ML20211J202
| ML20211J202 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/04/1986 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20211J167 | List: |
| References | |
| NUDOCS 8611110033 | |
| Download: ML20211J202 (10) | |
Text
_
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
If any periodic Type A test fails to meet. 75 La the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet.75 La a Type A test shall be perfonned at least every 18 months until two j
consecutive Type A tests meet.75 La at which time the above test i
schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within
{
0.25 La -
2.
Had a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at Pa, 49.6 psig, d.
. Type B and -C tests shall be conducted with gas at Pa, 49.6 psig at intervals no greater than 24 months except as noted in Table 3.6-1 and for tests involving:
1.
Air locks, 2.
Penetrations using continuous leakage monitoring systems, and 3.
Valves pressurized with fluid from a seal system.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
8611110033 861104 PDR ADOCK 05000302 P
PDR CRYSTAL RIVER - UNIT 3 3/46-3 Amendment No, s
~
F TABLE 3 6-1 (Continu:d) 0 h
CONTAllMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME g.3 -
7
.(seconds) 9.
MUV-40 (A)*
iso. MU system from RC 60 l
-MUV-41 (A)*
60 MUV-49 (B) g 60 MUV-261 iso. MU system from 60 g
control bleed-off MUV-260 60 MUV-259 60.i MUV-258 60 T
MUV-253 60 i
a 4:
MUV-163 check #
open during HPI and NA closed dur. nor, operation MUV-25 #
60 MUV-164 check #
NA MUV-26 #
60 MUV-160 check #
NA MUV-23 #
60 MUV-161 check #
NA MUV-24 #
60 MUV-27 #
open dur, nor, operation 60 and closed during RB Isolation
'10.
SWV-39 #
iso.
NSCCC from AHF-1C 60 SWV-45 # 3 60 SWV-35 #
iso. NSCCC from AHF-1A 60 SWV-41 #
60
=
SWV-37 #
iso. NSCCC from AHF-1B 60 SWV-43 #
6u SWV-48 #
- iso. NSCCC from 60
\\
MUHE-1A & 18 and WDT-5 l
SWV-47 #
- 60 l
SWV-49 #
- 60 l
SWV-50 #
- 60 l
SWV-80 #
iso. NSCCC from RCP-1A 60 SWV-84 #
60 i
SWV-82 #
iso. NSCCC from RCP-1C 60 SWV-86 #
60 I
3
.t CRYSTAL RIVER - UNIT 3 3/4 6-19 Amendment No.
TABLE 3.6-1 (Continutd)
CONTAllMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds)
Blind Flange 348 iso. fuel transfer tube from NA
' Transfer Canal Blind Flange 436 NA Equipment Hatch iso. RB NA 4
Personnel Hatch iso. RB NA
- Not subject to Type C Leakage Test
- Need not be subject to Type C Leakage Test until Refuel VI
- The provisions of Specification 3.0.4 are not applicable.
+ May be opened on an intermittent basis under administrative control consisting of a dedicated operator stationed at the valve in continuous communication with the control room with necessary parameters to rapidly isolate the penetration on a valid indication.
(A)
Isolates on Diverse Isolation Actuation Signal A (B)
_ Isolates on Diverse Isolation Actuation Signal B (A/B)
Isolates on Diverse Isolation Actuation Signal A or B CRYSTAL RIVER - UNIT 3 3/4 6-21a Amendment No.
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 REQUEST NO.1498, Revision 0 CONTAllMENT ISOLATION VALVES / LOCAL LEAK RATE TESTS -
LETDOWN COOLER ISOLATION LICENSE DOCtMENT INVOLVED: Technical Specifications PORTIONS:
Surveillance 4.6.1.2.d, Page 3/4 6-3 Table 3.6 Item 9, Page 3/4 6-19 Table 3.6 Footnote, Page 3/4 6-21A DESCRIPTION OF REQUEST:
This submittal requests that provisions be provided for valves MUV-40, MUV-41, and MUV-49 such that these valves "need not be subject to Type C Leakage Test until Refuel VI".
MUV-40 and MUV-41 are 2-1/2" motor operated gate valves located near the letdown coolers inside containment.
MUV-49 is a 2-1/2" air operated gate valve located outside containment in the Auxiliary Building. These valves are containment isolation valves and receive a signal to close when HPI is actuated.
These valves isolate the makeup system from the reactor coolant system.
REASON FOR REQUEST:
Appendix J to 10 CFR 50 and Technical Specification surveillance 4.6.1.2.d requires that Type C leakage tests of containment isolation valves be performed at intervals no greater than 24 months.
Local Leak Rate Tests (LLRTs) were performed during Refuel V on valves subject to Type C tests. The next LLRTs would be performed during Refuel VI.
Due to the length of the Reactor Coolant Pump (RCP) outage, fuel cycle VI was extended until Fall of 1987.
The 24 month surveillance period would expire before start of Refuel VI, therefore, Florida Power Corporation (FPC) proceeded with Type C testing of containment 1 solation valves during the RCP outage (9t approximately twelve months into the 24-month surveillance interval).
However, some containment isolation valves were not tested.
The reasons for not testing valves MUV-40, MUV-41, and MUV-49 are as follows:
- 1) testing had been performed approximately 12 months prior and the acceptance criteria were met; 2) from the ALARA standpoint, these three valves would require more manrem exposure than other containment isolation valves; and 3) previous test resul ts showed li ttle valve degradation compared to the acceptance criteria.
SAFETY EVALUATION OF REQUEST:
The tests for these valves were last performed July 15, 1985' and the results showed little valve degradation when compared to the acceptance criteria.
As a result of the 24 month surveillance interval, the next scheduled LLRT for these valves is July 15, 1987.
However, Refuel VI is not scheduled to begin until September 19, 1987. This one-time exemption request represents an approximate ten week extension to the LLRT for these three valves.
Based on the valves' test history and the length of the extension, degradation is not expected to be significant during the period until the next test.
The LLRT test connections for makeup system valves MUV-40, MUV-41, and MUV-49 are located in the Letdown Cooler Room in the Reactor Building.
The connections are between the coolers themselves and the D-ring wall.
In order-to install the required test connection fl anges, mechanics must position themselves in contact with the coolers. Before testing can begin, the coolers must be completely drained of all liquid.
Radiation surveys showed the Letdown Coolers reading 1R/hr on contact and 800 mr/hr in the general area.
In addition, there were hot spots, on the coolers, and in the immediate vicinity of the coolers, that read 2 to SR/hr.
Test flange installation and removal requires approximately.two manhours. Based on general area radiation levels alone, it was expected that 1.6 manrem exposure would result from test flange installation and removal.
Test personnel would have received 0.24 manrem connecting test equipment to the test fl ange.
Operations personnel would have received additional exposure hanging the required equipment clearances, aligning the system, and draining the liquid from the coolers in preparation for the test.
In summary, 1.84 manrem was estimated for the performance of LLRT for these three valves compared to the actual 0.5 manrem expended to - perform LLRTs on the approximately 110 remaining containment isolation valves (excluding the five Reactor Coolant Pump (RCP) seal return valves addressed in part A of this request) during the RCP outage.
SHOLLY EVALUATION OF REQUEST:
Florida Power Corporation (FPC) proposes this amendment does not involve a significant hazards consideration.
The change to the surveillance-frequency for Type C leak rate testing of the letdown cooler containment isol ation valves is a one-time only extension.
These valves are required to be leak rate tested every 24 months.
The last leak rate test for these valves was performed July 24, 1985 and the results showed little valve -degradation when compared to the' acceptance criteria.
The surveil 1ance extension requested is.
a temporary one which will exist for approximately ten weeks.
Based on the valves' test history, degradation is not expected to be significant during the period until the next test.
Based on the above, FPC finds the amendment will not:
1)
Involve a significant increase in the probability or consequence of an accident previously evaluated because the valves were last tested sati sf actorily and degradation is not expected to be significant during the period until the next test.
2)
Create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change introduces no new mode of plant operation nor does it requi re a physical modification.
3)
Involve a significant reduction in the margin of safety.
Any reduction of the margin of safety will be insignificant since the surveillance interval extension will be short (approximately ten weeks in length).
~rv
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
If any periodic Type A test fails to meet.75 La the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet.75 La a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet.75 La at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms.the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La.
2.
Had a duration sufficient to_ establish accurately the change in leakage between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at Pa 49.6 psig.
d.
Type B and C tests shall be conducted with gas at Pa, 49.6 psig at intervals no greater than 24 months except as noted in Table 3.6-1 and for tests involving:
1.
Ai r locks, 2.
Penetrations using continuous leakage monitoring systems, and 3.
Valves pressurized with fluid from a seal system.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
CRYSTAL RIVER - UNIT 3 3/4 6-3 Amendment No.
TABLE 3.6-1 (Continued)
CONTAIPMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds) 9.
MUV-40 (A)*##
iso.-MU system from RC 60 MUV-41 (A)*##
60 MUV-49 (B)##
60 MUV-261 iso. MU system from 60 control bleed-off MUV-260 60 MUV-259 60 MUV-258 60 MUV-253 60' MUV-163 check #
open during HPI and NA c1osed dur. nor. -operation MUV-25 #
60 MUV-164 check #
NA MUV-26 #
60 MUV-160 check #
NA MUV-23 #
60 MUV-161 check #
NA MUV-24 #
60 MUV-27 #
open dur. nor. operation 60 and closed during RB Isolation
- 10. SWV-39 f iso.
NSCCC from AHF-1C 60 SWV-45 #
60 SWV-35 #
iso. NSCCC from AHF-1A 60 SWV-41 #
60 SWV-37 #
iso. NSCCC from AHF-1B 60 SWV-43 #
60 SWV-48 #
- iso. NSCCC from 60 MUHE-1A & 18 and WDT-5 SWV-47 #
- 60 SWV-49 #
- 60 SWV-50 #
- 60 SUV-80 #
iso. NSCCC from RCP-1A 60 SWV-84 #
60 SWV-82 #
iso. NSCCC from RCP-1C 60 SWV-86 #
60 CRYSTAL RIVER - UNIT 3 3/4 6-19 Amendment No.
TABLE 3.6-1 (Continurd)
CONTAIMENT ISOLATION VALVES
' VALVE NUMBER FUNCTION ISOLATION TIME (seconds)
Blind Flange 348 iso. fuel transfer tube from NA l
Transfer Canal l
Blind Flange 436 NA Equipment Hatch iso. RB NA Personnel Hatch iso. RB NA
- Not subject to Type C Leakage Test
- Need not be subject to Type C Leakage Test until Refuel VI
- The provisions of Specification 3.0.4 are not applicable.
+ May be opened on an intermittent basis under administrative control consisting of. a dedicated operator stationed at.the
. valve in continuous communication with the control room with necessary parameters to rapidly isolate the penetration on a valid indication.
(A)
Isolates on Diverse Isolation Actuation Signal A (B)
Isolates on Diverse Isolation Actuation Signal B (A/B)
Isolates on Diverse Isolation Actuation Signal A or B CRYSTAL RIVER - UNIT 3 3/4 6-21a Amendment No.
LOCAL LEAK RATE TEST RESULTS VALVE NUMBER REFUEL IV REFUEL V AS FOUND AS LEFT AS FOUND AS LEFT (sccm)
(sccm)
(sccm)
(sccm)
(April 1983)
(July 1983)
(April.1985)
(July 1985)
MUV-253 2*
No Retest 20*
No Retest MVV-258 6.75 2*
35.2 186.4 MUV-259 2*
2*
20*
20*
MUV-260 2*
148.2 20*
20*
MUV-261 2*
2*
20*
20*
fiUV-40 4.1 2*
20*
20*
MUV-41 1375 9200 9350 4920 t
MUV-49 459 No Retest 3300 56.9
- The differences between 2 and 20 are the result of the minimum sensitivity of the instruments used during the leak-rate test.
1
LOCAL LEAK RATE ACCEPTANCE CRITERIA Florida Power Corporation _ tests containment isolation valves to the requirements of 10 CFR 50 Appendix J. - The testing program does establish valve leakage limits based upon valve diameter (i.e., a twelve inch valve
~
would be allowed - twice the leakage of a six inch valve).
The total combined leakage of all type B (non valve penetrations) and Type C (valves) must not exceed 0.6La.
La (percent /24 hours) is the maximum 64.3 psia.
Total allowable leakage rate at pressure Pa, where Pa
=
allowable leakage (0.6La) has been calculated to be 248,656 scc / min. The sum of Type C valve diameters is approximately 93 inches.
Dividing this value into 0.6La results in a maximisn allowable leakage for valves of 2386 scc / min / nominal inch. The Appendix J program assigns an Alert value of 70% and an Action limit of 95% of 2386 scc / min / nominal inch for each valve -(i.e.,
for a 4 inch valve diameter:
Alert = 6680 scc / min: Action
= 9040 scc / min).
The present program requires a review and evaluation of leakages exceeding the Alert value and " judicious" repair or replacement for leakages exceeding-the Action limit.
Some flexibility exists for valves leaking above the Action limit to permit considering the total valve leakages to. justify deferral of repair.
In no case, however, can any valve leakage exceed 0.15La.
The existing Florida Power program offers an effective, conservative approach to monitoring containment isolation valve. leakages.
.