ML20057A860

Amend 180 to License NPF-3,allowing Usage of Containment Atmosphere Gaseous Radioactivity Monitoring Sys as Alternate Method of Determining Presence of RCS Leakage & Clarifying Applicability of TS 4.0.4 Exceptions

ML20057A860
Person / Time
Site:	Davis Besse
Issue date:	09/09/1993
From:	Hopkins J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20057A861	List: ML20057A860 ML20057A863
References
NUDOCS 9309160088
Download: ML20057A860 (7)

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UNITED STATES

[.W) j NUCLEAR REGULATORY COMMISSION

• 44 WASHINGTON. D.C. 20ME0001 g

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TOLEDO EDISON COMPANY i

t CENTERIOR SERVICE COMPANY b.N.D THE CLEVELAND ELECTRIC ILLUMINATING COMPANY _

l DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1

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AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.180 License No. NPF-3 1

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

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated May 1, 1992, 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 wis' operate in conformity with the application,_the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) 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 tha. Commission's regulations; i

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; and E.

The isunce 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-3 is hereby amended to read as follows:

9309160088 930909 PDR ADOCK 05000346 P

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(a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.180, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jon B. Hopkins, Sr roject Manager Project Directorate III-3 Division of Reactor Projects III/IV/V' Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: September 9, 1993 O

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i ATTACHMENT TO LICENSE AMENDMENT NO.180 l

FACILITY OPERATING LICEMSE NO. NPF-3 DOCKET NO.60-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and

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contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 4-15 3/4 4-15 3/4 4-16 3/4 4-16 i

B 3/4 4-4 B 3/4 4-4 l

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i-REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE I

LIMITING CONDITION FOR OPERATION I

3.4.6.2 Reactor Coolant System leakage shall be limited tot a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAKAGE, c.

1 GPM total primary-to-secondary leakage through steam generators, d.

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

10 GPM CONTROLLED LEAKAGE, and f.

5 GPM leakage from any Reactor Coolant System Pressure Isolation Valve as specified in Table 3.4-2.

I APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

a.

Vith any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOVN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I b.

Vith any Reactor Coolant System leakage greater than any one offthe above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage l

rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least B0T STANDBY l

vithin 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 SHUTDOVN within the following 30 l

hours except as permitted by paragraph c below.

l c.

In the event that integrity of any pressure isolation valve specifie'd in Table 3.4-2 cannot be demonstrated, POVER OPERATION may continue, provided that at least two valves in each high pressure line having a non-functional valve are in and remain in, the mode corresponding to the isolated condition.(a) l l

d.

The provisions of Section 3.0.4 are not aoolicable.f.or entry l

i into MODES 3 and 4 for the purpose of testing the isolation valves in Table 3.4-2.

(*) Motor operated valves shall be placed in the closed position and power supplies deenergized.

1 DAVIS-BESSE, UNIT 1 3/4 4-15 6tddf 4/4. # 20/$1.

Amendment No. NM,180

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

Monitoring the containment atmosphere gaseous or particulate ~raaioactivity l

a.

at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Monitoring the containment sump level and flow indication at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

seals to the makeup system when the Reactor Coolant System pressure is 2185 20 psig at least once per 31 days.

d.

Performance of a Reactor Coolant System vater inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-2 shall be individually demonstrated OPERABLE by verifying leakage testing (or the equivalent) to be within its limit prior to entering MODE 2:

After each refueling outage, a.

b.

Whenever the plant has been in COLD SHUTDOVN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or more, and if leakage testing has not been performed in the previous 9 months, and Prior to returning the valve to service following maintenance, repair c.

or replacement work on the valve.

d.

The provisions of Specification 4.0.4 are not applicable for entry ints Modes 3 and 4.

4.4.6.2.3 Whenever the integrity of a pressure isolation valve listed in Table 3.4-2 cannot be demonstrated, determine and record the integrity of the high pressure flowpath on a daily basis.

Integrity shall be determined by performing either a leakage test of the remaining pressure isolation valve, or a combined leakage test of the remaining pressure isolation valve in series with the closed motor operated containment isolation valve.

In addition, record the position of the closed motor-operated containment isolation valve located in the high pressure piping on a daily basis.

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DAVIS-BESSE, UNIT 1 3/4 4-16 ppfy fpp. g/gpA Amendment No. 44, //f,180

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i REACTOR COOLANT SYSTEM i

l BASES (Continued) operation and by postulated accidents. Operating plants have demonstrated i

that primary-to-secondary leakage of 1 GPM can be detected by monitoring the i

secondary coolant.

Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will l

be located and plugged or repaired by sleeving in the affected areas.

l Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop it, service.

it will be found during scheduled inservice steam generator tube examina-j tions. As described in Topical Report BAW-2120P. degradation as small as j 20!. through wall can be detected in all areas.of a tube sleeve except for

, the roll expanded areas and the sleeve end, where the limit of detectability

. is 40'; through wall.

Tubes with imperfections exceeding the repair limit of i

• ; 40', of the nominal wall thickness will be plugged or repaired by sleeving 1

..the affected areas. Davis-Besse will evaluate, and as appropriate implement, j

l better testing methods which are developed and validated for comercial use j

so as to enable detection of degradation as small as 20% through wall without i

exception.

Until such time as 20% penetration can be detected in the roll

expanded areas and the sleeve end. inspection results will be compared to those j j obtained during the baseline sleeved tube inspection.

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!! Whenever the results of any steam generator tubing inservice inspection fal.1 1

into Category C-3, these results will be promptly reported to the Comission'

• pursuant to Specification 6.9.1 prior to resumption of plant operation. Such

! cases will be considered by the Commission on a case-by-case basis and may.

,. result in a requirement for analysis laboratory examinations, tests.

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additional eddy-current inspection, and revision of the Technical Specifica-tions, if necessary.

The steam generator water level limits are consistent with the initial t

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• : assumptions in the FSAR.

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i DAVIS-BESSE. UNIT 1 8 3/4 4-3 Amendment No.171 NE8R i

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REACTOR COOLANT SYSTEM BASES t

3/4.4.6 REACTOR COOLANT SYSTEM LEAragg 3/4.4.6.1 LEAKAGE DETECTION SYSTDt$

The RCS leakage detection systems required by this specification are provided to detect and monitor leakage from the Reactor Coolant Pressure Boundary.

These detection systems are consistent with the recomendation of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Deteetion Systems,! May Ig73.

3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE SOUNDARY LEAKAGE of ariy 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 $NUTDOWN.

Industry experience has shown that, wh!1e a limited amount of leakage is expected from the RCS. the UNIDENTIFIED LEAKAGE portion of this 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 total' steam generator tube leakage limit of 1 GPM for all steam generators ensures that the dosage contribution from tube leakage will be limited to a small fraction of 10 CFR Part 100 limits in the event of either{

1 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.

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

The CONTROLLED LEAKAGE limit of 10 GPM restricts operation with a total RCS leakage from all RC pump seals in excess of 10 GPM.

The surveillance requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the prob-ability of gross valve failure and consequent intersystem LOCA.

from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will beLeakage considered as a portion of the allowed limit.

DAVIS-SESSE. UNIT I 3 3/4 4,4 Amendment No.180 e-en 4

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