ML20034B678

Amends 52 & 51 to Licenses DPR-80 & DPR-82,respectively, Changing Scheduled Date for Removal of Boron Injection Tank from Unit 2

ML20034B678
Person / Time
Site:	Diablo Canyon
Issue date:	04/20/1990
From:	Bevan R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034B679	List: ML20034B678 ML20034B680
References
NUDOCS 9004300183
Download: ML20034B678 (10)

Text

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NUCLEAR REGULATORY COMMISSION t

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\\..n.-,f PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-80 1.

The Nuclear Regulatory Comission (the Comission) has found that:.

A.

The application for amendment by Pacific Gas & Electric Company (thelicensee),datedMarch 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954 as amended (the Act).andtheCommission'sregulationssetforthIn10CFR' Chapter I; B.

The facility will o)erate in conformity with the application the provisions of tie Act, and the regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endarsgering the health 3

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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 have t

been satisfied.

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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. DPR-80 is hereby amended to read as follows:

(2)_TechnicalSpecifications The Technical Specifications contained in Appendices and the Environmental Protection Plan contained in Appendix B, as revised through Amendnent No. 52, are hereby incorporated in the, license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendrent becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Roby_Bevan, Acting Director Project Directorate V Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical i

Specifications Date of Issuance: April 20, 1990 i

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NUCLEAR REGULATORY COMMISSION

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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNIT 2 DOCKET NO. 50-323 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. OPR-82 1.

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

A.

'The application for amendment by Pacific Gas & Electric Company (the licensee), dated March 14, 1990 complies with the standards and requirements of the Atomic Energy, Act of 1954, as amended (the i

Act), and the Commission's regulations set forth in 10 CFR Chapter It 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; 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 issuance of this amendment is in-accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requireinents have been satisfied.

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Accordingly, the license is arended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License

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No. DPR-82 is hereby amended to read as follows:

(2) Technical Specifications i

The Technical Specifications contained in Appendices an,i the.

Environmental. Protection Plan contained in Appendix B, td revised through Amendment No. 31, are hereby incorporated in the license.

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Pacific Gas & C 1.tric Company shall operate the facility in, accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license

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conditions.

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This license amendment becomes effective at the date of its issuance.

FOR TH'i NUCLEAR REGULATORY COMMISSION

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Roby Bevan, Acting Director j

Project Directorate V Division ofiReactor Projects III, IV, y and Special Projects l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance; April 20, 1990 1

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e ATTACHMENT TO LICENSE AMENDMENT NOS. 52-AND $1 FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 Replace the followin the attached pages. g ) ages of the Appendix "A" Technical Specifications with T1e revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. Overleaf pages are also included, as appropriate.

Remove Page Insert Page-3/4 3 31 3/4 3 3/4 5-9 3/4 5-9 3/4 5-10 3/4 5-10 B 3/4 5-2 B 3/4 5-2 i

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l TABLE 3.3-5 (Continued)

TABLE NOTATIONS (1) Diesel generator starting delay not included because offsite power available.

(2) Feedwater System overall response time shall include verification of each l

individual Feedwater System valve closure time as shown below:

Closure Time (not including Valve instrumentation delays)

FCV-438

< 60 seconds-439 7 60 seconds 440 7 60 seconds 441 7 60 seconds

$10 7 5 seconds i

520 7 5 seconds i

530 7 5 seconds 1

540 7 5 seconds 1510 7 5 seconds 1520 7 5 se*conds 1530 7 5 seconds 1540 7_ 5 seconds (3) Diesel generator starting and loading delays included.

(4) Diesel generator starting delay not included because offsite power is _

available.

Response time limit includes openbig of valves to establish i

SI path and attainment of discharge pressure for centrifugal charging j

pumps (where applicable).

Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

For Units 1 and 2 Cycle 4, the Safety Injection response time limit shall be as follows:

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Pressurizer Pressure-Low

< 12-I Differential Pressure Between Steam Lines-High-7 13 t

Steam Flow in Two Steam Lines-High Coincident i

with T

-Low-Low

< 15 SteamF18w1nTwoSteamLines-HighCoincident 9

~

h with Steam Line Pressure Low

< 13 Diesel generator starting delay not included because offsite power is j

available.

Response time limit includes opening of valves to establish SI i

path a.id attainment of discharge pressure for centrifugal charging pumps l

1 (where applicable).

(5) Diesel generator starting and sequence loading delays included.

Offsite t

power is not available.

Response time limit includes opening of: valves 1

to establish SI charging pumps. path and attainment of discharge pressure for centrifugal Sequential transfer of charging pump suction from the l

VCT to the RWST (RWST valves open, then VCT valves close) is included.

DIABLO CANYOH - UNITS 1 & 2 3/4 3-31 Amendment Nos. 52 and 51

H TABLE 3.3-5 (Continued)

_ TABLE NOTATIONS For Units 1 and 2 Cycle 4, the Safety Injection response time limit shall l

be as follows:

i

. Differential Pressure Between Steam Lines-High

< 23 Steam Flow in Two Steam Lines-High Coincident

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with T

-Low-Low

< 25 i

SteamFIN91n Two Steam Lines-High Coincident

~

with Steam Line Pressure-Low 5, 23 4

Diesel generator startin and sequence loading delays' included.

Response

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time limit includes open ng of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps (where applicable).

j (6) The maximum response time of 48.5 seconds is the time from when the con-tainment pressure exceeds the High-High Setpoint until the spray pump is.

i started and the discharge valve travels to the fully'open position assuming j

off-site power is not available.

The time of 48.5 seconds includes the 28-second maximum delay related to ESF loading sequence.

Spray riser piping fill time is not included.

The 80'-second maximum spray delay time does not include the time from LOCA start to "P" signal.

l (7) Diesel generator starting and sequence loading delays' included.

Sequential transfer of charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is not included.

Response time-limit includes opening of valves to establish SI flow path and attainment of discharge pressure for centrifugal charging pumps, SI, and RHR pumps j

(where applicable).

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DIABLO CANYON - UNITS 1 & 2 3/4 3-31a

'Amehdment Nos. 52 and ~1.

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• J EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 BORON INJECTION SYSTEM BORON INJECTION TANK LIMITING CONDITION FOR OPERATION 3.5.4.1 The boron injection tank shall be OPERABLE with:

A minimum contained borated water volume of 900 gallons of borated a.

water, b.

A boron concentration of between 20,000 and 22,500 ppm, and c.

A minimum solution temperature of 145'F.

APPLICABILITY: MODES 1, 2 and 3.

For Units L and 2 Cycle 4 ACTION:

With the boron injection tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in HOT STANDBY and borated to a SHUTOOWN MARGIN equivalent to 1% ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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$URVEILLANCE REQUIREMENTS 4.5.4.1 The boron injection tank shall be demonstrated OPERABLE by:

Verifying the contained borated water volume through a recirculation a.

flow test at least once per 7 days, b.

Verifying the boron concentration of the water in the tank at least once per 7 days, and 4

Verifying the water temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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I DIABLO CANYON - UNITS 1 & 2 3/4 5-9 Amendment Nos. 52 and 51

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EMERGENCY CORE COOLING SYSTEMS HEAT TRACING LIMITING CONDITION FOR OPERATION i

3.5.4.2 At least two independent channels of heat tracing shall be OPERABLE l

for the boron injection tank and for the heat traced portions of the associated flow paths.

APPLICABILITY:

MODES 1, 2 and 3.

For Units 1 and 2 Cycle 4.

ACTION:

i With only one channel of heat tracing on either the boron injection tank or on the heat traced portion of an associated flow path OPERABLE, operation may continue for up to 30 days provided the tank and flow path temperatures are verified to be greater than or equal to 145'F At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />;.

otherwise, 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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SURVEILLANCE REQUIREMENTS 4.5.4.2 Each heat tracing channel for the boron injection tank and associated flow path shall be demonstrated OPERABLE:

At least once per 31 days by energizing each heat tracing channel, a.

and b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the tank and flow path tem-peratures to be greater than or equal to 145'Fi The tank temperature l

Shall be determined by measurement.

The flow path temperature shall be determined by either measurement or recirculation flow until establishment of equilibrium temperatures within the tank, i

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DIABLO CANYON - UNITS 1 & 2 3/4 5-10 Amendment Nos. 52 and 51 o

EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)

The. requirement to maintain the RHR Suction Valvos 8701 and 8702 in the locked closed condition in MODES 1, 2 and 3 provides assurance that a fire could not cause inadvertent opening of these valves when the RCS is pressur-12ed to near operating pressure.

These velves are not part of an 2005 subsystem.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all centrifugal charging pumps and Safety Injection pumps except the required OPERABLE charging pump to be inoperable below 323'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The Surveillance Requirements provided to ensure 0PERABILITY of each component ensures that, at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.

Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA.

Maintenance of proper flow resistance and pressure drop in the piping system to each t

injection point is necessary to:

(1) prevent tou.1 pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable i

level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

3/4.5.4 BORON INJECTION SYSTEM The Boron Injection System is only required for Units 1 and 2 Cycle 4.

The OPERABILITY of the Boron Injection System as part of the ECCS ensures that-li sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS cooldown.

RCS cooldown c n be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.

The limits on injection tank minimum contained volume and boron concentra-l tion ensure that the assumptions used in the steam line break analysis are met, The contained water volume limit includes an allowance. for water not usable because of tank discharge line location or other physical characteristics.

The OPERABILITY of the redundant heat tracing channels associated with the boron injection system ensure that the solubility of the boron solution will be maintained above the solubility limit of 135'F at 21,000 ppm boron.

DIABLO CANYON - UNITS 1 & 2 B 3/4 5-2 Amendment Nos. 52 and 51