Text

Amends 50 & 41 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Specs to Define RCS Pressure Isolation Valves Allowable Leakage Criteria,Per NRC Guidance
	ML20106H351
Person / Time
Site:	Farley
Issue date:	10/15/1984
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20106H354	List: ML20106H351; ML20106H368;
References
	TAC-48714, TAC-48715, NUDOCS 8410310538
	Download: ML20106H351 (14)
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' UNITED STATES -

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' ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NllCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. NPF-2 J1.. The Nuclear Regulatory Comission (the Comission) has found that:

-A.

The application for amendment by Alabama Power Company-(the licensee) dated April 10, 1984, complies with the standards and

-requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in

- 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended,.the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations; i

D.

.The issuance of t.his license amendment will not be inimical to the common defense and security or to the health and safety of the

r publ__ic; an.d x.

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the.Comission's regulations and all applicable requirements have

. been satisfied.

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-2 is hereby

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amended to read as follows:

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. (2) Technical Specifications

'The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 50, are hereby incorporated in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION L

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1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 15, 1984

f ATTACHMENT TO LICENSE AMENDMENT NO. 50 AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO.-50-348 Revised Appendix-A as follows:

Remove Pages Insert Pages V

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3/4 4-17 3/4 4-17 3/4 4-18 3/4.4-18 3/4 4-19 3/4 4-19 3/4 4-19a 3/4 4-19b.

B 3/4 4-4 8 3/4 4-4

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INDEX

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation...........

3/4 4-1 Hot Standby...................

3/4 4-2 Hot Shutdown..................

3/4 4-3 Col d Shutdown..................

3/4 4-4 a

.3/4.4.2 SAFETY YALVES - SHUTDOWN............

3/4 4-5 3/4.4.3 uSAFETY VALVES - OPERATING............

3/4 4-6 3/4.4.4 PRESSURIZER............-.......

3/4 4-7 3/4.4.5 RELIEF-VALVES..................

3/4 4-8 3/4.4.6 STEAM GENERATORS 3/4 4-9 3/414~.7 -

REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............

3/4 4-16 Operational Leakage...............

3/4 4-17 3/4.4.8 CH EMI STRY....................

3 /4 4-2 0 3/4.4.9 SPECIFIC ACTIVITY................

3/4 4-23 3/4.4.10 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-27 Pressuri zer...................

3/4 4-31 Overpressure Protection Systems.........

3/4 4-32 3/4.4.11 STRUCTURAL ' INTEGRITY ASME Code Class 1, 2 and 3 Components......

3/4 4-34 FARLEY - UNIT 1 Y

AMENDMENT NO. 50 m-.

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'REACTURCOOLANTSYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.7.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAKAGE, c.

1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator, d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and e.

31 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 j; 20 psig.

f.

The maximum allowable leakage of any Reactor Coolant System Pressure Isolation Valve shall be as specified in

. Table 3.4-1 at a pressure of 2235 f; 20 psig.

-APPLICABILITY: MODES 1, 2,.3 and 4 ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 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 .

~

b.- With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 .

c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the limit specified in Table 3.4-1, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, 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 foliawing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each cf the above limits by; a.

Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Monitoring the containment air cooler condensate level system or containment atmosphere gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

FARLEY -. UNIT 1 3/4 4-17 AMENDMENT NO. 50

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REACTOR COOLANT SYSTEM

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SURVEILLANCE REQUIREMENTS (Continued)

Measurement of the CONTROLLED LEAKAGE from'the reactor coolant c.

pump seals at least once per 31 days when the Reactor Coolant System pressure is 2235 + 20 psig with the modulating valve fully open.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Monitoring the reactor head flange leakoff system at least once e.

.per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.7.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification

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4.0.5 except that in lieu of any leakage testing required by Specification 4.0.5, each valve should be demonstrated OPERABLE by verifying leakage to be within the allowable leakage criteria of 0.5 gpm per inch of nominal valve size with an upper limit of the maximum allowable leakage in Table 3.4-1;' and the measured leak rate for any given test cannot reduce the difference between the results of the previous test and the maximum allowable leakage specified in Table 3.4-1 by more than 50%:#

Every refueling outage during startup.

a.

b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve affecting the seating capability of the valve.

c.

Following valve actuation due to automatic or manual action or flow thnough the valve for valves identified in Table 3.4-1 by an asterisk.

d.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

To satisfy ALARA requirements, leakage may be measured indirectly (as from performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is

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capable of demonstrating salve compliance with the leakage criteria.

FARLEY - UNIT 1 3/4 4-18 AMEN 0 MENT NO. 50 4

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-TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES

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VALVE -

MAXIMUM NUMBER DESCRIPTION ALLOWABLE LEAKAGE **

-Q1E11V001A 12" GATE 5.000 GPM Q1E11V001B 12" GATE 5.000 GPM Q1E11V016A 12" GATE 5.000 GPM Q1E11V016G.

12" GATE 5.000 GPM Q1E11V021A 6" CHECK 3.000 GPM Q1E11V021B 6" CHECK 3.000 GPM Q1E11V021C-6" CHECK 3.000 GPM

Q1E21V032A 12" CHECK 5.000 GPM

'* Q1E21V032B 12" CHECK 5.000 GPM

Q1E21V032C

-12" CHECK 5.000 GPM

'* Q1E21V037A' 12" CHECK 5.000 GPM

Q1E21V037B 12" CHECK 5.000 GPM

Q1E21V037C 12" CHECK 5.000 GPM Q1E11V042A 10" CHECK 5.000 GPM Q1E11V042B 10" CHECK 5.000 GPM

-* Q1E21V076A 6" CHECK 3.000 GPM

Q1E21V076B 6" CHECK 3.000 GPM

Q1E21V077A 6" CHECK 3.000 GPM

Q1E21V077B 6" CHECK 3.000 GPM Q1E21V077C 6" CHECK 3.000 GPM Indicates the requirements of Section 4.4.7.2.2 Item (c) are applicable.

The measured leak rate for any given test cannot reduce the difference between the results of the previous test and the maximum allowable leakage specified in Table 3.4-1 by more than 50%.

FARLEY - UNIT 1 3/4 4-19 AMENDMENT NO. 50

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REAC' TOR COOLANT SYSTEM BASES 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.7.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant

'. Pressure Boundary. These detection systems are consistent with the recomendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3/4.4.7.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can _be reduced to a threshold value of less than 1 GPM.

This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The CONTROLLED LEAKAGE limitation restricts operation when i'

the. total flow suppi eed to.ne reactor coolant pump seals exceeds 31 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig. This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.

The surveillance requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity, thereby reducing the 6

probability of gross valve failure u.:1 consequent intersystem LOCA.

Leakage from the RCS Pressure Isolation valves is IDENTIFIED LEAKAGE and will be considered a portion of the allowed limit.

a The total steam generator tube leakage limit of 1 GPM for all steam generators ensures that the dosage contribution from the tube

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leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break.

The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. The 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.

f PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.

FARLEY-UNIT 1 8 3/4 4-4 AMENDMENT HO. 50 n

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NUCLEAR REGULATORY COMMISSION n

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ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE knendment No. 41 License No. NPF-8

'1.

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

A.

The cpplication for amendment by Alabama Power Company (the licensee) dated April 10, 1984, 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, as amended, the provisions of the Act, and the 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.

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-8 is hereby amended to read as follows:

4 (2)'

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment-No. 41, are.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION I

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ven A. Varga,3( bief

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C Operating Reactors Bran'

1 Division of Licensing

Attachment:

Changes to the Technical Spec'ifications Date of' Issuance:

October 15, 1984

?

ATTACHMENT TO LICENSE AMENDMENT NO. 41

- AMENDMENT NO. 41 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:

Remove Pages Insert Fag 3/4 4 3/4 4-17 3/4 4-17a.

'3/4 4-18 3/4 4-1E 3/4 4-19 3/4 4-19

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~ REACTdRCOOLANTSYSTEM

-OPERATIONAL' LEAKAGE-LIMITING CONDITION FOR.0PERATION 3.4.7.2 Reactor Coolant System leakage-shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAKAGE,

- /.

c.

1 GPM total primary-to-secondary leakage through 'all steam generators and 500 gallons per day through any one

-steam' generator, d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and e.

31 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235120 psig.

b f.

The maximum allowable leakage of any Reactor Coolant System Pressure Isolation Valve shall be as specified in Table 3.4-1 at a pressure of 2235 1 20 psig.

APPLICABIL1TY: MODES 1, 2,-3 and 4 ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT

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STANDBY within 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 .

b.

_ ith any Reactor Coolant System leakage greater than any W

one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits withir.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-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 .

cl With any Reactor Coolant System Pressure Isolation. Valve

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leakage greater than the Ifmit specified in Table 3.4-1, d

isolate the high pressure portion of the affected system W.

from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at

'J 1 east two closed manual or deactivated automatic valves, 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 REQUIREMENTS 2

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i

-4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by; a.-

Monitoring the containment atmosphere par'ticulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

+

b. -Monitoring the containment air cooler condensate level system or containment atmosphere gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

FARLEY - UNIT 2 3/4 4-17 AMENDMENT NO. 41

'. 1. 3.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continu_ed) c.

Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2235 + 20 psig with the modulating valve fully open. The provisions of~ Specification 4.0.4 are not applicable for entry into MODE 3 or~4.

d.

Performance of a Reactor Coolant System water inventory balance at 1 east once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

e.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.7.2.2 Each Reactor Coolant System Pressure Isolation Yalve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5 except that in lieu of any leakage testing required by Specification 4.0.5, each valve should be demonstrated OPERABLE by verifying leakage to be within the allowable leakage criteria of 0.5 gpm per inch of nominal valve size with an upper limit of the maximum allowable leakage in Table 3.4-1; and the measured leak rate for any given test cannot reduce the difference between the 'results of the previous test and the maximum allowable leakage specified in Table 3.4-1 by more than 50%:#

a.

Every refueling outage during startup.

b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve affecting the seating capability of the valve.

c.

Following valve actuation due to automatic or manual action or flow through the valve for valves identified in Table 3.4-1 by an asterisk.

d.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

To satisfy ALARA requirements, leakage may be measured indirectly (as from performance of pressure indicators) if accomplished in accordance with l

l approved procedures and supported by computa'tions showing that the method is capable of demonstrating valve compliance with the leakage criteria.

l FARLEY - UNIT 2 3/4 4-18 AMENDMENT N0. 41

' TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE' ISOLATION VALVES V/lVE MAXIMUM NUMBER DESCRIPTION

' ALLOWABLE LEAKAGE **

Q2E11V001A 12" GATE 5.000 GPM Q2E11V001B 12" GATE 5.000 GPM

-Q2E11V016A 12" GATE 5.000 GPM

-02E11V016B 12" GATE 5.000 GPM Q2E11V021A-6" CHECK 3.000 GPM

.Q2E11V021B 6"' CHECK 3.000 GPM Q2E11V021C 6" CHECK 3.000 GPM

= Q2E21YO32A 12" CHECK 5.000 GPM

-

Q2E21V032B 12" CHECK 5.000 GPM

Q2E21V032C' 12" CHECK 5.000 GPM

Q2E21V037A 12" CHECK 5.000 GPM

Q2E21V037B 12" CHECK 5.000 GPM

Q2E21V037C-12" CHECK 5.000 GPM

'Q2E11V042A.

10". CHECK 5.000 GPM Q2E11YO42B.

10" CHECK 5.000 GPM

Q2E21V076A 6" CHECK 3.000 GPM

Q2E21V0765 6" CHECK 3.000 GPM

Q2E21V077A 6" CHECK 3.000 GPM

Q2E21V0778 6" CHECK 3.000 GPM

.Q2E21V077C' 6" CHECK 3.000 GPM t

Indicates the requirements of Section 4.4.7.2.2 Item (c) are applicable.

The measured leak rate for any given test cannot reduce the difference between the results of the previous test and the maximum allowablo leakage specified in Table 3.4-1 by more than 50f.

9 FARLEY - UNIT 2 3/4 4-19 AMEN 0 MENT NO. 41

-_ -

v t e Letter Sequence Other
TAC:48714, (Approved, Closed) TAC:48715, (Approved, Closed)
Initiation Acceptance... Administration Questions Answers Results Approval Other: ML20106H351
MONTHYEAR1984-10-15 [Table View]

ML20106H351

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