leakage Rates & to Allow Air Lock Door to Be Open
	ML17303A421
Person / Time
Site:	Palo Verde
Issue date:	06/03/1987
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17303A422	List: ML17303A421; ML17303A424;
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	NUDOCS 8706150018
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 ARIZONA PUBLIC SEPVICE COMPANY, ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT NO.

1 AMENDMENT TO FA(ILITY OPERATING LICENSE Amendment No.

I7 License No.

NPF-41 1.

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

A.

The application for amendment, dated October 2, 1986, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Pa'so Electric

Company, SoutherrI California Edison

Company, Public Service Company of New Mexico, Los Anaeles Department of Mater and Power, and Southern California Public Power Authority (licensees},

complies with the standards and requirements of the Atomic Energy Act of

1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of Act, and the regulations of the Commission; C.

There is reasonable assurance (i, that the activities authorized by this amendment can be conducted without endangerirIg 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 security or to the health and safety of the public; 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.

870bi50018, 870b03 PDR ADOCK 05000528 P

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 17, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications Date of Issuance:

June 3

1987 George

. Knighton, irector Project Directorate V

Division of Reactor Projects - III/IV/V 5 Special Projects

st 1

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June 3, 1987 ENCLOSURE TO LICENSE ANENDj~iENT NO, 1 7 FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-528 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.

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa es 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-15 B 3/4 6-2 Overleaf Pa es 3/4 6-6 3/4 6-16 B 3/4 6-1

C

3/4.6 CONTAINMENT 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 3.6-1 of Specification 3.6.3.

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 Type A or B

test, by leak rate testing the seal with gas at P

49.5 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

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.

PALO VERDE - UNIT 1 AMENDMENT NO.

17

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:

2.

Less than or equal to L

, 0. 10X by weight of the a'ontainment air per 24'ours at P, 49.5 psig, or a'ess than or equal to Lt, 0.05K by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of Pt, 24.8 psig.

b.

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

"APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

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 leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 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 prior 'to increasing the Reactor Coolant System temperature above 210~F.

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 Part 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 shutdown at either P

49.5 psig or at Pt 24.8 psig during each 10-year service a

period.

The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

PALO VERDE - UNIT 1 3/4 6-2 AMENDMENT NO.

17

CONTAINMENT SYSTEMS BASES 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 4 psig and (2) the containment peak pressure does not exceed the design pressure of 60 psig during LOCA conditions.

The maximum peak pressure expected to be obtained from a LOCA event is 49.5 psig.

The limit of 2.5 psig for initial positive containment pressure will limit the total pressure to 49. 5 psig which is less than the design pressure (60 psig) and is consistent with the safety analyses.

3/4. 6. l. 5 AIR TEMPERATURE The limitation on containment average air temperature ensures that the overall containment average air temperature does not exceed the initial tem-perature condition assumed in the safety analysis.

3/4. 6.1. 6 CONTAINMENT STRUCTURAL INTEGRITY 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 49.5 psig in the event of a LOCA.

The containment design pressure is 60 psig.

The measurement of containment tendon lift-offforce; the tensile tests of the tendon wires or strands; the examina-tion and testing of the sheathing filler grease; and the visual examination of tendon anchorage assembly

hardware, surrounding concrete and the exterior sur-faces of the containment are sufficient to demonstrate this capability.

The tendon wire or strand samples will also be subjected to tests.

All of the required testing and visual examinations should be performed in a time frame that permits a comparison of the results for the same operating history.

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 Prestressed Concrete Containment Structures,"

Revision 3, 1984, and Regulatory Guide 1.35. 1, "Deter-mining Prestressing Forces for Inspection of Prestressed Concrete Containments,"

~1984.

The required Special Reports from any engineering evaluation of containment abnormalities shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages),

the inspection procedures, the toler ances on cracking, the results of the engineering evaluation, and the corrective actions taken.

PALO VERDE " UNIT 1 B 3/4 6-2 AMENDMENT NO.

17

3/4.6 CONTAINMENT SYSTEMS BASES 3/4. 6. 1 PRIMARY CONTAINMENT 3/4. 6. 1. 1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.

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

3/4.6. 1.2 CONTAINMENT 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 fs further limited to less than or equal to 0.75 L

or less than or equal to 0.75 L

as applicable during performance of 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 with the requirements of Appendix J of 10 CFR Part 50.

3/4. 6. 1. 3 CONTAINMENT AIR LOCKS The limitations 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 provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

PALO VERDE - UNIT 1 8 3/4 6-1

CONTAlNMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) b.

If any periodic Type A test fails to meet either 0.75 L

or 0.75 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 0.75 L

or 0.75 Lt, a Type A test shall be performed at least every 18 months until two'onsecutive Type A tests meet either

0. 75 L

or 0.75 Lt at which time the above test schedule may be I

resumed.

c.

The accuracy of each Type A test shall be verified by a supplemental test which:

d.

1.

Confirms the accuracy of the Type A test by verifying that the supplemental test result L

minus the sum of the Type A test

result, L

, and the superimposed leak r ate, L

, is equal to or less than 0.25 L

2.

Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

3.

Requires that the rate at which gas is injected into the contain-ment 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 P

, 49.5 psig, at intervals no greater than 24 months except for tests involving:

1.

Air locks, 2.

Purge supply and exhaust isolation valves with resilient material seals.

e.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Specifications 4,6.1.7.3 and 4.6.1.7.4.

Air locks shall be tested and demonstrated OPERABLE per Specification 4.6.1.3.

g.

The provisions of Specification 4.0.2 are not applicable.

PALO VERDE - UNIT 1 3/4 6-3 AMENDMENT NO.

17

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 entry 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 0'5 L

at P

, 49.5 psig.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

Operation 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, or 2.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3.

The provisions of Specification 3.0.4 are not applicable.

b.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6. 1.3 Each containment air lock shall be demonstrated OPERABLE:

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying seal leakage to be less than or equal to 0.01 L

when determined with the volume between the door seals pressurized to greater than or equal to 14.5 +

0.5 psig, for at least 15 minutes, "Except during entry to repair an inoperable inner door, for a cumulative time not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per year.

PALO VERDE - UNIT 1 3/4 6-4 AMENDMENT NO. 17

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued b.

By conducting overall air lock leakage tests at not less than P

a'9.5

psig, and verifying the overall air lock leakage rate is within its limit:

1.

At least once per 6 months¹,

and 2.

Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on t$ e air lock that could affect the air lock sealing capability."

c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

¹The provisions of Specification 4.0.2 are not applicable.

This constitutes an exemption to Appendix J of 10 CFR Part 50 PALO VERDE - UNIT 1 3/4 6-5 AMENDMENT NO.

17

CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6. 1.4 Primary containment internal pressure shall be maintained between

-0.3 and 2.5 psig.

I APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6. 1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

PALO VERDE - UNIT 1 3/4 6-6

CONTAINMENT SYSTEMS 3/4. 6. 2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWT on a containment spray actuation signal and automatically transferring suction to the containment sump on a recirculation actuation signal.

Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY:

MODES 1, 2, 3, and 4."

ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .,

restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.6.2. 1 Each containment spray system shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is positioned to take suction from the RWT on a containment spray actuation (CSAS) test signal.

By verifying that each pump develops an indicated differential pressure of greater than or equal to 257 psid at greater than or equal the minimum allowable recirculation flowrate when tested pursuant to Specification 4.0.5.

C.

At least once per 31 days by verifying that the system piping is full of water to the 60 inch level in the containment spray header

(>115 foot level).

d.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) and recirculation actuation (RAS) test signal.

2.

Verifying that upon a recirculation actuation test signal, the containment sump isolation valves open and that a

recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

"Only when shutdown cooling is not in operation.

PALO VERDE - UNIT 1 3/4 6-15 AMENDMENT NO.

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.

3.

Verifying that each spray pump starts automatically on a safety injection actuation (SIAS) and on a containment spray actuation (CSAS) test signal.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

PALO VERDE - UNIT 1 3/4 6-16

TABLE 3.6-1 (Continued) 0~K 10 E

VALVE HUHBER PENETRATION NUHBER FUHCTION E.

SAFEVY/RELIEF VALVES MAXIMUM ACTUATION TIME (SECONDS)

SIA-PSV 1511 23 SIB-PSV 140'4 SIB-PSV 189 26 SIA-PSV 179 27 SIE-PSV 474 28 Co'ntainment recirculation sump to containment

spray, LPSI and HPSI headers 1A 8 1B Containment recirculation sump to containment

spray, LPSI and HPSI headers 2A 8 2B From shutdown cooling RC Loop 2 From shutdown cooling RC Loop 1 Safety injection drain relief H.A, N.A.

H. A.*

N.A:*

N.A.

)

Valves also covered by Specification 3/4.4.8. 3 SHot Type C Tested PALO VERDE " UNIT 1 Q/4 g Qo

ML17303A421

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