ML18092A216
| ML18092A216 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/19/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GL-83-27, NUDOCS 8407020480 | |
| Download: ML18092A216 (8) | |
Text
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. *,., 0 PS~G*
Public Service Electric and Gas Company P.O. Box 236
.~an~o~ks Bridge, New Jersey 08038 Nuclear Department
(,.
Director of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing
Dear Mr. Varga:
INADEQUATE CORE COOLING INSTRUMENTATION TMI ITEM II.r,.2 SALEM GENERATING STATION UNITS NO. 1 AND 2 DOCKET NOS. 50-272 and 50-311 Following is a description of the Core Exit Thermocouple (CET)
System upgrade, as requested by Messrs. T. Huang and L.
Phillips of ONRR.
The in-containment portion of the ICCI System will utilize the existing core exit thermocouples for instrumentation monitoring.
These thermocouples are of the Type K design which are considered qualified by Regulatory Guide 1.97.
Upon exiting the reactor vessel head area, the CET design will incorporate qualified Combustion Engineering, Inc. (CE) connectors and mineral insulated (MI) cables.
This MI cable will be routed from the CET connector to four CE supplied connector plates located above the head area.
use of MI cable will assure adequate cable separation in the vicinity of the reactor vessel head.
MI cable will then be routed via two independent paths to two qualified electrical penetration assemblies.
The penetration assemblies will be of the type designed to accept thermocouple signal cable.
The qualified CET system will not utilize the existing reference junction box.
Outside of containment, fully qualified IEEE organic cable will be used up to the backup displays.
- ~--8407020480 840619 The Energy People PDR ADOCK 05000272 P
PDR 95-2168 (75M) 12-83
Mr. Steven 6/19/84 Two fully qualified microprocessor based backup displays will be utilized.
The backup display will be capable of displaying core exit temperature on a digital meter.
The minimum number of thermocouples that the backup display will selectively read will meet the NUREG 0737 requirement.
The backup display will be supplied by Combustion Engineering, Inc.
The ICCI System primary display will consist of the plant computer and its associated supplementary equipment.
In a letter dated April 4, 1984, we proposed to upgrade the CET connectors in the reactor vessel (RV) head area and install MI cables from the RV head region to four qualified connector plates.
This change was to be installed during the fifth (current) and second (spring 1985) refueling outages for Units 1 and 2 respectively.
However, due to additional upgrade proposed in this letter, which involves purchase items of long lead time, we feel that the earliest date the CET system upgrade could be installed is the sixth (1986) and third (1986) refueling outages for Units 1 and 2 respectively.
A preliminary copy of the proposed RVLIS Technical Specif i-cation is also attached for your review.
Should you have any questions on the above, please contact us.
Attachments C
Mr. Donald C. Fischer NRC Project Manager Mr. James Linville Senior Resident Inspector Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation
PliPELIMINAR' PROPOSED CHANGE TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 DESCRIPTION OF CHANGE Ref:
LCR 84-03 Add Reactor Vessel Level Instrumentation System (RVLIS) Tables 3.3-lla, 3.3-llb and 4.3-11 and Table Notation pages associated with Specification 3.3.3.7, Accident Monitoring Instrumentation.
REASON 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 ICC! equipment.
SIGNIFICANT HAZARDS EVALUATION The RVLIS equipment has been installed as a result of NUREG-0737 on the Salem units.
The Westinghouse designed system was approved by NRC and.the installation of the system subjected to a 10 FR 50.59 Safety Evaluation.
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.
/
P~ELIMINAR,_
INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPE.RATION 3*.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-lla and Table 3.3-llb shall be operable.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
- a.
As shown in Table 3.3-lla and Table 3.3-llb.
- b.
The provisions* of Specification 3.0.4 are not*
applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.7 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK AND CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-11.
3/4 3-
c::: z H
t-3 w
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\\\\ R "{ TABLE 3.3-lla (CONTINUED)
ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT
- 13.
PORV Block Valve Position Indicator
- 14.
Pressurizer Safety Valve Position Indicator
- 15. Containment Pressure - Narrow Range
- 16. Containment Pressure - Wide Range
- 17. Containment Water Level -
Wide Range
- 18.
- 19.
Reactor Vessel Level Instrumentation System (RVLIS)
TOTAL NO.
- OF CHANNELS 2/valve**
2/valve**
4 2
2
. 65
. 4***
REQUIRED NO. OF CHANNELS 2/valve**
2/valve**
2 2
2 4/core quadrant 2
(*) Total number of channels is considered to be two (2) with (1) of the channels being manual calculation by licensed control room personnel using *data from OPERABLE wide range Reactor Coolant Pressure and Temperature along with Steam Tables as described in ACTION 5.
(**) Total number of channels is considered to be two*~2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:
Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level Operable.
(***)Total number of channels is considered to be four (4), comprised of two independent trains each containing one (1) 11Dynamic Head 11 and one (1) 11Full Range 11 instrument.
No credit is taken, for purposes of channel count, for the additional 11Upper Range 11 instrument on each train.
ACTION 1
1 7
7 1
1
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TABLE 3.3-llb (CONTINUED)
ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT
- 13.
PORV Block Valve Position Indicator
- 14.
Pressurizer Safety Valve Position Indicator
- 15. *containment Pressure - Narrow Range
- 16. Containment Pressure - Wide Range
- 17. Containment Water Level -
Wide Range
- 18.
- 19.
Reactor Vessel Level Instrumentation System (RVLIS)
TOTAL NO.
Of CHANNELS 2/valve**
2/valve**
4 2
2 65
. 4***
MINIMUM NO. OF CHANNELS 1
1 1
1
.1 2/core quadrant 1
(*) Total number of channels is considered to be two (2) with one {l) of the channels being manual calculation by licensed control room personnel using data from OPERABLE wide range Reactor Coolant Pressure and Temperature along with Steam Tables as described in ACTION 5.
(**) Total number of channels is considered to be two (2) with one {l) of the channels being any one {l) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:
Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level Operable.
(***) Total number of channels is considered to be four (4), comprised of two independent trains each containing one (1) 11Dynamic Head 11 and one (1) 11Full Range 11 instrument.
No credit is taken, for purposes of channel count, for the additional "Upper Range" instrument on each train.
ACTION 2
2 29 2
2 2
2
e PRELIMl*NARY TABLE 3.3-lla & b (continued)
TABLE NOTATION ACTION 1 With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-lla, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 2 With the number of OPERABLE accident monitoring channels less than the MINIMUM Number of Channels shown in Table 3.3-llb, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT SHUTDOWN withi~ the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 With the number of OP(RABLE ch~nnels one l~ss ~han the Required Number of Cha~nels showri in Table 3.3-lla, operation ma} proceed provided that the Boric Acid Tank assoc~ated with the remaining OPERABLE channel sati'..fies all requirements of Specification 3.1.2.8.. a.
ACTION 4 With the number of OPERABLE channels one less than the Required Number at Channels shown in Table 3.3.lla, operations m2y proceed provided that an OPERABLE Steam Generator Wide Range Level channel is available as an alternate means of indication for the Steam Generatcr with no OPERATABLE Auxiliary Feedwater Flow Rate channel.
ACTION 5 With the number of DPERABLE channels less than the Required Number of Cnannels show in Table 3.3-lla, operation may proceed provided that Steam Tables are available jn the Control Room and the following Required Channels shown in Table 3.3-lla are OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:
- a.
Reactor Coolant Q,tlet Temperature - THOT (Wide Range)
- b.
Reactor Coolant Pressure (Wide Range)
SALEM -
U~.:IT (BoT.{)
3/4 3-
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~\\
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TABLE 4.3-11 (CONTINUED)
SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT
- 12.
PORV Position Indicator
- 13.
PORV Block Valve Position Indicator
- 14.
Pressurizer Safety Valve Position Indicator
- 15. Containment Pressure - Narrow Range
- 16. Containment Pressure - Wide Range
- 17. Containment Water Level -
Wide Range
- 18.
- 19.
Reactor Vessel Level Instrumentation System (RVLIS)
CHANNEL CHECK M
M M
M M
M M
M CHANNEL CALIBRATION NA NA NA NA R
R R
R I
~. -
I*
CHANNEL FUNCTIONAL TEST Q
NA NA NA NA NA I e