ML20054D178

Amend 50 to License DPR-66,changing Allowable Test Time for Solid State Protection Sys Instrumentation Channels & Purge & Exhaust Valve Isolation Requirements

ML20054D178
Person / Time
Site:	Beaver Valley
Issue date:	04/05/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20054D173	List: ML20054D172 ML20054D178 ML20054D186 ML20054D193
References
NUDOCS 8204220414
Download: ML20054D178 (7)

Text

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UNITED STATES

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'h NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555 f

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DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. DPR-66 1.

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

A.

The application for amendment by Duquesne Light Company, Ohio EdfLson Company, and Pennsylvania Power Company (the licensees) datsd November 9,1981, 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, the provisions of the Act, and the rules and 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 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 nave been satisfied.

e204220414 820405 DRADOCKOS000g

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Accordingly, the license is amended by changes to the Tecnnical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-06 is hereby amended to read as follows:

(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 Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION O

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Chief /

Operating Reactors Branch 1 Division of Licensing

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Attachment:

Changes to the Technical Specifications Date of Issuance:

April 5,1982

V ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:

Remove Pages Insert Pages 3/4 3-20 3/4 3-20 3/4 6-19c 3/4 6-19c 3/4 9-4 3/4 9-4 3/4 9-9 3/4 9-9 1

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TABLE 3.3-3 (Continued)

"rABLE NOTATION

1. rip function may be bypassed in this MODE below P-11.

T EAhihe channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

ACTION STATEMENTS ACTION 13 - With.the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CC:_D SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1., provided the other L

channel is operable.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels:

a. Below P-il or P-12, place the inoperable channel in the tricoed condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding F-ll or F-12; otherwise be in at least HOT STANDBY within the following 6 nours.

b. A:cve P-11 and F-12, place the inoperable channel in the trio:ed condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may continue until performance of the rext required CHANNEL FUNCTIONAL TEST.

ACTION 15 - With a channel associated with an cperating loop inoperable, restore the inoperable channel to GPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for' up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.

ACTION 16 - With the number of OPERABLE Channels one less than the Total Number of Channels:

a. Below P-11 or P-12, place the inoperable channel in the bypass condition; restore tne inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding P-11 or i

P-12; otherwise be in at least HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

BEAVER VALLEY - UNIT 1 3/4 3-20 Amendment No. 50

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_ TABLE 3.6-1 (Continued) ni ISDLATION TIME 35 VALVE NUMBER TESTABLE DURING (Sec) 03 INSIDE/0UTSIDE FUNCTION PLANT OPERATION INSIDE/0UTSIDE 5

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C.

Containment Purge and Exhaust Q

1.

VS-D-5-38 VS-D-5-3A Containment Purge Exhaust No 8 (1) 8 (1) 2.

VS-D-5-5B VS-D-5-5A Containment Purae Supply No 11 (1) 8 (1) c-3.

VS-D-5-6 Containment Purae Vacuum Breaker No N/A N/A

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D.

Manual T

1.

ICH-181 MOV-CH308A Seal Injection Water to RC Pump No N/A N/A a

2.

1C11-182 MOV-CH308B Seal In.iection Water to RC Pumo No N/A N/A 3.

ICH-183 MOV-CH308C Seal Injection Water to RC Pump No N/A N/A

• 4 MOV-CH142 Reactor Coolant System Letdown Yes N/A N/A

• S.

MOV-CC11283 1CCR-252 CCW from RHR Hx & RHR Pump Seal Coolers Yes N/A N/A

• 6.

MOV-CC112A3 1CCR-251 CCW f rom RHR Hx A RHR Pump Seal Coolers Yes N/A N/A

• 7.

MOV-CC112A2 lCCR-247 CCW to RHR Hx A RilR Pump Seal Coolers Yes N/A N/A g.

• 8.

HOV-CC11282 1CCR-248,

CCW to RilR lix & RilP Pump Seal Coolers Yes N/A N/A

1. 9.

.MOV-FW-151A Auxiliary Feedwater Yes N/A N/A 3

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1. 10.

MOV-FW-151 R Auxiliary Feedwater Yes N/A N/A g

1. 11.

MOV-FW-151C Auxiliary Feedwater Yes N/A N/A

1. 12.

MOV-FW-151D Auxiliary feedwater Yes N/A N/A gf

1. 13.

MOV-FW-151E Auxiliary feedwater Yes N/A N/A

1. 14.

HOV-FV-151 F Auxiliary Feedwater Yes N/A N/A

1. 15.

MOV-RW104A Riverwater to Recirc. Spray Hx Yes N/A N/A

1. 16.

MOV-RW104C Riverwater to Recirc. Spray lix Yes N/A N/A

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1. 17.

MOV-RWin4B Riverwater to Recirc. Spray HX Yes N/A N/A q:

1. 18.

.MOV-RW104D Riverwater to Recric. Spray lix Yes N/A N/A

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E (1) APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

The provisions of specification 3.0.4 are not applicable. The Containment Purge Exhaust and Supply valves will be locked shut during operation in modes 1, 2, 3, and 4.

REFUELING OPERATIONS CONTAINMENT BUILDING FENETRATIONS

_ LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:

a.

The equipment door closed and held in place by a minimum of four bolts, b.

A minimum of one door in each airlock is closed, and c.

Each penetration providing direct access frem the containment atmosphere to the outside atmosphere shall be either:

l.

Closed by an isolation valve, blind flange, or manual valve, or 2.

Exhausting at less than or equal to 7500 cfm through OPERABLE Containment Purge and Exhaust Isolation Valves with isolation times as specified in Table 3.6-1 to l

OPERABLE HEPA filters and charcoal adsorbers of the Supplemental Leak Collection and Release System (SLCRS).

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, innedi-ately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.

SURVEILI.ANCE REOUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be determined to be in its above required condition within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment.

4.9.4.2 The containment purge and exhaust system shall be demonstrated OPERABLE by:

a.

Verifying the flow rate through the SLCRS at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the system is in operation.

b.

Testing the Containment Purge and Exhaust Isolation Valves per the applicable portions of Specificatien 4.6.3.1.2, and c.

Testing the SLCRS pe-Specification 4.7.8.1.

BEAVER VALLEY - UNIT 1 3/4 9-4 Amendment No.d8 l

50

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REFUELING OPERATIONS CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purce and Exhaust isolation system shall be OPERABLE.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel withint the containment.

ACTION:

With the Containment Purge and Exhaust isolation system inoperable, close each of the purge and exhaust eenetrations providino direct actass from the containment atmosphere to the outside atmosphere.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 150 ho:rs prior to the start of and at least once per 7 days durino CORE A*.TERATIONS by verifyino that contain-ment Purae and Exhaust isolation oc:urs on manual initiation and on a high-hich radiation signal from eat of the containment radiation 1

monitorino instrumentation channels.

50 BEAVER VALLEY - UNIT 1 3/t 9-9 Amendrent No. /)