ML14183A110

Amend 115 to License DPR-23,revising Tech Spec to Permit Plant Operation at Less than 1,380 Mwt W/Only Two Safety Injection Pumps Operable

ML14183A110
Person / Time
Site:	Robinson
Issue date:	03/07/1988
From:	Lainas G Office of Nuclear Reactor Regulation
To:
Shared Package
ML14183A111	List: ML14183A110 ML14183A112
References
DPR-23-A-115 NUDOCS 8803110005
Download: ML14183A110 (15)

Text

UNITED STATES 0,NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No. DPR-23

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

A. The application for amendment by Carolina Power & Light Company.

(the licensee), dated February 24, 1988, as supplemented February 26, 1988, and March 1, 1988, 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 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 3.3 of Facility Operating License No. DPR-23 is hereby amended to read as follows:

T903 0

5006 PDR ADOCi PDR P

-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 115, are hereby incorporated in the license. Carolina Power &

Light Company 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 RE ULATORY COMMISSION Gus C. Lainas, Assistant Director for Region II Reactors Division of Reactor Projects I/Il

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 7, 1988 LA:P

,PR PM:PD RPR OGC-B Us?

.DRPR R

1f AD RR PAnd RLo E

n am LReyes G

s 3/3 /88 3/

88 3/ /88 3/&\\ /88 3/ri/

88 3//88

ATTACHMENT TO LICENSE AMENDMENT NO. 115 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages, as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 3.3-2 3.3-2 3.3-3 3.3-3 3.3-4 3.3-4 3.10-2 3.10-2 3.10-2a 3.10-2a 3.10-3 3.10-3 3.10-3a 3.10-3a 3.10-4 3.10-4 3.10-4a 3.10-4a 3.10-5 3.10-5 3.10-5a 3.10-5a 3.10-22 3.10-22

b.

Each accumulator is pressurized to at least 600 pai and contains at least 825 ft3 and no more than 841 ft of water with a boron concentration of at least 1950 ppm. No accumulator may be isolated.

c. Three safety injections pumps are operable.*

d. Two residual heat removal pumps are operable.

e. Two residual heat exchangers are operable.

f. All essential features including valves, interlocks, and piping associated with the above components are operable.

8. During conditions of operation with reactor coolant pressure in excess of 1000 psi 5 the A.C. control power shall be removed from the following motor operated valves with the valve in the specifiedposition:

Valves Position MOV 862 AAB Open MOV 864 AAB Open MOV 865 A,8,6C Open MOV 878 AAB Open NOV 863 A68 Closed NOV 866 A8 Closed

h.

During conditions of operation with reactor coolant pressure in excess of 1000 psig, the air supply to air operated valves 603 and 758 shall be shut off with valves in the closed position.

With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, the reactor may be made critical; however, steady state reactor core power level shall not exceed 1380 megawatts thermal. Prior to exceeding 1380 megawatts thermal, NRC review and approval is required.

3.3-2 Amendment No. 97, 115

I. Power operation with less than three loops in service is prohibited.

3.3.1.2 During power operation, the requirements of 3.3.1.1 may be modified to allow any one of the following components to be inoperable. If the system is not restored to meet the requirements of 3.3.1.1 within the time period specified, the reactor shall be placed in the hot shutdown condition utilizing normal operating procedures. If the requirements of 3.3.1.1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.

a. One Accumulator may be isolated for a period not to exceed four hours.

b. If one safety injection pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the remaining two safety injection pumps are demonstrated to be operable prior to initiating repairs.*

c. If one residual heat removal pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the other residual heat removal pump is demonstrated to be operable prior to initiating repairs.

For reactor core power levels up to and including 1380 megavatts thermal, Specification 3.3.1.2.b shall be modified to read$ "If one of the two automatically initiated safety injection pumps becomes inoperable, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the remaining automatically initiated safety injection pump is desonstrated to be operable prior to initiating repairs."

3.3-3 Amendment No.

,1

d. If one risidual heat exchange 'ecomes inoperable during normal reactor operation, aheactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

e. If any one flow path including valves of the safety injection or residual heat removal system is found to be inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the other flow path(s) are demonstrated to be operable prior to initiating repairs. The hot leg injection paths of the Safety Injection System, including valves, are not subject to the requirements of this specification.

f.

Power or air supply may be restored to any valve referenced in 3.3.1.1.g. and 3.3.1.1.h. for the purpose of valve testing or maintenance providing no more than one valve has power restored and provided that testing and maintenance is completed and paver removed vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except for accumulator isolation valves (HOV 865 A,3,6C) which will have this tine period limited to four hours.

3.3.4 Amendment No. 9//,77, 115

3.10.1.5 Except for physics tests, if a full length control rod is withdrawn as follows:

at positions ' 200 steps and is > 15 inches out of alignment with its bank position, or at positions < 200 steps and is > 7.5 inches out of alignment with the average of its bank position then within two hours, perform the followingi

a. Correct the situation, or

b. Determine by measurement the hot channel factors and apply Specification 3.10.2.1, or

c. Limit power to 70 percent of rated power 3.10.1.6 Insertion limits do not apply during physics tests or during period exercise of individual rods. However, the shutdown margin indicated in Figure 3.10-2 must be maintained, except during the low power physics test to measure control rod worth and shutdown margin. For this test, the reactor may be critical with all but one full length control rod inserted.

Amendment No. $7, 115 3.10-2

3.10.2 Power Distribution Limits 3.10.2.1 At all times except during Low power physics testo, the hot channel factors, FQ(Z) and FAN, defined in the basis, must meet the following limits:

F (Z) < (2.32/P) x K(Z) for P > 0.5 (Note 1)

FQ() < 4.64 x K(2) for P ( 0.5 (Note 2)

F < 1.65 (1 + 0.2(1-P) )

Note 1:

With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as follovst FQ(t) < (2.26/P) x K(Z) for P > 0.5 Note 2; With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as follows F (Z) < 4.52 z K(M) for P < 0.3 3.10-2a Amendment No.

115

where P is tgfraction of rated power (2300 10) at which the core is operating. Fq(Z) is the measured FQ(2) including the measurement N

QE uncertainty factor FN

• 1.05 and the engineering factor F Q 1.03.

u Q

FAH is the measured FA, including a 1.04 measurement uncertainty factor. K() is based on the function given in Figure 3.10-3, and 2 is the axial location of FQ.

3.10.2.1.1 Following initial loading, or upon achieving equiLibrium conditions after exceeding by 10% or more of rated power, the power FQ(Z) was last determined, and at least once per effective full power month, power distribution maps using the movable detector system, shall be made to confirm that the hot channel factor limits of Specification 3.10.2.1 are satisfied and to establish the target axial flux difference as a function of power level (called the target flux difference).*.

If either measured hot channel factor exceeds the specified limit, the reactor power shall be reduced so as not to exceed a fraction equal to the ratio of the FQ(Z) or F limit to the measured value, whichever is less, and the high neutron flux trip setpoint shall be reduced by the same ratio.

If subsequent incore mapping cannot, within a 24-hour period, demonstrate that the hot channel factors are met, the overpower AT and overtemperature AT trip setpoints shall be similarly reduced.

• During power escalation at the beginning of each cycle, the design target may be used until a power level for extended operation has been achieved.

3.10-3 Amendment No.

?7, 115

3.10.2.2 F (Z) shall be determined to be within the limit given in 3.10.2.1 by satisfying the following relationship for the middle axial 802 of the core at the time of the target flux determination:

2.32 K(2 F(2) 2.2) [:?

I for P > 0.5 (Note 3)

F (Z) < 4.64 ["(Z)] for P ' 0.5 (Note 4)

Note 3:

With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as fottovs FQ(Z) < (2.26) (2 for P > 0.5 Note 4:

With only twd safety Injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as follovs FQ(Z) < 4.52 for P < 0.5 3.10-3&

Amendment No. 115

where V(Z) is defined in Figure 3.10-4 which corresponds to the target band and P > 0.5.

3.10.2.2.1 If the relationship specified in 3.10.2.2 cannot be satisfied, one of the following actions shall be taken:

a)

Place the core in an equilibrium condition where the limit in 3.10.2.2 is satisfied and re-establish the target axial flux difference b) Reduce the reactor power by the maximum percent calculated with the following expression for the middle axial 80% of the core:

F (Z) x V(2)

(max. over Z of-]

x J a51001 (Note 5) 2.32 P

c)

Comply with the requirements of Specification 3.10.2.2.2.

3.10.2.2.2 The Allowable Power Level above which initiation of the Axial Power Distribution Monitoring System (APDMS) is required is given by the relation:

APL = minimum over Z of 2.32 z K(Z) 1001 (Note 6)

F7(U)

V(ZMY Note 5:

With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as followss

[lMaz. over Z of FQ(Z) z V(Z)J -

11 z 1001 2.26 x K(Z)

P Note 6:

With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as followst APL

• Minimum of Z of 2.26 x K(Z) a 100%

FQ

) z V(z) 3.10-4 Amendment No. 87.

115

where FQ(Z) is the measured FQ(), including the engineering E

H factor F Q 1.03 and the measurement uncertainty factor F

• 1.05 at the time of target flux determination from a paver distribution map using the movable incore detectors. V(Z) is the variation function defined in Figure 3.10-4 which corresponds to the target band. K(Z) is the function defined in Figure 3.10-3.

The above limit is not applicable in the following core plane regions.

1)

Lower core region 02 to 102 inclusive.

2) Upper core region 90% to 100% inclusive.

3.10-4a Amendment No.

115

At power levels in excess of APL of rated power, the APDMS will be employed to monitor FQ(2).

The limiting value is expressed as:

2.103/P (Not* 7)

. (U + u.)

where:

a. P is the fraction of rated power (2300 Mwt) at which the core is operating (P < 1.0).

b. R., for thimble j, is determined from core power maps and is by definition:

6 F

1 Oi 3

z

[r(2)i S(2)J F

is the value obtained from a full core map including S(2),

but without the measurement uncertainty factor Fy or the IU engineering uncertainty factor, rQ.

The quantity F(Z)ij 5()

is the measured value without inclusion of the instrument uncertainty factors F.

Those uncertainty factors, fN

• 1.05, FS w 1.02t as well as the engineering factor F

• 1.03, have Q

Q been included in the limiting value of 2.103/P.

c. oj is the standard deviation associated with the determination of a.

d. S(Z) is the inverse of the K()

function given in Figure 3.10-3.

Note 7:

With only two safety injection pumps operable, each capable of automatic initiation from a separate emergency bus, this formula shall be modified to read as follows:

(rF(Z) SCz)] max. ( 2.049/P (1

• rj) 3.10-5 Amendment No. 07, 115

This limit is not applicable during physics tests and excore detector calibrations.

3.10.2.2.3 With successive measurements indicating the anthalpy rise hot channel factor,.

, to be increasing with exposure, the total peaking factor, Q(2),

shall be further increased by two percent over that specified in Specifications 3.10.2.2, 3.10.2.2.1, and t

3.10OSa Amendment No. 115

M 0

(12.0,.647) x CIS W

z CIL 0

2 4

6 910 12 0ELEVATION IN CORE (FEET) r ISMIE 3.10-3 NORMAL12 ED AX IAL DEPEM4ENCE FACTOR FOR Fq VERSUS ELE VAT ION

((1AK 2q 2.32)

Note:

With only two safety injection pumps operable, each capable of automatic C.T iitiation from a separate emergency bus, peak Fq -2.26.