ML20106C754
| ML20106C754 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/25/1992 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20106C749 | List: |
| References | |
| NUDOCS 9210060333 | |
| Download: ML20106C754 (11) | |
Text
.. _. _. - _.. _.. _ _... _ _.. _.. _. _. -_... _. _. - _ -...
i ATTACHMENT l to JPN 92 055 t
PROPOSED TECHNICAL SPECIFICATION CHANGES REACTOR WATER CLEANUP LEAK DETECTION SYSTEM TABLE 3.21 REVISION (JPTS 9102N i
l l
New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 l
DPR55 9210060333 920925 PDR ADOCK 05000333 P
PDR-
JAFNPP TABLE 3.2-1
{
INSTRUMENTATION THAT INIT' ATES PRIMARY CONTAINMENT ISOLATION Minimum No.
of Operable Total Number of instrument instrument Channels Channels Per Provided by Design Trip System (1) instrument Trip Level Setting for Both Trip Systems acJm (2) 2(6)
Reactor Low Water Level
> 177 in.above TAF 4 inst. Channels a
1 Reactor High Fressure
$75 psig 2 inst. Channels 0
}
(Shutdown Cooling isolation) 2 Reactor Low-Lew-Low Water Level
> 18 in. above TAF 4 inst. Channels A
2 (6)
High Drywell Pressure
< 2.7 psig 4 inst. Channels A
I 2
High Ra-T#an Main
< 3 x Normal Rated 4 Inst. Channels B
Stearv.h e Tunnel Full Power Backgrout (9)
{
2 tow Pressure Main Steam Une
> 825 psig (7) 4 Inst. Channels B
4 2
High Flow Main Steam Une 5140'/o of Rated Steam Flow 4 Inst. Channels B
2 Main Steam Line Leak
< 40P above max cmbient 4 Inst. Channels B
Detecticn High Temperature 1
4 Reastor Cleanup System Equipment 5407 above max ambient 8 Inst. Channels C
Area High Temperature 2
Low Condenser Vacuum
> 8' Hg. Vac (7)(8) 4 Inst. Channels B
Closes MSIV's Amendment No.((,[
[,,1d, %
3
i Attachment il to JPN 92-055 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGE REACTOR WATER CLEANUP LEAK DETECTION SYSTEM I/33LE 3.21 flEVJS1QRIJPTS91-029) 1.
OfSCRIPTjQN OF THE PROPOSED _CHARCtES This application for an amendment to the James A. FitzPatrick Technical Specifications reflects a plant modification which installed two additional thermocouples (temperature elements), associated cabling. temperature switches and circuitry, in tho vicinity of the RWCU 6 inch lino at the containment penetration. The changes to the Technical Specifications are addressed below.
Minor changes in format, such as type font, margins or hyphenation, are not described in this submittal. These changes are typographical in nature and do not af fect the content of the Technical Specifications.
Ei2np f 4. Tabht322d For the " Reactor Cleanup System Equipment Area Hi h Temperaturo" instrument:
0 Change the minimum number of operable instrument channels per trip system f rom "3" to "4."
Change the total number of instrument channels provided by design for both trip systems from "G"
to "8."
11.
E11BEQSE OF TFiE PROEQSEp CHANGES The Authority's program 'o address NRC IE Bulletin 79-01B " Environmental Qualification of Class IE Equipment" (Reference 3) postulated a hi h energy line 0
break in a nineteen foot section of RWCU pipe that runs between the containment penetration and the RWCU "A" pump room (Reference 4). As a result, two new temperature elements were added to isolate the RWCU system from the reactor vesselin the event of a line break in this area (Reference 5). Six existing temperature elements monitor other RWCU systnm areas.
The NRC (in References 1 and 2) identified a discrepancy between t ' number of RWCU area temperaturo detectors in the plant and listed in the Technical Specifications. Table 3.21 of the Technical Specifications only listed six RWCU area high temperature instrument channels when ei ht channels were installed in the 0
plarit. When those two now temperature elements were installed, the Authority did net revise the Technical Specifications. This proposed char.e adds these two new channels to Table 3 21 to reflect their installation as part of the equipment qualification program.
When approved, the operability requirements of LCO 3.2.A will apply to these new z
temperature elements, if less 'han four instrument channels (temperature elements) are operablo per trip system, action statment 2.c (Table 3.2-1 on page 65) will require that the RWCU system be isolated.
Attachment il to JPfe92 055 SAFETY EVALUATION Page 2 of 7 111.
SAFETY IMPLICATIONS Of_THE PROPOSED CHANGES The purpose of the RWCU Leak Detection System, the modification made to this system, the safety implications of that modification and the safety implications of the Technical Specification change are discussed below. These discussions support the conclusion that there are no adverse safety implications.
RWCU Leak Detection Systern The purpose of the RWCU Leak Detection System is to close RWCU System primary containment isolation valvos when high area temperatura indicates a High Ener w Line Break (HELB) or leak. The system meets single f ailure critoria by utilizing two instrument channels to perform the system function. Channel A isolatos 12MOV 15,
^
the RWCU suction lino isolation valvo insido containment. Channel B isolatos 12MOV-18, the RWCU suction lino isolation valve outsido containment, and 12MOV-09, the RWCU return line isolation valve outside containment.
The RWCU system is a six inch line as it leaves primary containment through penetration X-14. The isolation valve insido containment is 12MOV 15. Tho isolation valvo outsido containment is 12MOV-18. This six inch lino runs for about 19 feet before turning down to penetrate the ceiling of the room containing RWCU pump A. Thero, the line splits into two-four inch lines running to the suction side of the A and B RWCU pumps. The lino to the B purap penetratos a wai; separating the two pumps. Tho discharge of each pump is a three inch line until they join in the B rmmp room. There the lino returns to a four inch sizo and runs to the room containing the rogenerative and non-regenerative heat exchangers.
9
?rior to the modification adding two temperature channels, the RWCU Leak Detection system providoi redundant detection instrumentation in the three equipment rooms (i.e., A and B pump rooms and heat exchanger room) to detect the of fect of breaks in the RWCU system. These HELB breaks were postulated in accordance with criteria in the Giambusso letter regarding the postulation of piping failures outsido containment (Reference 6). Breaks were postulated in the six inch line in pump A room, in the four inch dischargo line in pump B room and close to the inlet of the first regenerative heat exchanger in the heat exchanger room. No breaks are postulated downstream of the first heat exchan0er.
Modificatiqa The two temperature elements (12TE-122 A and B) were added to Division I and il (channels A and B) of the RWCU system to provide area temperature monitoring to detect and mitigate the affects of a high energy line break (HELB). A six inch RWCU line break was postulated on top of the RWCU pump A room on elevation 300'. This location is downstream of isolation valve 12MOV-18 before the line enters RWCU pump A room. This break was not defined when addressing Reference 6. It was postulated as part of the response to IE Bulletin 79-018 (References 4,5 and 7). The added temperature elements are installed in the vicinity of the six inch lino. The proximity of the detectors to the assumed break assures that the calculated response timo for isolating RWCU isolation valves 12MOV-15 and 12MOV-18 (Reference 8) will be satisfied.
. 1 to JPN 92 055 SAFETY EVALUATION Page 3 of 7 Tho new detectors were wired to existing sparo temperature switches in the control room. The output of the temperature switches is integrated with the logic for the existing isolation function (References 9 and 10). The temperature twitches originally used in this modification were replaced. The replacements and the new detectors aro Class IE and seismic Category I (Reference 11). They have the required range, reliability, equipment qualification, and accuracy to perform their intended function.
Safelyjfnplications of Modification The modification increases the number of instrumutation channels used for RWCU isolation. This increases the probability that an inadvertent or spurious isolation of
~
the RWCU systorn could occur. This 10 probability event has minimal effect on the reactor and no safety significant offect. The additional temperature elements will isolate the RWCU piping from the primary system in the event of a pine bresik or leak outside the containment. Althou0h a low probability event, the potential effects can be significant if prompt isoiation does not occur. Since the instrumentation monitors an additional area where a postulated pipe break could occur, it provides safety benefits with minimal potential for s.'fety of fects.
The ability of the system to perform its intended safety function is assured by the codos and standards imposed (seismic Cate0ory I and Class IE).
The additional instrumentation channels are included in the existing plant surveillance pro 0 ram (References 12 and 13) to assure operability. The modification did not requiro revision of the current surveillance procedure other than the addition of the two new temperaturo channels. The monthly instrument functional test consists of lif ting the thermocouplo extension leads, injecting a simulated electrical signal into the channel and verifyin0 that the primary relays deener0 zo. The quarterly calibration i
follows the same proceduro and involves adjustment of the temperature switch to checklist / data sheet value. The temperaturo element is a dual element design.
Durin0 calibration, the temperature readings of the portions of the temperature element used for the trip function and for control room temperature indication are compared and must agroo within 10 F. An instrument check of the portion of the temperature element used for indication is performed daily. The portion of the temperature element used for the trip function is calibrated with an ice bath at two year intervals (Reference 14). This interval limits pesonnel radiation exposure.
Safety Imolications of Technical Specification Chanan This proposed Technical Specification change has no adverse effect on safety. The now instrumentatinn is tested in accordance with the same surveillance procedure as other parts of the RWCU Leak Detection system. The coerability requirements of LCO 3.2.A will apply to these new temperature elemer.A If less than four instrument channels (temperature elements) are operabie per trip system, action statment 2.c (Table 3.2-1 on page 65) will require that the RWCU system be isolated. These two new temperature elements provido additional protection against pipe rupture and do not alter the conclusions of the plant's accident analyses as documented in the FSAR or the NRC staff's SER.
l
. 1 to JPN 92-055 SAFETY EVALUATION Page G of 7 5.
NYPA lotter, C. A. McNeill, Jr., to Stono and Webster, D. J. Cirrone, JAFP 83-1080 regarding Reactor Building high energy line break, dated October 28, 1983.
G.
NRC letter, A. Giambusso, to Licensees and License Applicants, dated December 18,1972 regarding the postulation of piping failures outsido containment.
7.
Stono and Webster Report J. O No.14MO.19, "High '
rgy Line Break (HF.LB)
Analysis in the JAFNPP Ruactor Building For Response to.2 Bulletin 79-01B,"
Revision 2 dated January 20,1984.
~
8.
James A. FitzPatrick Nuclear Power Plant Calculation 001 "RWCU Thermocouplo Response Timo Evaluation" Modificatiun F186-132, dated Novamber 30,1987.
9.
Gilbert / Commonwealth letter, M.S. Sarmiento to L. Guaquil, dated May 15, 1984, (gal-NYJF-073), " Modification F1-82-053 Additional Steam Loak Octoctors for Actuation of the RWCU and HPCI Isolation Valves - Cost Estimato."
- 10. Services Systems Engineering Memorandum, JSEM-91-073, "RWCU Leak Deto", tion Switch 12TS-iO2B Replacement," Revision 1, dated February 8, 1992.
- 11. NYPA letter. R..'. Converso, to Wood instrument Compny, R. Got! -
J AF P-87-0830, rogardino Environmental Qualification of Weed temperature sensors, dated October 15, i c87.
- 12. James A. FitzPatrick Nuclear Power Plant Instrument Surveillanco Proceduro, ISP-49, " Reactor Water Cleanup Up Area High Temperature Instrument Functional Test /Calil, ration," Revision 20, dated August 6,1991,
- 13. James A. FitzPatrick Nuclear Power Plant instrument Maintenance Proceduro, IMP G9, " Temperature Element (Thermocouple Types) and Associated Lnop Calibration," dated March 13,1992.
- 14. James A. FitzPatrick Nuclear Power Plant Surveillanco Test Proceduro, ST-40Ei,
" Daily Survoillance and instrument Chock," Revision 51, dated July 25,1992.
Background documentation not specifically referenced:
1.
James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report Sections 4.9 and 7.3.
2.
James A. FitzPatrick Nuclear Power Plant Final Safety Analysis Report, Supplement 25.
.m.
Attachment il to JPN-92-055 SAFETY EVAL.UATION Page 7 of 7 3.
James A. FitzPatrick Nuclect Power Plant Safety Evaluation Report (SER), dated Noven.ber 20,1972.
4.
James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report Supplement No.1, dated Februacy 1,1973.
5.
James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report Supplement No. 2, dated October 4,1974.
6.
James A. FitzPatrick Nuclear Power Plant Safety Evaluation for " Analog Transmitter Trip System (ATTS) Installation" Modification F182-053, JAF-SE-84-027, Revision 2, dated October 10,1984, i
i o
l-1
ATTACHMENT lil to JPN-92-055 PROPOSED TECHNICAL SPECIFICATION CHANGE REACTOR WATER CLEANUP LEAK DETECTION SYSTEM
' TABLE 3.2-1 REVISION MARKUP OF TECHNICAL SPECIFICATION PAGES (JPTS 91-029) l l
l.;
i l
l l
l New Yoik Power Authority JAMES A. FITZPATRICK 'llVCLEAR POWER PLANT Docket No. 50-333 DPR-59 l
JAFNPP TABLE 3.2-1 INSTRUMrtr7ATION THAT INITI A75 PRIMART COMIDENT ISQLA.llQt(
Minimuun Number of Total Number of Instrument Operable Instrument Channels Channels Provided by Design Action per Trio System (1)
Instrument Trio Level Settina for Both Trin Sysr===
(2) 2 (6)
Reactor Low Mater 1177 in. abovo TAF 4 Inst. Channels A
Level 1
Peactor High Pressure 175 psig 2 Inst. Channels D
(Shutdown Cooling Isolation) 2 Reactor Low-Low-Low
)_18 in, above TAF 4 Inst. Channels A
Mater Level 2 (6)
High Drywell Pressure f_ 2.7 p sity 4 Inst. Channels A
2 High Radiation Main 3,3 x Normal Rated 4 Inst. Channels B
Steam Line Tunnel full Power Background (9) 2 Los. Pressure Main 2_825 psig (7) 4 Inst. Channels B
Steam Line 2
High Y1ow Main Steam
__,140% of Rated Steam 4 Inst. Channels B
Line Flow 2
Main Steme Line Leak
$_40*F above max 4 Inst. Changels B
Detection High ambient Temperature h
3 Reactor Cleanup Sys-
__40*F above mar 6 Inst. Channels C
ter-Equipment Area ambient High Temperature fT 1
2 Low Condenspr Vaccum 1 8" Hg. Vac (7) (8) 4 Inst. Channels B
j Closes MSIV's Amendment No. 14, M, M, 64, 90, Pf3, kd, % 9 64
.