ML20149F306
| ML20149F306 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/1997 |
| From: | Todd F Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20149F291 | List: |
| References | |
| NUDOCS 9707220137 | |
| Download: ML20149F306 (6) | |
Text
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DOCKET NO.: 50-354 UNIT: Hope Creek l'
DATE: 'M/05/97 f.< :, \\; y COMPLETED BY:
F.
Todd-4?
'i TELEPHONE:
(609) -339-1316-
%1
[1I l'\\
o AVERAGE DAILY UNIT POWER LEVEL
' MONTH, MAY'1997 x
(
i;,.y'...
- DAY.' ; AVERAGE DAILY POWER LEVEL DAY
. AVERAGE DAILY POWER LEVEL H-
~"l
. (MWe-Ne t ) -
(MWe-Net)
L
- 1
-3046 l'7 1055 i'
i'
'2 :
.052-18 1054 l.
- 3 1049 19 1038
.4
'043:
20 1047 l 3 5'
"1057 21' 1052-i.
j l-6 1056 22.
1055 J
7
'1058 23 1050
. '8 l'054 24 1049
- l.
l.
9 1058 25
-1042-10 1053 26 1040
'll 103.2 27 945 12 1052-28 1044 13' 1054 29 1050 t.
14 1057 30 1047 1
1.5 '
1045 31 859 L
1
{
-16.
1051 l
i 6
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+
r DOCKET NO.: 50-354 UNIT: Hope Creek-D?fE: 07/05/97 COMPLETED BY:
L.
Kepley TELEPHONE:
(609) 339-1106
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION
' MONTH JUNE 1997 The following items completed during May 1997 Pave been evaluated to determine:
-1.
.If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased;-or 2.
If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety-analysis report may be created; or 3.
If the margin of safety as defined in the basis for any technical specification is reduced.
The'10CFR50.59 Safety Evaluations showed that these items did not.
create a new safety hazard to the plant nor did they affect'the safe shutdown of the reactor.
These items did not change the plant effluent releases and did not alter the existing environmental. impact.
The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
' Design Changes Summary of Safety Evaluations Radwaste Asphalt Drum Level Instrumentation Installation, 4EC-03161, Package 1, Revision O.
This design change modified the solid radwaste asphalt drum filling level monitoring and control loops by:
- 1) replacing the ultrasonic level transmitters with microprocessor based, parameter programmable, ultrasonic devices;
- 2) changing the scheme used to select the lead and standby fill p
stations; and '3) removing the'hi hi trip;of the extruder.
Since j
the fill. operation _is a slow procedure and is monitored by closed l
< circuit video,.the operator _will be able to terminate the filling i
operation.without reliance on the hi hi trip.
A hi alarn will alert:the operator-that the drum is close to full.
UFSAR section 11.4.2.4, which. described the level indication and control loops, was_ changed.
The asphalt drum system, its operation, or its failure do not contribute to or initiate any accident scenario postulated ' in the 'UFSAR.
The asphalt' drum system is not used to mitigate or preclude any accident described in the UFSAR.
The I
I
~.
- -- - ~~
~
w.
s asphalt drum system does not communicate, either physically or f
electrically, withiany system important~to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
Replacement of Air-Operated Valves in.the Safety Auxiliaries Cooling. System (SACS),'4EC-03612, Package 13, Revision O.
The' Residual. Heat Removal (RHR).. pump room cooler water supply valves iri the SACS.were replaced.
-The previous valves were carbon steel air. actuated flexible-wedge' gate valves.
The replacement valves
-are stainless steel air actuated ball-valves which are more
. suitable-to the application.
UFSAR Figure 9.2-4 was changed-to show the type and material of the replacement valves / actuators.
UFSAR Table 3.9-18 was changed to show the veP;e/ actuator
. replacement type.
This replacement does not change the function
~f the valves or the. function of the affected systems.
The o
change does not alter the ability of the SACS, the Equipment Area
- Cooling' System (EACS), or the RHR pump room unit coolers ~to perform their intended safety functions.
The affected systems will function in accordance'with'the original design and licensing basis of-the plant.
Therefore, this design change does involve an Unreviewed Safety.
' Question.
Replacement of Air-Operated Valves in the Safety Auxiliary Cooling System (SACS), 4EC-03612, Package 18, Revision-O.
The High Pressure Coolant Injection (HPCI) pump room cooler water supply valves in the SACS were replaced.
The previous valves were carbon steel air actuated flexible-wedge gate valves.
The replacement valves are stainless steel. air actuated ball valves which are more suitable to.the application.
UFSAR Figure 9.2-4 was changed to show the type.and material of the replacement valves and actuators.
UFSAR Table 3.9-18 was changed to show the valve / actuator replacement type.
This replacement does'not change the function of the valves or the function of the affected systems.
The change does not alter the ability of the SACS,'the Equipment Area Cooling System (EACS), or the HPCI pump room unit coolers to perform their intended safety function.
The affected systems will function in accordance with the original design and licensing basis of the plant.
Therefore, this design change does not involve an Unreviewed Safety-Question.
i Replacement of. Air-Operated Valves.in the Safety Auxiliaries Cooling System (SACS), 4EC-03612, Package 22, Revision O.
The Filtration,' Recirculation, Ventilation System _(FRVS) l
~,
. _ ~
e
. u..
s s
l Recirculation System cooling coil water supply' valves in the SACS "were replaced.
The previous. valves were carbon steel air actuated flexible-wedge: gate valves.
The replacement valves are stainless steel air actuated ball valves which are more suitable tosthe application.
UFSAR Figure 9.2-4 was changed to show the type and material of'the replacement valves and actuators.
UFSAR TableL3.9-18.was changed to show the valve / actuator replacement 1 type.
This replacement does not change the function of the valves or.the function of the affected systems.
The' change does not alter the ability of the SACS or the FRVS Recirculation
. system to perform'their intended. safety functions.
The affected
. systems will function inLaccordance with the original design and Elicensing basis of the plant.
Therefore, this design change does not involve an.Unreviewed Safety Question, y
Replacement of Air-Operated Valves in the. Safety Auxiliaries Cooling System (SACS), 4EC-03612, Package 29, Revision'O.
The Core Spray (CS) pump room cooler water supply valves in the SACS were replaced.
The previous valves were-carbon. steel air.
actuated flexible-wedge gate valves.
The replacement ~ valves are stainless steel' air actuated ball valves which are more suitable to.the application.
UFSAR Figure 9.
4 was changed to-show the l
type and material of the replacement valves and actuators.
(
Table 3.9-18 was changed to show the valve / actuator replacement l
type.
This replacement does-not change the function of the valves or the function of the affected systems.
The change does not-alter the ability of the SACS, the Equipment Area Cooling l
System (EACS), or the CS pump room' unit coolers to perform their l
intended safety functions.
The affected systems will function in accordance with the original design and licensing basis of the plant.
Therefore, this design change does not involve an Unreviewed j
Safety Question, q
Station Service Water System (SSWS) Pumps Pit Level Transmitters j
h Removal / Abandonment, 4HE-00265, Package.
1,. Revision O.
This R
l design change. removed the SSWS pumps'suc' on level l
instrumentation loops (lEALIT-2241A through 1EALIT-2241D and
[
their associated instruments).
.These were non-safety related i,
loops that were designed to monitor the wacer levels in the SSWS L
pump bays _for recording / indication in the Main Control Room.
These indications were not'used by the operators nor were they required for the operation of the.SSWS pumps.
The operating procedures did not rely upon these instrumentation loops for any safety-related function or operation.
Removal of these instruments did not affect the operation of the SSWS nor did it 4
4 r
e D
~..
g :.. -
I aff,ect the design basis'of the system.
This design change did
, not involve'any unique tests or experiments.
Therefore,,this design change does not involve an Unreviewed Safety Question.
Remove Flow Switch 1EPFS-2225C, 4HE-00356, Package 3, Revision O.
L Previously implemented and reported design change 4EC-03453, l~
Package 1 1(erroneously reported in the December 1994 Monthly
'OperatingLReport as' design change 4EC-5343, Package 1) modified l
the station service water system (SSWS) traveling screen logic
'and disconnected the cables of the service water screen and L
backwash flow switch 1EPFS-2225C, but left the flow switch in L
place.
Design change 4HE-00356 removed the flow switch, lEPFS-
~
2225C, and installed gaskets and a blind flange in place of the
' flow switch.
Stress and seismic evaluations have been performed j
to_ demonstrate the adequacy of the change.
The replacement of i
the flow switch with a blind flange does not affect the amount of flow being provided to the Reactor Auxiliary Cooling System (RACS) and Safety Auxiliary Cooling System (SACS) heat exchangers during plant conditions, transients, and accident conditions.
l
-The change does not:
- 1) change, degrade, or prevent actions described or assumed in any accident described in the UFSAR, 2) alter any assumptions previously made in evaluating radiological consequentes of any accident described in the UFSAR, 3) affect the mitigation of the radiological consequences of any accident described in the UFSAR, 4) affect a fission product barrier, or
- 5) ' change the composition or inventory of radioactivity releases.
L This change does not adversely affect the operability of the Station Service Water System (SSWS).
Therefore, this design change does not involve an Unreviewed Safety Question.
6-UFSAR Change Notices Summary of Safety Evaluations l
UFSAR Change Notice H97-022, UFSAR Sections 13 & 17, Transfer of Quality Verification (QV) from Manager - Corrective Action &
Quality Services (CA&QS) to the Manager - Quality Assessments (QA). _This.UFSAR change reflects a realignment of the QV
-functions from the Manager - CA&QS to the Manager - QA.
The l
realignment of responsibility for the OV functions to the Manager
- QA'has no direct affect on any systems, structures, or I
components as ' described in the Salem and Hope Creek UFSARs.
This change will not reduce the level-of management control and authority, responsibill. ties, training or qualifications of personnel, or anyLQA program commitments.
The Quality Assurance 1
program, as described in the Hope Creek and Salem UFSAR Section
.i 17.2, will continue to meet the criteria of 10CFR50 Appendix B.
0
j 1
I
..A
... ; o Therefore, this UFSAR change-does not involve an Unreviewed Safety Question.
1 UFSAR Changs Notice H97-026, UFSAR Sections 13.1 & 17.2, Transfer of Project Managers and Functions from Nuclear Engineering to i
Nuclear Business Support.
This change transferred the responsibility for Project Management from Nuclear Engineering to Nuclear. Business Support in UFSAR Sections 13.1 and 17.2.
The change realigned organizational' relationships to affect a more positive control of Nuclear Business Unit (NBU) activities.
The change had'no effect on any systems, structures, or components described in the UFSAR.
The change did not result in any 1
reduction in the qualifications and training requirements of personnel,' technical support for plant operations, management j
control and authority, administrative program commitments or quality assurance program.
This change meets the intent of the NUREG 0800.
The revised organization will improve alignment of responsibilities and management focus on activities related to plant safety, Therefore, this UFSAR change does not involve an Unreviewed i
l Safety' Question.
Procedures Summary of Safety Evaluations NC.NA-AP.ZZ-0035(Q), Revision 7, Nuclear Licensing and Reporting.
This procedure revision deletes the attachment that detailed the description of the station ~ reporting requirements and served as a reference for the station staff to indicate which reports are l
required by federal, state, and local agencies.
The text of the procedure continues to provide sufficient guidelines for the i
[
preparation, review, and submittal of correspondence to the NRC.
l This is an administrative change only.
The: -: fore, this procedure change does not involve an Unreviewed Safety Question.
Temporary Modifications Summary of Safety Evaluations
' Deficiency Reports Summary of Safety Evaluations l-Other Summary of Safety Evaluation I
There were no changes in these categories implemented during May 1997.
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