ML18093A478
| ML18093A478 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/29/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18093A479 | List: |
| References | |
| NLR-N87194, NUDOCS 8711020409 | |
| Download: ML18093A478 (7) | |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 October 29, 1987 NLR-N87194 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSES DPR-70 AND DPR-75 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses (FOL) DPR-70 and DPR-75 for the Salem Generating Station, Unit Nos. 1 and 2, respectively.
In accordance with the requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed.
In accordance with the requirements of 10CFR50.9l(b) (1), a copy of this request has been sent to the State of New Jersey as indicated below.
This amendment request adds. Reactor Vessel Level Instrumentation System (RVLIS) to Technical Specification Tables 3.3-11 and 4.3-11 and Table notation pages associated with Specification 3.3.3.7, Accident Monitoring Instrumentation.
These changes add specifications for instrumentation dealing with inadequate core cooling to provide assurance that the RVLIS equipment is operated and maintained within acceptable limits. contains further discussion and justification for these proposed revisions.
This amendment request, pending the necessary review and approval, requires no special consideration regarding the date of issuance or effective date.
This submittal includes one (1) signed original, including affidavit, and thirty-seven (37) copies pursuant to 1 0 CF RS 0
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Document Control Desk 2
10-29-87 Should you have any questions on the subject transmittal, please do not hesitate to contact us.
Sincerely, Attachments C
Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
Ref: LCR 87-10 STATE OF NEW JERSEY COUNTY OF SALEM
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SS.
Corbin A. McNeill, Jr., being duly sworn according to law deposes and says:
I am Senior Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated October 29, 1987
, concerning Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, are true to the best of my knowledge, information and belief.
Subscribed and Sworn-~~ yefore me this dfd day of c:f~, 1987
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l.ARAINE Y. BEARD M Noto~ ~ublic of New Jersey My Co
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p1' res y Comm1ss1on E~piresMay 1, 1991 blic of New Jersey mm s ion ex on -----------------
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.PROPOSED CHANGE SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 REACTOR VESSEL LEVEL INSTRUMENTATION SYSTEM Description of Change LCR 87-10 Paqe 1 of 3 Add Reactor Vessel Level Instrumentation System (RVLIS) to Tables 3.3-11 and 4.3-11 and Table Notation pages associated with Specification 3.3.3.7, Accident Monitoring Instrumentation.
Tables 3.3-lla and 3.3-llb in the Salem Unit 1 Technical Specifications have been combined into a single table (3.3-11) and the Total Number of Channels column has been omitted as its inclusion in the Technical Specifications is irrelevant.
R~ason for Change These proposed changes will add specifications for instrumentation dealing with inadequate core cooling to provide assurance that the RVLIS equipment installed at the facility is operated and maintained within acceptable limits.
This proposed change is in response to NUREG-0737, Technical Specifications guidance provided in NRC Generic Letter 83-27 and an additional request (Varga to Uderitz, dated November 17, 1983) for Technical Specifications for Inadequate Core Cooling (ICC) instrumentation.
Significant Hazards Consideration The RVLIS equipment has been installed on the Salem units in response to NUREG-0737.
The Westinghouse designed system was approved by NRC and the installation of the system subjected to a 10CFR50.59 Safety Evaluation.
The RVLIS is a purely informational system.
No control functions are required to be performed by the system and none are provided in its design.
Since this proposed license change is associated only with out-of-service time of an information system, no accident/
.transient probability of occurrence is impacted.
Consequently, the proposed Technical Specification (TS) change does not affect the probability of a previously evaluated accident.
In addition, the possibility of a new or different type of accident from any previously evaluated is not created.
RVLIS neither replaces nor couples with any existing safety system.
Although it does act to provide additional information to the operator during postulated accident conditions, it is not the only indicator of an approach to, or recovery from, a potential Inadequate Core Cooling event.
The following is provided to support a conclusion that the proposed TS change does not involve a significant reduction in margin of safety or increase the consequences of a previously evaluated accident.
The Core Exit Thermocouple (CET) system provides an indication of radial distribution of temperature rise across representative regions of the core.
CET response to the presence of superheated
LCR 87-10 Page 2 of 3 steam is one of the indicators of an approach to a postulated ICC situation.
While the CET's will not provide an indication of the amount of core voiding, their response provides a direct indication of the existence of an ICC event, the effectiveness of recovery action, and the restoration of adequate core cooling.
The Saturation Margin Monitor (SMM) indicates the approach to a postulated ICC event by detecting saturation conditions.
The significant parameters continuously displayed are:
Reactor Coolant delta P (P actual -
P saturation)
Reactor Coolant delta T (T saturated -
T actual)
Wide Range Reactor Coolant System (RCS) Pressure indication displays general RCS Pressure trends.
Wide Range RCS Temperature indication is available for determining trends of ICC recovery actions.
Steam Generator (SG) Level indication in conjunction with Auxiliary Feedwater (AFW) Flow indication assure the adequacy of make-up water and hence heat sink availability for the RCS.
Also, SG Pressure indication may be used in conjunction with other indications in determining heat sink availability and heat removal capability during ICC mitigatinq actions.
The significant parameter changes for which the above noted indications are used in determining the adequacy-of core heat removal 0
0 0
are:
RCS delta T less than Full Load delta T.
RCS or CET Temperatures constant or decreasing.
SG Pressure constant or decreasing at a rate equivalent to the rate of decrease of RCS Temperature while maintaining SG level with continuous AFW flow.
Other plant parameters which may indicate an approach to a postulated ICC event< a~e unexplained changes in Pressurizer Level and Letdown Flow greater than Charging Flow.
Current operating guidance for Small Break Loss of Coolant Accident (LOCA) response with no Reactor Coolant Pumps running requires the operator to perform the following:
0 0
Control natural circulation with AFW flow and steam dumping.
Monitor natural circulation with the following trended parameters:
CET's stable or decreasing.
LCR 87-10 Page 3 of 3 RCS Hot Leg Temperature stable or decreasing.
SG Pressure stable or decreasing.
RCS Cold Leg Temperature at saturation temperature for SG Pressure.
RCS Subcooling greater than 10°F.
Cautions are provided to the operator that voiding may occur in the RCS during depressurization.
This will result in a rapidly increasing Pressurizer Level.
The operator is also required to monitor subcooling margin.
In addition, natural circulation rapid cooldown procedural guidance exclusive of RVLIS operability also exists.
In summary, plant instrumentation exclusive of RVLIS is adequate to determine heat sink availability, detect the onset of a postulated ICC event, and monitor the effectiveness of mitigating actions.
While RVLIS is provided to permit a more continuous indication of the approach to ICC, its availability is not absolutely necessary to ensure safe shutdown.
Therefor~, no significant hazard exists and the margin of plant safety is not significantly reduced by the proposed Technical Specification.
Since the Reactor Vessel Level Instrumentation System adds to the information available to the control room operator during normal and post accident conditions, thereby providing an additional measure of safety, and because the proposed license change constitutes additional limitations, controls, and surveillance requirements for the new system to assure that the system is maintained OPERABLE, we have determined that operation of the facility in accordance with this proposed change constitutes no significant hazards consideration.
This proposed change conforms with Example (ii) of "Examples of Amendments That are Considered Not Likely to Involve Significant Hazards Considerations *** "
provided by the Commission in 48 FR 14870.
REVISED PAGES -
UNIT NO. 1