ML20100D472

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Amend 108 to License DPR-44,changing Tech Specs to Permit Reactor Operation W/Reload 6 (Cycle 7)
ML20100D472
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 03/19/1985
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20100D476 List:
References
DPR-44-A-108 NUDOCS 8504020462
Download: ML20100D472 (12)
v • d • e


Text

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[traecoy[g UNITED STATES a

g NUCLEAR REGULATORY COMMISSION 3

j WASHINGTON, D. C. 20555

,+....sI PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 i

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. DPR AA 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated September 7,1984, 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,

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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; 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 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. DPR-44 is hereby amended to read as follows:

8504020dkb2 850319 PDR ADOCK 05000277 P

PCR

7-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.108, are hereby incorporated in the license. PECO 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 REGUL TORY COMMISSION oh F. Stolz, Chief Op ating Reactors Branch #4 vision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 19,1985 i

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ATTACHMENT TO LICENSE AMENDMENT NO.108 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

Remove Insert iv iv.

119 119 133a 133a 133d 133d 133e 133e 142 142a 142a 142b 142e 142f 142i 1421 142k 241 241 4

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PBAPS Unit 2 LIST OF FIGURES Figure fItle

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Page 1.1-1 APRM Plow Bias Scram Relationship To 16 Normal Operating Conditions 4.1.1 Instrument Test Interval Determination 55 Curves 4.2.2 Probability of System Unavailability 98 Vs. Test Interval 3.4.1 Required Volume and Concent' ration of 122 Standby Liquid Control System Solution 3.4.2 Requ' ired Temperature vs. Concentration 123 for Standby Liquid Control System Solution 3.5.K.1 Deleted 142 l

1 3.5.K.2 MCPR Operating Limit vs. Tau, P8X8R fuel 142a 3.5.K.3 Deleted 142bl 3.5.1.E Kf Factor Vs. Core Flow 142d 3.5.1.F.

Deleted 142e l 3.5.1.G Caleted 142f l 3.5.1.H MAPLEGR Vs. Planar Average Exposure, 142g i

Unit 2, P 8X8R Fuel, Type P8DRB285, 100 mil channels f

3.5.1.I MAPLHGR vs. Planar Average Exposure, 142h Unit 2, P 8x8R Fuel, Type P8DRB284 H, i

80 mil & 100 mil channel & 120 mil channels 3.5.1.J.

MAPLHGR vs. Planar Average Exposure 1421

- i Unit 2, P8X8R and BP8X8R Fuel, Type P8DRB299

].

and BP8DRB299, 100 mil channels 3.5.1 K.

MAPLHGR vs. Planar Average Exposure 142j Unit 2, P8X8R Fuel (Generic) 3.5.1.L.

MAPLBGR vs. Planar Average Exposure 142kl Unit 2, BP8X8R Fuel, Type BP8DRB299H.

4 1

-iv-Amendment No. )$, $9, Q, JS, 79, $$,108

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1 PBAPS 3.4 BASES STANDBY LIQUID CONTROL SYSTEM A.

The conditions under which the Standby Liquid Control System must provide shutdown capability are identified via the Plant Nuclear Safety Operational Analysis (Appendir G).- If no more than one operable control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and the Standby Liquid Control system is not required.

Thus, the basic reactivity requirement for the core is the primary determinant of when the liquid control system is required.

The purpose of the liquid control system is to provide the capability of bringing the reactor from full power to a cold, 3

xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted.

To meet this objective, the liquid control system is designed to inject a quantity of boron that produces a concentration of 660 ppm of boron in the reactor core in less than 125 minutes.

The 660 ppm concentration in the reactor core will br'ing the reactor from full power to a subcritical condition, considering the l

hot to cold reactivity difference, xenon poisoning, etc.

The time requirement for inserting the boron solution was selected to override the rate of reactivity insertion caused by cooldown of the reactor following the xenon poison peak.

The minimum limitation on the relief valve setting is intended to prevent the recycling of liquid control solution via the lifting of a relief valve at too low a pressure.

The upper limit on the relief valve setting provides system protection from overpressure.

B.

Only one of the two standby liquid control pumping loops is needed for operating the system.

One inoperable pumping circuit does not immediately threaten shutdown capability, and reactor operation can continue while the circuit is being repaired.

Assurance that the remaining system will perform j

its intended function and that the long term average 1

availability of the system is not reduced is obtained for a j

one out of two system by an allowable equipment out of service time of one third of the normal surveillance i

frequency.

This method determines an equipment out of I

service time of ten days.

Additional conservatism is i

introduced by reducing the allowable out of service time to

.I seven days, and by increased testing of the operable redundant component.

i i

Amendment No. 77, 76, 79,108 I

PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE _ REQUIREMENTS 3.5.I Average Planar LHGR 4.5.I Average Planar LHGR During power operation, the APLHGR The APLHGR for each type of fuel for each type of fuel as a function as a function of average planar of average planar exposure shall not exposure shall be checked daily exceed the limiting value shown in.

during reactor operation at the applicable figures during two

>25% rated thermal power.

recirculation loop operations.

During single loop operation, the APLHGR for each fuel type shall not exceed the above values multiplied by the following reduction factor: 0.79 for P8X8R and BP8X8R fuel.

If at any time '

during operation it is determined by normal surveillance that the limiting value of APLHGR is being exceeded, action shall be i

initiated within one (1) hour to restore APLHGR to within prescribed limits.

If the APLHGR is not returned to within prescribed limits within five (5) hours reactor power shall be decreased at a rate which would bring the reactor to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless APLHGR is returned to within limits during this period.

Surveillance and corresponding action shall continue until reactor operation t

is within the prescribed limits.

3.5.J Local LHGR 4.5.J Local LHGR j

During power operation, the linear The LHGR as a function of core heat generation rate (LHGR) of any height shall be checked daily rod in any fuel assembly at any during reactor operation at axial location shall not exceed

>25% rated thermal power.

design LHGR.

LHGR < LHGRd LHGRd = Design LHGR

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13.4 kW/ft for all 8X8 fuel l

Amendment No. 49, pp. 79. 7$. S$.108 j

-133a-L

PBAPS Unit 2 Table 3.5.K.2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

  • MCPR Operating Limit **

Fuel Type For Incremental Cycle Core Average Exp,os,ure BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC i

P8X8R ***

1.23 1.29 l

If requirement 4.5.K.2.a is met.

These values shall be increased by 0.01 for single loop operation.

      • Applicable to all P8X8R fuel bundles including BP8X8R l

and the P8DRB285 (Reload 5) types.

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Amendment No, pp,108

-133d-l

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PBAPS Unit 2 Table 3.5.K.3 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

  • MCPR Operating Limit **

Fuel Type For Incremental Cycle Core Average Exposure BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC P8X8R***

1.34 1.41 l

If surveillance requirement 4.5.K.2 is not performed.

These values shall be increased by 0.01 for single loop operation.

      • Applicable to all P8X8R fuel bundles including BP8X8R l

and the P8DRB285 (Reload 5).t.ypes.

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l Amendment No. $5,108

-133e-

PEACH BOTTOM UNIT 2

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FIGURE MCPR OPERATING LIMIT vs 7 P8K8R*

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'FBAPS UNIT 2 5.0 MAJOR DESIGN FEATURES 5.1 SITE FEATURES The site is located partly in Peach Bottom Township, York County, partly in Drumore Township, Lancaster County, and partly in Fulton Township, Lancaster County, in southeastern Pennsylvania on the westerly shore of Conowingo Pond at the mouth of Rock Run Creek.

It is about 38 miles north-northeast of Baltimore, Maryland, and 63 miles west-southwest of Philadelphia, Pennsylvania.

Figures 2.2.1 through 2.2.4 of the FSAR show the site location with respect to surrounding communities.

5.2 REACTOR A.

The core shall consist of not more than 764 fuel assemblies.

B.

The reactor core shall contain 185 cruciform-shaped control rods, 5.3 REACTOR VESSEL i

The reactor vessel shall be as described in Table 4.2.2 of the FSAR.

The applicable design codes shall be as described in Table 4.2.1 of the FSAR.

5.4 CONTAINMENT A.

The principal design parameters for the primary containment shall be as given in Table 5.2.1 of the FSAR.

The applicable design codes shall be as described in Appendix M of the FSAR.

B.

The secondary containment shall be as described in Section 5.3 of the FSAR.

C.

Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.3.4 of the FSAR.

Amendment No. U, Q, 79,108

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