ML20151L533

Redistributed Amend 99 to License DPR-54,adding Limiting Conditions of Operation & Surveillance Requirements Re Shunt Trip Attachment Installed at Facility in Response to Generic Ltr 83-28

ML20151L533
Person / Time
Site:	Rancho Seco
Issue date:	07/14/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151L494	List: ML20151L489 ML20151L533 ML20151L551
References
GL-83-28, NUDOCS 8808040071
Download: ML20151L533 (6)

Text

.

, f Ce%9

+ ,\ UNITED STATES 8' :s.c 'h NUCLEAR REGULATORY COMMISSION 5

l W ASHING TON, D. C. 20555 k..v...f SACRAMENT 0 MUNICIPAL UTILITY DISTRICT DOCKET N0. 50-312 RANCHO SECO NUCLEAR GENERATING STATION

_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. OPR-54

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

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated November 8,1985, as supplemented December 9, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the application, the prnvisions of the Act, and the regulations of the Commission; C. i. nee is reasonable assurance (1) that the activities authorized by this amendment can be conducted witi1out endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comissicn's regulations; D. The issuance of this amendment will not be inimical to the conynon 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 requireraents have been satisfied.

8808040071 880725 DR ADOCK0500g2

~2-

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachmeat to this licence amendment, I and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.99 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This Amendment to the Technical Specification shall become effective within 30 days of the issuance date. The implementation delay is provided to allow titre for modification of affected procedures and promulgation of these changes to personnel.

FOR THE NUCLEAR REGULATORY COMMISSION George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Attachmerit: l Changes to the Technical Specifications Date of Issuance: July 14, 1988 l

l l

l

- _ . , , ,.7 , . .. --. _ - -

i ATTACHMENT TO LICENSE AMENDMENT N0.99 FACILITY OPERATING LICENSF NO. DPR-54 DOCKET N0. 50-312 Replace the following pages of the Appendix "A" Technical Specifications j with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3-25a 3-25a )

l 3-26a 3-26a '

4-4 4-4

. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.5.1.6 Hith one of the Reactor Trip Breaker diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the breaker in trip in the next hour.

3.5.1.7 In the event that both Reactor Trip Breaker diverse trip features fail in the untripped state, the Breaker will be declared inoperable, and the power supplied to the rod drive mechanisms through the failed trip device shall be manually removed within 30 minutes. The condition will be corrected and the remaining trip devices shall be tested within eight hours. If the condition is not corrected and the remaining trip devices are not tested within the eight-hour period, the reactor shall be placed in the hot shutdown condition within an additional four hours.

3.5.1.8 ~he SCR relays for the regulating rods duplicate the trip function of the DC breakers for the safety rods. With the number of OPERABLE SCR relays one less than the total number of SCR relays in a channel, restore the inoperable SCR relay to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the SCRs associated with the inoperable relay in trip in the next hour. With two or more SCR relays inoperable, place all SCR relays associated with that channel in trip in the next hour.

3.5.1.9 The inoperable channel in Sections 3.5.1.6, 3.5.1.7, and 3.5.1.8 may be bypassed for up to 30 minutes in any 24-hour period when necessary for surveillance testing per Specification 4.1.1.

Bale.1 Every reasonable effort will be made to maintain all safety instrumentation in operation. A startup is not permitted unless three power range neutron instrument channels and two channels each of the following are operable:

four reactor coolant temperature instrument channels, four reactor coolant flow instrument channels, four reactor coolant pressure instrument channels, four pressure-temperature instrument channels, four flux-imbalance flow instrument channels, four power-number of pumps instrument channels, and four high reactor building pressure instrument channels. The safety features actuation system must have two analog channels functioning correctly prior to startup. EFIC system instrumentation as required by Table 3.5.1-1 must be operable.

Operation at rated power is. permitted as long as the systems have at least the redundancy requirements of Column B (Table 3.5.1-1). This is in agreement with redundancy and singlo failure criteria of IEEE 279 as described in FSAR section 7.

The four reactor protection channels were provided with key operated maintenance bypass switches interlocked to allow on-line test',ng or maintenance on only one channel at a time during power operation. Each channel is provided alarm and lights to indicate when that channel is bypassed.

Amendment No. 31,87,93, 99 3-25a

' l l

RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Since the EFIC receives signals from the RPS it is important that only corresponding channels be placed in "maintenance bypass." If a channel of RPS is in maintenance bypass, only the corresponding channel of EFIC can be l bypassed. An interlock feature also prevents bypassing more than one EFIC channel at a time. These interlocking features allow the EFIC system to take a single failure in addition to having one channel in maintenance bypass.  ;

Various RPS test features can inhibit initiate signals to the EFIC system and l degrade thb EFIC system below acceptable limits if the RPS channel is not in l bypass. Therefore, no testing should be performed on a RPS instrument string which supplies an output to EFIC without placing that RPS channel in bypass.

The EFIC system is designed to allow testing during power operation. The EFIC system can be tested from its input terminals to the actuated device controllers without placing the channel in key locked "maintenance bypass."

A test of the EFIC trip logic will actuate one of two relays in the ,

controllers. The two relays are tested individually to prevent automatic l actuation of the component. I Each EFIC channel key operated maintenance bypass switch is provided with alarm and lights to indicate when the maintenance bypass switch is being used.

The source range and intermediate range nuclear flux instrumentation scales i overlap by one decade. This decade overlap will be achieved at 10-10 amps j on the intermediate range scale.

Power is normally supplied to the control red drive mechanisms from two separate parallel 480 volt sources. Redundant trip devices are employed in each of these sources. If any one of these trip devices fails in the untripped state, on-line repairs to the failed device, when practical, will  !

be made, and the remaining trip devices will be tested. Eight hours is ample I time to test the remaining trip devices and in many cases make on-line repairs. If on-line repairs are not practical, the device will be replaced with a spare or placed in tripped condition in a timely manner.

l Amendment No. 31,93, 99 3-26a

Im RANCHO SECO UNIT 1

~

o TECHNICAL SPECIFICATIONS

@ Surveillance Standards e Table 4.1-1 (Continued)

.D INSTRfmENT SURVEILLANCE REQUIRDENTS Channel Description Check Test Calfbrate Remarks l D

8. Reactor coolant pressure /

temperature comparator S M R e

• 9. Power /febalance/ flow comparator 5 M R

, 10. Pump / flux comparator 5 M R

11. High Reactor Building Pressure Channels D M R 12a. Protection channel cof ncidence logic NA M MA

b. ARTS Turbine Trip 5 M R Monf tor Channels i

• e c. ARTS Loss of WW Pumps S M R

'

• Monitor Channels l

13a. CRD Trfp Breaker RPS Undervoltage trfp NA M.P NA

b. RPS Shunt Trfp NA M.P NA

c. SCR Relays NA M NA i Safety Features Systee

14. Emergency core cooling fnjection, emergency butiding cooling and 4 butiding isolation analog channels

a. Reactor coolant pressure channel S M R i b. Reactor Building

4 pstg channel S M R

^

44 l

1

_ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ___ _ _ _ _