IR 05000388/1984042
| ML17139C731 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/16/1984 |
| From: | Bettenhausen L, Florek D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17139C728 | List: |
| References | |
| 50-388-84-42, NUDOCS 8412110278 | |
| Download: ML17139C731 (17) | |
Text
U. S
~
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-388/84-42 Docket No.
50-388 License No.
NPF-22 Priori ty Category C
Licensee:
Penns lvania Power and Li ht Com an 2 North Ninth Street Allentown Penns 1 vania 18101 Facility Name:
Sus uehanna Steam Electric Station Unit 2 Inspection At:
Salem Townshi Penns lvania Inspection Cond d:
0 tobe 2-5 1984 Inspectors:
D. J.
Florek, Lead Reactor Engineer ate Approved by:
.
H. Bettenhausen, Chief Test Program Section date Ins ection Summar
Inspection on October 2-5, 1984 (Report No. 50-388/84-42)
Areas Ins ected:
Routine unannounced inspection of Unit 2 Startup Test Program during test conditions TC-5 and 6.
The inspection included overall startup test program, test results evaluation and compliance with technical specification on Minimum Critical Power Ratio.
The inspection involved 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> on site by one region based inspector.
Results:
One violation was identified.
(Inadequate surveillance procedures regarding End of Cycle Recirculation Pump trip Instrumentation).
@4J2i i'O>7~()gpgppQB)
g ggii.20
>>p ADDCK o p~R
g r
1.
Persons Contacted Penns lvania Power and Li ht Com an F. Butler, Instrument and Control Supervisor
'P. Capatosto, NQA Engineer T. Clymer, NQA Coordinator A. Dominguez, Lead Plant Engineer J. Glasser, Unit 2 I&C Foreman H. Keiser, Plant Superintendent J. Klucar, Lead Shift Test Engineer R. Kreider, QA Engineer T. Nork, Startup Coordinator
"A. Piemontese, Compliance Engineer R. Prego, Operations QA Supervisor
~R. Sheranko, Startup Test Group Supervisor C. Smith, Power Production Engineer
- D. Thompson, Assistant Plant Superintendent J.
Todd, Compliance Engineer J. Zentz, Startup Test Engineer U.S. Nuclear Re ulator Commission
"R. Jacobs, Senior Resident Inspector L. Plisco, Resident Inspector The inspector also contacted several other licensee employees, including members of the technical and Quality Assurance staffs, unit supervisors, and reactor operators.
- Denotes those present at exit meeting on October 5, 1984.
2.
Startu Test Pro ram References
~
'usquehanna Steam Electric Station (SSES)
Final Safety Analysis Report SSES Safety Evaluation Report and Supplements 1, 2, 3, 4, and
Regulatory Guide 1.68, "Initial Test Programs for Water Cooled Reactor Power Plants" SSES Startup Test Schedule AD-TY-460 Startup Test Administrative Procedure J
2.1
\\
Overall Startup Test Program
~Sco e
The inspector reviewed ST-99.6,
"Test Plateau 4 (100%
ROD Line)
Testing", to assess whether the completed and planned testing at test conditions TC-4, 5, and 6 satisfied commitments in FSAR Chapter 14.
~Findin s
The inspector verified that the completed and planned testing satisfied FSAR commitments.
No unacceptable conditions were noted.
2.2 Test Results Evaluation
~Sco e
The 29 test results listed in Appendix A were reviewed.
Inspection report 50-388/84-21, Section 2.6, describes the scope of the test results evaluation inspection.
In addition, the test results of Appendix A of Inspection report 50-388/84-38 were reviewed for acceptance of test results by management and Test Review Committee (TRC) and Plant Operations Review Committee. (PORC) review.
~Findin s
The test results listed in Appendix A to Inspection Report 50-388/84-38 were verified to have been accepted by management and reviewed by TRC/
PORC.
Except as noted below, each test listed in Appendix A of this report and change thereto was approved in accordance with the adminis-trative procedures; test objectives were met, test exceptions were noted, all data was obtained, test steps and data sheets were properly signed, an independent evaluation of test data was performed, and test results were compared with acceptance criteria, test briefings were conducted prior to the conduct of each test, TRC/PORC review had not yet been performed, gA review of the test results was in process and management had not yet accepted the test results.
The last three items will be assessed in a subsequent inspection.
A summary of each startup test is provided in the following discussio ST-1.7 Chemistry Data Test was conducted with an exposure of 558 effective full power hours and reactor at approximately 75% power.
Reactor Water Cleanup Chemistry Parameter Value Acce tance Criterion Conductivity (umho/cm)
Chloride (ppb)
pH I-131 Dose Equivalent (j Cu/gm)
.5
<20 6.6
<LLD
<1
<200 5.6-8.6
<.2 TER-131 was written on the following out-of-specification items:
Value Acce tance Criterion Feedwater pH CRD oxygen ppb 6.4 6.5 - 7.5
<50 I
Feedwater metallic solids and copper could not be obtained.
ST-2-1 Radiation Survey With the reactor at 99.4% power four test exceptions were identified (TER-140-143).
Two areas in the turbine building and two areas in the reactor building exceeded 2.5 m rem/hr.
The highest reading was
mrem/hr.
ST-12.2 APRM Calibration This test was done at 70.8% power and 98% power.
All acceptance criteria were satisfied.
A summary of results follows.
Reactor power Reactor pressure Total Core flow s
APRM A
C E
B D
F Desired 70.6 70.6 70.6 70.6 70.6 70.6 70.8%
~958 si 62.2 mlb/hr Actual 70.94 71.62 7i.31 71.44 71.19 71.07 Desired 98.2 98.2 98.2 98.2 98.2 98.2 98%
~987 si 99.6 mlb/hr Actual 98.3 99.1 98.7 98.7 98.3 9 ST-15.3 HPCI Auto guick Start to Vessel This test was conducted at 73.6% power with the reactor at 960 psig.
HPCI failed the level I acceptance criterion for achieving greater that 5000 gpm in less than 25 seconds since it took 26.3 seconds to achieve 5000 gpm.
TER-133 was written.
Repair and retest is planned.
HPCI did meet technical specification performance so that other testing was continued.
ST-19.2 Core Performance The test was performed at 70.8 and 99.6% power.
Acceptance criteria were satisfied.
A summary of results is:
Reactor power,
%
Reactor pressure, psig Total Core flow, mlb/hr ~',
MFLCPR MFLPD MAPRAT 70.8 958 62.3
.774
.647
.619 98.6 988 99.6
.814
.875
.878 ST-21. 1 Core Response to Control Rod Movement With reactor power at 60.3%, reactor pressure at 948 psig and total core flow 48.9 mlb/hr, rod 46-43 was inser ted two notches.
LPRM string 48-41 was utilized to demonstrate that greater than 5% change in steady state value was obtained.
No divergent parameters were observed.
Acceptance criteria were satisfied.
ST-21.2 Core Response to Pressure Change With reactor power at 61. 1%, reactor pressure at 948 psig and total core flow of 48 '
mlb/hr, an approximately 10 psi step change in reactor pressure produced no divergent osci llations as indicated by LPRM string 48-41.
ST-22. 1 Pressure Regulator Control Valve Controlling This test was performed at 70% and 99.3% power.
Acceptance criteria were satisfied.
No divergent osci llations were noted.
A summary of results is:
Reactor Power,
%
Reactor pressure, psig Total core flow, mlb/hr Margin to scram-flux Margin to scram-pressure
958 62.4 42%
81 psi 99.3 988
'9.5 12%
52 psi
ST-22.2 Pressure Regulator Control Valve Controlling This test was conducted at 70% and 99.3% power.
Acceptance criteria were satisfied.
No divergent osci llations were noted.
ST-22.3 Pressure Regulator Control Valve and Bypass Valve Controlling.
With the reactor at 70% and reactor pressure at 958 psig, a step change in pressure was initiated.
No divergent oscillations were noted.
Acceptance criteria were met.
ST-23.2 Feedwater Manual Flow Step Changes The test was performed on all three feedwater pumps at approximately 99.9% power.
The level I acceptance criteria were satisfied.
Level 2 test exceptions were identified for each pump.
PUMP TER Reason 138 139 137 136 Overshoot greater than 15%
Rate of response was less than 10%
Overshoot greater than 15%
Overshoot greater than 15%
ST-23.2 Feedwater Level Setpoint Changes ST-29. 1 The test was performed at 73.7% power.
All acceptance criteria were satisfied.
No divergent oscillations were noted.
Recirc A Flow in Local Manual.
This test was done at 70.4% and 94.2% reactor power Reactor power,
%
M-G A speed,
%
M-G-B speed,
%
Total Core flow, mlb/hr Margin to scram flow-biased flux 70.4
45
16%
38%
94.2
72 89.9 15%
21.7%
No divergent osci llations were noted.
met.
Acceptance criteria were
ST-29.1 Recirc B Flow Steps in Local Manual This test was done at 70.4% and 94.2% power Reactor power,
%
M-G-A speed,
%
M-G-B speed,
%
Total Core flow, mlb/hr Margin to scram flow-biased flux 70.4
45
16%
38%
94.2
72 89.9 14.7%
21.3%
No divergent osci llations noted.
Acceptance criteria were met.
ST-32.2 Containment Temperature at Steady State One test exception (TER-131)
was identified because the minimum shield wall area temperature was 82', with a minimum allowable value of 100'F.
A summary of other temperatures follows:
Parameter Value
'F Acce taece Criteria CRD area Average dry well temp
~
Maximum local drywell (Max average area below)
reactor vessel Min. local under vessel Average drywell head Maximum drywell head 113 123 129 109.5 102 137.5 140
<185
<135
<150
<135
>100
>135
<150 ST-33. 1 Steady State Vibration Main Steam Piping Inside Drywell This test was conducted at 98.9% power.
One level 2 test exception was noted (TER-135).
One point exceeded the 80 mil limit; the peak to peak value was 139 mi 1. Instrument error is suspected.
ST-33.2 ST-33.3 Steady State Vibration Main Steam and Feedwater Piping Outside Drywell At 99% power all acceptance criteria were satisfied.
Steady State Vibration Recirculation Piping This test was conducted at 63.5%
81.7% and 99% power.
Reactor power,
%
Total Core flow, %
A pump speed,
%
B pump speed,
%
63.5 81.7
50.4 75.4
32
80
57
Vibration levels were well within acceptance criteri ST-37. 1 Gaseous Radwaste Effluent Verification Initial conditions were reactor power 74.5%, reactor pressure 961 psig and total core flow 62.8 mlb/hr.
The effluents measured were:
<LLD Kr-85
<LLD Ar-41 1.31X10-5 Acceptance criteria were satisfied.
3.
Technical Specification Compliance on Minimum Critical Power Ratio
~Sco e
The inspector held discussions with reactor engineering personnel and instrumentation and control personnel.
He reviewed the documents listed below to verify compliance with technical specifications 3.2.3, 3.3.4.2, and 3.7.8, The documents reviewed were RE-OTP-021, Process Computer data book, ST-5.3, SI-283-313, SI-283-314, SI-283-413, SI-283-514, SM-264-003, SSES Technical Specification Matrix PLIS-17,311, AD-gA-422, and SA-A32774.
~Findin s
The inspector verified that the MCPR Limit determined by use of technical specification figure 3.2.3-1 is manually inserted into the computer and was properly established using the scram time derived from startup test ST-5.3 which satisfied technical specification 3. 1.3.2.
The K (f) curve utilized in the computer for automatic flow control was K (f)= 1+.44 (1-WT/WTR) and is consistent with figure 3.2.3-2.
Based on the interview with reactor engineering personnel, the process computer values are changed per figure 3.2.3-1 based on surveillance operability determination for the turbine bypass and end-of-cycle recirculation pump trip and are requested by operations.
Technical Specification (TS) matrix which verified that surveillance activities were identified was reviewed.
Technical Specification survei 1-lance requirements for the turbine bypass system were satisfied by SO-293-002; a review of this procedure showed results were satisfactor The end of cycle recirculation pump trip TS compliance is summarized below.
Mhere the surveillance procedure was determined to be unacceptable, additional discussion follows.
Technical S ecification and Descr i tion Surveillance-.Ance table Procedure Table 3.3.4.2-2 Setpoint Turbine Stop Valve Closure Setpoint Turbine Control Valve-Fast Closure SI-283-313 No S I-283-314 No Table 3.3.4.2.3 Response Time Turbine Stop Valve Closure Response Time Turbine Control Valve SI-283-413 No Fast Closure 4.3.4.2. 1 Channel Functional Channel Calibration SI-283-413 No SO-293-001 Yes SI-283-313 Yes 4.3.4.2.2 Logic System Functional SI-283-514 No.
4.3.4.2.3 Response Time Turbine Stop Valve Closure Response Time Turbine Control Valve Fast Closure S I-283-413 No SI-283-413 No 4'.4.24 Breaker arc suppression SM-264-003 No
SI-283-313 did not indicate that it satisfied Technical Specification table 3.3.4.2-2 nor did it refer to the action statements of Technical Specification 3.3.4.2 if acceptance criteria were not satisfied.
Thus MCPR limits.would not be modified as a result of the test.
Discussions with instrumentation and control system representatives indicated that SI-283-313 was established to satisfy this Technical Specification.
The setpoint established in the surveillance procedure did, however, meet the Technical Specification.
SI-283-413 did not account for the total End-of-Cycle Recirculation Pump Trip response time.
The surveillance procedure only addressed the instru-ment response time and did not address the breaker arc suppression time.
Interview with instrumentation and control and technical personnel indi-cated that there was no procedure developed to accomplish this activity.
The inspector verified that the instrument response times from SI-283-413 added to the breaker arc suppression time from the preoperational test program satisfied the Technical Specification.
SI-283-514 was found to reference action statements that did not exist in Technical Specifi-cations.
SM-264-003 was found not to contain the required breakers for arc suppression time data.
It will be replaced by SM-264-005 which will be developed prior to its need (approximately 60 months),
since the data derived from the preoperational test is still valid.
When the problem was identified, the licensee also reviewed the procedures affecting Unit 1; similar procedural problems exi sted which the licensee committed to resolve.
On Unit 1, the licensee utilized the MCPR limit assuming the end-of-cycle recirculation pump trip is inoperable.
The resolution to Unit 1 procedures will be assessed along with Unit 2.
The inspector stated that the failure to have adequate surveillance procedures to determine compliance with Technical Specifications was contrary to Technical Specification 6.8. 1.C and the licensee administ-rative procedure AD-QA-422 "Surveillance Testing Program" Revision 5.
This is a violation (388/84-42-01).
4.
ualit Assurance Interface 5.0 During the inspection the inspector observed that Quality Assurance reviews were completed on test condition 5 Startup tests ST-12.2, 19.2, 22. 1, 22.2, 22.3, 29. 1, 33.3 and 37. 1.
The inspector also reviewed Quality Assurance Surveillance Reports (QASR)84-108 (ST-33.2,84-110 (ST-18.1),84-114 (ST-21.1),
and 84-113 (ST-29.1).
The inspector also noted that ST-35. 1 Q35 was reviewed subsequent to the plateau review of test condition 3.
The licensee indicated that this was a retest requested by the TRC.
TRC/PORC and management had accepted the results
'f the review.
No acceptable conditions were noted.
Tours of Facilit The inspector made several tours of the facility during the course of the inspection including the reactor building, turbine building, control
structure, and control room.
The inspector also observed work in progress, housekeeping, and cleanliness.
No unacceptable conditions were noted.
6.0 Exit Interview At the conclusion of the site inspection on October 5, 1984 an exit meeting was conducted with the licensee's senior site representatives (denoted in paragraph 1).
The findings were identified and previous inspection items were discussed.
At no time during this inspection was written material provided to the licensee by the inspecto Appendix A Test Results Evaluation 1.
"Chemistry Data-Power Ascension Test", Revision 1, Test Implemented September 26, 1984.
2.
ST-2. 1
"Startup Test Program Radiation Survey", Revision 5, Test Implemented September 29, 1984.
3.
ST-12. 2 4.
ST-12. 2
"APRM Calibration at High Power (75%)", Revision 2, Test Implemented September 25, 1984.
"APRM Calibration at High Power (100%)", Revision 2, Test Implemented September 29, 1984.
5.
ST-15.3 HPCI Auto (}uick Start to Vessel",
Revision 2, Test Implemented September 25, 1984.
6.
ST-19,2
"Core Performance (75%) Using Process Computer",
Revision 2, Test Implemented September 25, 1984.
7.
ST-19 '
"Core Performed (100%) Using Process Computer",
Revision 2, Test Implemented September 27, 1984.
8.
ST-21. 1
"Core Response to Control Rod Movement", Revision 2, Test Implemented September 25, 1984.
9.
"Core Response to Pressure Change",
Revision 3, Test Implemented September 25, 1984.
10.
ST-22. 1
"Pressure Regulator Control Valve Controlling", Revision 1, Test Implemented September 25, 1984.
11.
ST-22. 1
"Pressure Regulator Control Valve Controlling", Revision 1, Test Implemented September 29, 1984.
12.
"Pressure Regulator Control Valve and By-pass Valve Controlling", Revision 1, Test Implemented September 24, 1984.
13.
ST"22.2
"Pressure Regulator Control Valve and By-pass Valve Controlling", Revision 1, Test Implemented September 29, 1984.
14.
"Pressure Regulator By-pass Valve Controlling", Revision 1,
Test Implemented September 25, 1984.
15.
ST-23.2 16.
~
~
"Feedwater (A) Manual Flow Step Changes",
Revision 2, Test Implemented September 29, 1984.
"Feedwater (B) Manual Flow Step Changes",
Revision 2, Test Implemented September 29, 198 V
17.
ST"23.2 18.
ST-23.3 19.
ST-29.1 20.
ST-29.1 21.
ST-29. 1 22.
ST-29.1 23.
ST-32.2 24.
ST-33. 1 25.
ST-33.2 26.
ST-33.3 27.
ST-33.3 28'T-33.3 29.
ST-37. 1
"Feedwater (C) Manual Flow Step Changes",
Revision 2 Test Implemented September 19, 1984.
"Feedwater Level Setpoint Changes",
Revision 2 Test Implemented September 25, 1984.
"Recirc A Flow Steps in Local Manual", Revision 2 Test Implemented September 25, 1984.
"Recirc A Flow Steps in Local Manual", Revision 2 Test Implemented September 29, 1984.
"Recirc B Flow Steps in Local Manual", Revision 2 Test Implemented September 25, 1984.
"Recirc B Flow Steps in Local Manual", Revision 2, Test Implemented September 29, 1984.
"Containment Temperature at Steady State",
Revision 3, Test Implemented Date not recorded.
"Steady State Vibration Main Steam Piping Inside Drywell",
Revision 2, Test Implemented September 29, 1984.
"Steady State Vibration Main Steam and Feedwater Piping Outside Drywell", Revision 2, Test Implemented September 28, 1984.
"Steady State Vibration Recirc Piping", Revision 2, Test Implemented September 25, 1984.
"Steady State Vibration Recirc Piping", Revision 2, Test Implemented September 27, 1984.
"Steady State Vibration Recirc Piping", Revision 2, Test Implemented September 28, 1984.
"Gaseous Radwaste Effluent Verification", Revision 2, Test Implemented September 25, 1984.