ML20081K931

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Proposed Tech Specs Section 3/4.4.12 for low-temperature Overpressure Protection
ML20081K931
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/18/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20081K928 List:
References
NUDOCS 9107020171
Download: ML20081K931 (7)
v • d • e


Text

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ANO-2 TECilNICAL SPECIFICATION PROPOSED CilANGED PAGES s

9'107020171 o10618 l

{,DR ADOCK 05000368 PDR

. i REACTOR COOLANT-Ss91EH DVERPRESSURE PROTECTION SYSTEM LIMITING CONDITION FOR opt' RATION 3.4.12 Two LTOP relief valvis shall be in service.

APPLICABILITY: MODES 5 and 6, when the RCS is not adequately vented.

ACTION:

a. With only one LTOP relief valve in service restore the Inoperable LTOP relief valve to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or depressurize and adequately vent the RCS within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,
b. With no LTOP relief valves in service, depressurize and adequately vent the RCS within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
c. In the event an RCS vent or the LTOP relief valves are used to

. mitigate an LTOP pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

d. 1he provisions of Specification 3.0.4 are not applicable.

. SURVEILLANCE REQUIREMENTS 4.4.12 Verify LTOP relief valve or RCS vent path alignment at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l ARKANSAS - UNIT 2 3/4 4-28 Amendment No.

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REACTOR COOLANT SYSTEM BASES  :

3/4.4.10 STRUCTURAL INTEGR111 The inservice inspection and testing programs for ASME Code class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boller and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a(g)(6)(1).

ASME Code Class 1 components of the reactor coolant system were designed to provide accesr to permit inservice inspections in accordance with Section XI of the ASt.E Boiler and Pressure Vessel Code, 1971 Edition and Addenda through Summer 1973. ASME Code Class 2 and 3 components were designed to provided access to permit inservice inspection in accordance with Section X1 of the Af.ME Boller and Pressure Vessel Code, 1971 Edition and Addenda through Winter 1972.

3/4.4.11 REACTOR COOLANT SYSTEM V.ENIS The reactor coolant vents are provided to exhaust noncondensible gases and/or steam from the primary system that could inhibit natural circulation core cooling. The OPERABILITY of at least one vent path from the reactor vessel head and the reactor coolant system high point ensures the capability exists to perform this function. The valve redundancy of the i

vent paths serves to minimize the probability of inadvertent actuation and breath of reactor coolant pressure boundary while ensuring that a singic failure of a vent valve, power supply, or control system does not prevent isolation of the vent path. Testing requirements are consistent with ASME Section XI for Class 2 valves (see 3/4.4.10 above) and Item II.B.1 of NUREG-0737, " Clarification of.THI Action Plan Requirements," November 1980, 3/4.4.12 LOW TEMPERATURE OVERPRESSURE PROTECTION Low Temperature Overpressure Protect ion (LTOP) is provided by redundant relief valves on the pressurizer which discharge from a single discharge header. Each LTOP relief path contains two motor operated isolation valves and a non-power operated relief valve having a design setpoint of 450 psig.

For single failure protection both relief valves are required to be in service unless an adequate vent path of 6.38 square incheslor larger is maintained. The LTOP relief valves are aligned by the operator by opening the isolation valvor during cooldown prior to the RCS' cold leg temperature decreasing Selov 200*F. The LTOP-relief valves are considered to be in service when the associated isolation valves are open.

ARKANSAS - UNIT 2 B 3/4 4-11 Amendment No. (1,

i REACTOR COOLANT SYSTEti j EASIS The low temperature transient P-T limits provide pressure restrictions for the protection against. non-ductile failure under transient conditions. These limits are calculated in accordance with the methodologies described in Combustion Engineering owners Group (CEOG) report CEN-381-P and in Attachment 1-P to CEN-381-P.

The LTOP system ensures that the RCS will be protected from these pressure transients which could exceed the applicable hTOP pressure-temperature limits for 21 EPPY when one or more of the RCS cold leg temperatures is less than or equal to the I. TOP enable temperature. . The design basis pressurization event is a full safety injection initiation from water-solid conditions (injection from two llPSI and three charging pumps). The peak transient pressure in this .

event (540 psla) is lower than the applicable LTOP P-T limits. These limits are less restrictive than the P-T 11 mitt in Technical Specification 3/4.4.9 due to the use of detalle n :tactur.s moci'anics in place of pre-established margins used in the Adde Code, Sectic,n 111 Appendix G methodologies.

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ARKANSAS - UNIT 2 B 3/4 4-12 Amendment No.

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M 181STRATIVE CONIRQLS_

1. Radiological Environmental Monitoring Sample Analysis, f Specification 3.12.1.
m. Unplanned Offsite Release daring one hour period of 1) more than 1 curie of radioactive material in liquid effluents. 2) more than  ;

150 curies of noble gas in gaseous effluents, or 3) more than O.05 curies of radiolodine in gaseous ef fluents. This report shall be submitted within 30 days of the occurrence of the event and shall include the following information: ,

1. Description of the occurrence.
2. Identify the cause(s) of exceeding the Ifmit(s).
3. Explain corrective action (s) taken to mitigate occurrence.
4. Define action (s) taken to prevent recurrence. I
5. Summary of the consequenec(s) of occurrence.
n. Hitigation of LTOP pressure transients, Specification 3.4.12.

The report shall describe the circumstances initiating the transient, the effect of the relief valves or RCS vents on the transient, and any corrective action necessary to prevent recurrence.-

SEMI-ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT

  • 6.9.3 Routino radioactive ef fluent release reports covering the operating of. the unit during the previous 6 months of operations shall be submitted within 60 days af ter January 1 cud July 1 of each year.
  • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste system, the submittal shall

- specify the releases of radioactive material from each unit.

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ARKANSAS - UNIT 2 6-19a Amendment No. $J, 74.

ATTACilMENT 1 ENGINEERING REPORT A-MPS-ER-003 LOW TEMPERATURE OVERPRESSURE PROTECTION PRESSURE-TEMPERATURE LIMITS FOR ANO-2 FOR 21 EFPY This Report is Proprietary and is tTeing Submitted Under Seperate Cover Letter

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ATTACilMENT 2 ENGINEERING REPORT A-MPS-ER-004 LOW TEMPERATURE OVERPRESSURE PROTECTION ANALYSIS FOR ANO-2 FOR 21 EFPY l

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