ML20247B346

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Amend 112 to License DPR-54,revising Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1
ML20247B346
Person / Time
Site: Rancho Seco
Issue date: 07/17/1989
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247B302 List:
References
NUDOCS 8907240098
Download: ML20247B346 (7)
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Text

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,k UNITED STATES -

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K  ?, . NUCLEAR REGULATORY COMMISSION-8 WASHINGTON, D. C. 20555 t

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SACRAMENTO. MUNICIPAL. UTILITY. DISTRICT.

DOCKET.NO. 50 312 RANCHO SECO NUCLEAR GENERATING. STATION AMENDMENT.TO. FACILITY OPERATING. LICENSE Amendment No. 112 License No. DPR-54

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

A. The application for amendment by Sacremento Municipal Utility District (the licensee) dated February 28, 1986, as revised May _14,1987, and-August 31, 1988, complies with that standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Corinission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the 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 the Commission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 beer, satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment. and para-graph 2.C.(2) of Facility Operating License No. DPR-54 is hereby ' amended to read as follows: {

(2) Technical. Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, g2ggoh d2 P

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3. This license amendment shall become effective >:ithin 30 days of the issuance date. The implementation delay is provided to allow time for modification of affected procedures and proinulgation of the changes to personnel.

FOR TilE NUCLEAR REGULATORY COMMISSION

[ M George W. Knightca, Director Project Directorate V Division of Reactor Projects III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: July 17, 1989 1

IJ V,. . ..: .

ATTACHMENT TO LICENSE AMENDMENT NO.112 FACILITY OPERATING' LICENSE NO. DPR-54

-DOCKET NO. 50-312 Replace the following pages of the Appendix "A"_ Technical Specifications .

with the, attached pages. The revised pages are identified by Amendment number-and contain vertical lines indicating the area of change.

r Remove Insert 3-39 3-39 3-40 .3-40 3-40a 3-40a 3-40b

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.6 REACTOR BUILDING -

Anolicability All modes from HEATUP-COOLDOWN through POWER OPERATION, inclusive.

Obiective 4

To assure containment integrity.

Specification 3.6.1 Containment integrity sh?ll be maintained.

Action Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT SHUTDOWN 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 />.

3.6.2 Containment integrity shall be maintained when the reactor coolant-system is open to the containment atmosphere and the requirements for a refueling shutdown are not met. 1 3.6.3 Positive reactivity insertions which would result in the reactor being subtritical by less than 1 percent Ak/k shall not be made by control rod motion or boron dilution whenever the containment integrity is not intact. -

3.6.4 The reactor shall not remain critical if the Reactor Suilding internal pressure exceeds 1.5 psig or vacuum exceeds -1.5 psig.

3.6.5 Prior to criticality following refueling shutdown, a check shall be made to confirm that all manual containment isolation valves which should be closed are closed.

3.6.6 The containment lsolation valves specified in Table 3.6-1 shall be OPERABLE with closure times ~as'shown in Table 3.6-1.

If, under reactor critical operating conditions an automatic containment isolation valve is determined to be inoperable, the other containment isolation valve in the line shall be tested to ensure operability. If the inoperable valve is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be brought to the cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the valve will be placed in a safety features position.

3-39 A. endment No. 31,97,16d,112

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.6-1 CONTAINMErlf ISOLATION VALVES NORMAL (1) MAXIMUM AUTO OPERATING CLOSURE VALVE NUMBER DESCRIPTION ISQL, POSITION TIME. sec.

SFV-22009 RC System Letdown AB Side YES OPEN 25 SFV-22023 RC System Letdown, RB Side YES OPEN 25 SFV-24004 RC Pump Seal Return, RB Side YES OPEN < 60 SFV-24013 RC Pump Seal Return, AB Side YES OPEN 12 SFV-46014 RB. CCH Supply, AB Side NO OPEN 14 SFV-46203 RB CCH Return, RB Side NO OPEN 14 SFV-46204 RB CCW R3 turn, AB Side .

NO OPEN 18 SFV-46906 CRD Cooling Hater Supply, AB Side NO OPEN 13 SFV-46907 CR0 Cooling Water Return, RB Side NO OPEN 14 SFV-46908 CRD Cooling Water Return, AB Side NO OPEN 11 SFV-53503 RB Purge Inlet, AB Side YES CLOSED (2) 25 SFV-53504 RB Purge Inlet, RB Side YES CLOSED (2) 25 SFV-53603 RB Press. Equalizer, RB Side YES CLOSED 25 SFV-53604 RB Purge Outlet, AB Side YES CLOSED (2) 25 SFV-53605 RB Purge Outlet, RB Side YES- CLOSED (2) 25 SFV-53610 RB Press. Equalizer, AB Side YES CLOSED 25 SFV-53612 RB Atm. Purge Sample, AB Side YES OPEN 25 l SFV-53613 RB Atm. Rad. Sample, AB Side YES OPEN 25 SFV-53615 Reactor Building Hydrogen Purge YES OPEN 25 SFV-53616 Reactor Building Hydrogen Purge YES OPEN 25 SFV-60001 RC System Vent 1501., RB Side YES OPEN 25 SFV-60002 RC System Vent 1501., AB Side YES OPEN 25 SFV-60003 RC System Drain Isol., AB Side YES OPEN 25 SFV-60004 RC System Drain Isol., AB Side YES OPEN 25 SFV-66308 RB Normal Sump Drain, AB Side YES OPEN 25 SFV-66309 RB Normal Sump Drain, AB Side VES OPEN 25 SFV-70001 Przr. Liquid Sample Isol., RB Side YES CLOSED 25 SFV 70002 Przr. Liquid Sample Isol., AB Side YES CLOSED 25 SFV-70003 Przr. Vapor Sample Isol., RB Sioe YES CLOSED 25 SFV-72501 Przt. Grs Sample Isol., RB Side YES CLOSED 25 SFV-72502 Przt. Gas Sample Isot., AB Side YES CLOSED 25 SFV-92520 Przt. Nitrogen 1s01., AB Side YES CLOSED 25 1

(1) Valves without auto-isolation may be open provided the controls for the respective valve are attended by an operator. Auto-isolation valves may be in any position.

(2) See Section 3.6.7 Amendment No. 31, 72, 87, 112 3-40

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES NORMAL (1) HAXIMUM AUTO OPERATING CLOSURE VALVE NUMBER DESCRIPTION 15DL, POSITION TIME. set.

HV-20593 OTSG-A Sample Isol., AB Side NO CLOSED 12 HV-20594 OTSG-B Sample Is.?.. AB Side NO CLOSED 5 HV-20609 OTSG-A Blowdown Isol., RB Side NO CLOSED 15 HV-20610 OTSG-B Blowdown Isol., RB Side NO CLOSED 14 HV-20611 OSTGs Blowdown Isol., AB Side NO CLOSED 22 HV-53617 Reactor Building Hydrogen Purge NO CLOSED 25 HV-53618 Reactor Building Hydrogen Purge NO CLOSED 25 i HV-70040 Hydrogen Monitor Containment Outlet Isol. NO CLOSED 25 HV-70041 Hydrogen Monitor Containment Inlet Isol. NO CLOSED 25 HV-70042 Hydrogen Monitor Containment Inlet Isol. NO CLOSED 25 HV-70043 Hydrogen Monitor Containment Outlet Isol. Nf CLOSED 25 HV-70044 Hydrogen Monitor Containment Outlet 1501. NO CLOSED 25  ;

HV-70045 Hydrogen Monitor Containment '

Inlet Isol. NO CLOSED 25 HV-70046 Hydrogen Monitor Containment Inlet Isol. NO CLOSED 25 ,

HV-70047 Hydrogen Monitor Containment '

Outlet Isol. NO CLOSED 25 (1) Valves without auto-1 solation may be oper, provided the controls for the respective valve are attended by an operator. Auto-isolation valves may be i in uny position.

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l Amendment No. 112 3-40a L____ -

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.6.7 The Reactor Building Purge Valves, SFV 53503, SFV 53504, SFV 53604, and

.SFV 53605, shall be closed with their respective breakers de-energized, except during cold shutdown or refueling. Valves SFV 53303 and SFV 53604 shall be verified to be in the above condition at least monthly. The breakers / disconnects on valves SFV 53504 and SFV 53605 shall be verified to be de-energized at least monthly.

3.6.8 The Reactor Building Purge Valves shall isolate on high containment' radiation level. See Table 3.5.1-1 for operability requirements.

BA111

.The reactor coolant system conditions of cold shutdown assure that no steam will be formed and hence no pressure buildup in the containment if the reactor coolant system ruptures.

The selected shutdown conditions are based on the type of activities that are being carried out and will preclude criticality in any occurrence.

The Reactor Building is designed for an internal pressure of 59 psig and an external pressure 2.0 psi greater than the internal pressure. The design external pressure corresponds to the differential pressure that could.be developed if the building is sealeu with an internal temperature of 120'F with a barometric pressure of 29.0 inches of Hg and the building is subsequently cooled to an internal temperature of 80*F with a concurrent rise in barometric pressure to 31.0 inches of Hg.

When containment integrity is established, the limits of 10 CFR 100 will not be exceeded should the maximum hypothetical accident occur.

The OPERABILITY of the containment isolation ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere by pressurization of the containment. Containment isolation within the time limits specified for valves which receive an automatic isolation signal ensures that the release of radicartive material to the environment will be consistent with the assumptions used in the analyses for LOCA. Valves which are permitted to be open during plant operation are 61ther part of closed systems which would not cause releases to the environment, or are administrative 1y controlled to ensure their rapid closure in the event of an accident.

Specifications 3.6.7 and 3.6.8 are in response to NUREG 0737 item II.E.4.2.

REFEREEE (1) USAR, section 5 l

Amendment No. 31, 49, 87, 112 3-40b

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