ML20096G692
| ML20096G692 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/12/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20096G682 | List: |
| References | |
| NUDOCS 9205260205 | |
| Download: ML20096G692 (5) | |
Text
i 8
[SCO 080 0
o UNITED STATES
- ,h NUCLE AR REGULATORY COMMISSION j
f g.
.t W ASHING T ON, D. C. 20555 h.....*
SAFETY EVALUATION BY THE. QfflCE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.159 TO FACILITY OPERATING LICENSE N0. OPR-16 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
1.0 INTRODUCTION
By letter dated February 15, 1990, as supplemented January 22, 1992, GPU Nuclear Corporation (GPUN/the licensee) requested changes to the Oyster Creek Nuclear Generating Station (OCNGS) Technical Specifications (TS) which would revise TS 3.13.B.1 and 3.13.B.2, delete current TS 3.13.B.3 and 3.13.B.4 and the note at the bottom of the page 3.13-1 which applied only during the previous operating cycle.
Specifically, the proposed T!. 3.13.B.2 would replace current TS 3.13.B.2, 3.13.B.3 and 3.13.B.4 and place no limitation on the number of inoperable position indicators for the nine ASME Code safety valves during power operation.
Each safety valve has a primary and a backup position indicator.
The primary device is an acoustic monitor while the backup device is a thermocouple. The requirements for relief and safety valve position indication were described in NUREGs 0578, 0660 and 0737. Accoustic monitors were installed in 1980 in response to NUREG 0578 to complement the existing thermocouples. A minor change to the associated bases was also requested.
In addition, where TS definitions are used in TS 3.13.D, 3.13.E, 3.13.F and 3.13.G they are now capitalized. This is an editorial change to make these TS consistent with the TS sections.
Currently, OCNGS TS require a plant shutdown depending on the number of inoperable safety valve position indicators and the ' location of their associated safety valves. The nine safety valves are located on the main steam )iping inside containment and they discharge directly to the containment atmosp;ere. These valves are spring-type code safety valves with no means of remoto control.
Between October 1984 and February 1990, there have been approximately 24 safety valve acoustic monitor failures during power operation.
So far, only a limited power reduction resulted from TS requirements. However, based on this experience with the acoustic monitors, the licensee antis pates that other power reductions or shutdowns will be nece-sary. The licensee's safety evaluation has concluded that safety valve position indcators provide no real safety benefit for the OCNGS, and that since no benefit would result from 9205260205 920512 PDR ADOCK 05000219 P
d
. upgraJing or replacing the acoustic monitors with a more reliable system, the licensee is requesting a change to OCNCS TS Section 3.13.B in order to eliminate the potential for unnecessary shutdowns due to safety valve position indicator operatility requirements, in order to be consistent with the requirements of NUREG 0737, item II.D.3, the proposed TS will still require that all safety valve position in'ication instrumentation be operabite prior to startup following each cold shutdown (see TS Section 3.13.C).
If a thermocouple becomes inoperable, no compensatory measures would be required.
If an acoustic monitor becomes inoperable, the acoustic monitor on an adjacent valve, if operable, would have its setpoint reduced. A setpaint reduced in this manner would be allowed to return to normal if the acoustic monitor alarms due to background noise.
This ensures the continued operability of adjacent valves acoustic monitor.
2.0 EVAlVATION The essence of the proposed change is to permit continued operation with no limitation on the number of inoperable position indicators for the safety valves.
Repair of any inoperable devices would still be required prior to startup following each cold shutdown.
The basis for the proposed change is that, at the OCNGS, procedure-directed operator response to symptoms indicative of a primary system steam or liquid release inside containment is no different whether the source is an open safety valve or breach in the reactor coolant pressure boundary.
The nine safety valves at the OCNGS are spring-loaded and do not have any mechanism for remote operator control of the valve's position from the control room.
This means that if a safety valve has inadvertently opened and is stuck open, the operator cannot take any direct action to close the valve. The derived benefit is information only.
The control room alarm response procedure alerts the operator to an open safety valve based on tie acoustic monitors. The procedure does not direct the operator to take any action other than to confirm that the valve actually opened by examining drywell pressure indicator or safety valve discharge thermocouple readings.
After developing the symptom-based Emergency Operating Procedures (E0Ps), it was determined that safety valve position indication is no longer necessary based on the manner in which the E0Ps direct the operator's actions. The E0Ps instruct the operator to respond to 31 ant parameters without the need to diagnose the event. The operator taces actions to control reactor vessel and containment conditions to bring these parameters under control.
The operator's actions in response to a loss of reactor vesse' water inventory are the same regardless of the source of the inventory loss. The discharge of steam to the drywell from the opening of a safety valve or any other. primary system leakage path would be immediately evident to the operator by a rapid increase in drywell pressure'and temperature.
The high drywell pressure condition is an entry point into both the reactor pressure vessel (RPV) control and containment control procedures.
The RPV control procedure directs the operator to control RPV water level and pressure and confirm reactor shutdown.
The containment control procehre gives the operator guidance for controlling drywell pressure
- =__.
. and temperature and torus pressure, temperature and water level.
The presence of the safety valve acoustic monitor alarm does not alter the operator actions in controlling the changes in plant parameters during an event.
With the development and implementation of symptom-based emergency operating procedures at the OCNGS, the operations response is governed by changes in plant parameters (symptoms) and not by what cause1 those paremeters to change.
Consequently, operator response to a stuck open safety valve is not affected or dependent on the operability of the valve acoustic monitors or thermocouples.
Thus, operability of safety valve position indication is not necessary at the OCNGS for transient or accident mitigation and TS for safety valve position indication should not require a plant shutdown or necessitate power reduction in order to ensure compliance. The staff, therefore, finds the proposed changes and related bases to be acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental asr ssment and finding of no significant impact have been prepared and published in the federal itaister on May 12, 1992 (57 FR 20307). Accordingly, based upo. the environmental assessment, we have determined that the issuance of the amendment will not have a significant effect on the quality of the human environment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
H. Razzaque Date:
May 12, 1992 l
l l
d
)
7590-01 l
UNITED STATES NUCLEAR REGULATORY COMMISSION iif3LNjlcLEAR CORPORATION DOCKET NO. 50-219 NOTICE OF ISSUANCE OF AMENDMENT TO i
FACILITY OPERATING LICENSE The U.C Nuclear Regulatory Comission (Comission) has issued Amendment No.158. to Facility Operating; License.No OPR-16 issued to GPU Nuclear
' Corporation (the licensee), which revised the Technical Specifications for i
operation of the Oyster Creek Nuclear Generating Station located in Ocean County, New Jersey.
The amendment is-effective as of the date of issuance.-
The amendment would revise the Technical Specifications to permit no limitation on the number of inoperable position-indicators for nine ASME Code safety valves-~during power operation.
The application for the amendment complies with the standards and requirements of the-Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comissio'n has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Notice of; Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER-on March 21, 1990 (55 FR 10561). No request for a hearing or petition for leave to intervene was filed following this notice.
-The Comission has prepared an-Environmental Assessment related to the
~
action:and'has determined not to prepare an environmental impact statement.
l-Based upon the environmental assessment, the comission has concluded that the l
a s issuance of this amendment will not have a significant effect on the quality of the human environment.
For further details with respect to the action see (1) the application for amendment dated February 15, 1990, as supplemented January 22, 1992 (2) Amendment No.158 to License No. DPR-16, (3) the Commission's related Safety Evaluation, and (4) the Commission's Environmental Assessment. All of these items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street hk'., Washington, DC 20555 and at the local public document room located at the Ocean County Library, Reference Department, 101 Washington Street, Toms River, New Jersey 08753.
A copy of items (2), (3) and (4) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission. Washington, DC 20555, Attention:
Document
. Control Desk.
Dated at Rockville, Maryland this 12th day of May 1992.
FOR THE NUCLEAR REGUI ATORY COMMISSION fnd!y V: 40&wht Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
. _ !,