ML17228A570

Proposed TS Section 3/4.7.1.1,turbine Cycle,Safety Valves, Deleting Ref to 1974 Edition of ASME Code & Referring to Testing in Accordance W/Ts 4.0.5,ISI & IST Spec

ML17228A570
Person / Time
Site:	Saint Lucie
Issue date:	05/23/1994
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17228A568	List: ML17228A567 ML17228A570
References
NUDOCS 9406010046
Download: ML17228A570 (11)

Text

INDEX LIST OF TABLES {Continued)

TABLE PAG 3.7-1 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS...................... 3/4 7-2 STEAM LINE SAFETY VALVES PER LOOP... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-8 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL.................... 3/4 7-22 3.7-3a D ELETED ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 7-26 3.7-3b D ELETED...... 3/4 7-27 3.7-4 FIRE HOSE STATIONS.................................... 3/4 7-36 3.7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES 3/4 7-38 4.8-1 DIESEL GENERATOR TEST SCHEDULE......".................. 3/4 8-8 4.8-2 BATTERY SURVEILLANCE REQUIREMENT...'................... 3/4 8-12 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES........................................ 3/4 8-18 4.1')-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P ROGRAH ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 11-2 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS P ROGRAM ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 11-8 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM......... 3/4 12-3 3.12-2 REPORTING LEVELS fOR RADIOACTIVITY CONCENTRATIONS IN FNVIRONHENTAL SAMPLES................................. 3/4 12-7 4.12-1 DETECTION CAPABILITIES FOR ENVIRONHENTAL SAMPLE ANALYSIS o i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 12-8 B 3/4.2-1 D ELETED ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i' ~ ~ ~ ~ ~ B 3/4 2-3 B 3/4..4-1 REACTOR VESSEL TOUGHNESS.............................. B 3/4 4-9

5. 7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................. 5-5 6.2-1 MINIMUM SHIFT CREW COHPOSITION-TWO UNITS WITH TWO SEPARATE CONTROL ROOMS 6-5 9406010046 940523 PDR ADDt K 05000389 i PDR, ~~"

ST. LUCIE UNIT 2 XXV Amendment No. S,.M 53

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a 3/4.7 PLANT SYSTBtS 3/4.7.1 TURBINE CYCLE SAFETY VALVES Lr Cr TING CONDITION FOR OPERATION 9.7.1.1 All line safety valves shall

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code be OPERABLE~cui4 APPLICABILITY: MODES 1, Z and 3.

ACTION:

a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, 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 />.

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1. E ch m in s am li e code s fety val shall e demon trated PERA (E, w~thJlif sett ngs nd or ice siz as show in Tab 4.7-0 in ac rdan wig Se ion I o the NE Boile and Pre sure Yes el Cod , 1974 dftio .

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ST. LUG IE - UNIT 2 3/4 7-1 Amendment No8

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3 7-2 TABLE STEAN LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING 1% ORIFICE SI2E Header A Header B

a. 8201 8205 1000 psia 16 in. 2 8202 .8206 1000 psia 16 in. 2 0203 8207 1000 psia 16 in.

8204 8208 1000 psia 16 in.

e. 8209 8213 1040 psia 16 in.

8210 8214 1040 psia 16 in. 2 8211 8215 1040 psia 16 in. 2 8212 8216 1040 psia 16 in.

St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment Administrative Chan e to Delete ASME Code Reference ATTACHMENT 2 SAFETY ANALYSIS Introduction A change is proposed to revise the St. Lucie Unit 2 Technical Specifications Section 3/4.7.1.1 to change the reference to, a specific edition of the ASME Code to a reference to testing in accordance with Technical Specification 4.0.5 and renumber the safety valve set point Table 4.7-0 to Table 3.7-2. The list of tables in the index is also revised.

Discussion The proposed change to the St. Lucie Unit 2 Technical Specifications revises the specific reference to the Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition to be similar to the Unit 1 Technical Specification and consistent with the revised Standard Technical Specifications for Combustion Engineering Plants, NUREG 1432. In addition, the change renumbers the safety valve set point table from a surveillance table to an Limiting Condition for Operation (LCO) table.

Surveillance requirement 4.7.1.1 currently states that, each main steam line code safety valve shall be demonstrated OPERABLE, with lift settings and orifice sizes as shown in Table 4.7-0, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition. The Edition of the ASME Code endorsed for the second ten year interval for St. Lucie Unit 2 is the 1986 Edition of the ASME Code.

This proposed change relocates the reference to the set point table to Limiting Condition for Operation (LCO) 3.7.1.1 and renumbers the table accordingly. This Technical Specification change eliminates the need for future changes to the Technical Specification because Specification 4.0.5 ensures that in-service testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

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-St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment Administrative Chan e to Delete ASME Code Reference ATTACHMENT 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves a no significant hazards consideration are included in the Commission s regulation, 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Each standard is discussed as follows:

(1) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of 'an accident previously evaluated.

The proposed amendment does not involve a significant, increase in the probability or consequences of an accident previously evaluated because the main steam code safety valves will continue to be tested in accordance with current NRC requirements as implemented through 10 CFR 50.55a. The NRC specifies the ASME code requirements 'for a facility through revisions to 10 CFR 50.55a and through the review and approval of the plant specific in-service testing plan for pumps and valves at the beginning of each in-service inspection interval. The probability or consequences of an accident are not increased because testing of the main steam safety valves is in accordance with the appropriate NRC requirements.

(2) Use of the modified specification would not create the possibility of a new or different, kind of accident from any previously evaluated.

The use of, this modified specification can not create the possibility of a new or different kind of accident from any previously evaluated since there is no physical change to the facility or the set points for the main steam safety valves.

The valves will be tested in accordance with current requirements. No new failure mode is introduced due to the change because no plant change is being made and main steam safety valve test methods are consistent with the endorsed edition of the ASME Code.

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"(3) Use of the modified specification would not involve a significant reduction in a margin of safety.

The existing technical specification references an outdated version of the ASME Code. This change corrects the reference to Specification 4.0.5 which ensures that in-service testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

Safety valve setpoints or tolerances are not changed by this proposal. Therefore, the modified specification corrects the ASME Code reference and does not involve a significant reduction in a margin of safety.

Based on the above, we have determined that the proposed amendment does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the probability of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety; and therefore does not involve a significant hazards consideration.

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