IR 05000338/1979010
| ML19269D915 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/16/1979 |
| From: | Cantrell F, Dyer J, Webster E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19269D911 | List: |
| References | |
| 50-338-79-10, 50-339-79-15, NUDOCS 7906200318 | |
| Download: ML19269D915 (14) | |
Text
-
e UNITED STATES
- g* "009
- o NUCLEAR REGULATORY COMMISSION g
[
o REGION il O
$
101 MARlETTA STREET. N.W.
ATLANTA, GEORGIA 3o3o3
%,...../
Report Nos.: 50-338/79-10 and 50-339/79-15 Licensee: Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Units 1 and 2 Docket Nos.: 50-338 and 50-339 License Nos.: NPF-4 and CPPR-78 Inspection at North Anna Site near Mineral, Virginia Inspectors: [
2Acfm I~
3 !79 E. H. W bster L
Date Signed
,
ot%J a
r/shr J.'A. Dyer i
Date Signed Approved by:
/6
' '
F. S. Cantrell, Actinpection Chief, RONSB Bate $igned SUMMARY Inspection on March 5-9, 1979 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours on-site in the areas of operations review, IE Bulletin and Circular review and review of con-tainment purge controls for Unit 1; 42 inspector-hours on-site in the areas of preoperational test procedure review, preoperational test observation, review of IE Bulletins and Circulars, startup procedure verification and comparison of as built systems to FSAR for Unit 2.
Results In the seven areas inspected, no apparent items of noncompliance or deviations were identified.
2252 243 7906200R8,
t
.
DETAILS 1.
Persons Contacted License Employees
- W. R. Cartwright, Station Manager
- J. D. Kellams, Superintendent - Operations
- S. L. Harvey, Operating Supervisor
- D. L. Smith, Resident QC Engineer
- J. W. Martin, Supervisor, VEPC0 QA
- E. R. Smith, Superintendent - Technical Services
- D. G. McLain, Engineering Supervisor
- W. R. Madison, NRC Coordinator F. C. White, Acting Fire Marshall G. A. Kann, Engineer J. P. Smith, Associate Engineer J. B. Ferrer, Assistant Engineer P. A. Furman, Assistant Engineer T. J. Schreckenghost, Engineering Technician NRC Resident Inspector
- M. S. Kidd
- Attended Exit Interview 2.
Ex_it Interview The inspection scope and findings were summarized on March 9, 1979 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings
_
Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of Plant Operations - Unit 1 The inspector reviewed plant operations logs for the period February 15 through March 4,1979 conformance with requirements established in Technical Specifications, and Licensee Administrative Procedures.
The 2252 244
.
..
,
.
-
.
-2-inspector conducted a plant tour on March 7, 1979 to review administra-tive controls concerning equipment maintenance health physics, house-keeping, fire protection and staffing.
Operations Logs Reviewed:
a.
(1) Shif t Supervisor Log (1-log-1)
(2) Control Room Operating Log (1-log-2 and 1-log-4*)
(3) Jumper Log (4) Shift Order Book (5) Auxiliary Logs (1-log-6C*and 1-log-6D*)
(6) Deviation Report Index and Deviation Reports from February 15, 1979 to present.
(7) Calorimetric Calibration (1-PT-24*)
- Indicates log reviewed for March 6, 1979 only.
'
-
The inspector identified six minor log keeping errors which licensee personnel corrected before inspector departure. Log entries for nine events requiring review and potentially reportable to NRC as nonroutine events were tracked through the licensee's deviation report system and were found to have been properly handled.
b.
Plant Tour The inspector toured the Control Room and Auxiliary Building with attention given in the following areas:
(1) A sampling of monitoring instrumentation recording as required (2) Radiation controls properly established (3) Plant housekeeping - The inspector noted unmarked wood pieces in a secondary plant relay panel.
In discussing control of flammable materials with licensee management, the inspector was shown two QC inspection reports numbers 1R-N-79-336 dated Februa ry 22, 1979 and IR-N-79-305 dated February 16, 1979 which documented approximately twelve uses of wood in the operating plant, several of which may not have used fire retardant treated wood. Management committed to analyze and revise, as necessary, the flammable control program for wood to preclude recurrence of this problem. The inspector will review this area in future inapections (338/79-10-01).
(4) Fluid Leaks - The inspector noted a rather large steam leak from a feedwater flow sensor fitting designated 1-FW-57.
Licensee management was informed and had barriers erected to assure safe personnel access. Plans to replace the fitting were indicated for the upcoming maintenance outage.
2252 245
..
..
.
~
.
.
-3-(5) Existence of piping vibrations - none noted.
(6) Selected valve positions - as required.
(7) Selected caution tag information as required.
(8) Selected instrument calibrations at proper intervals - as required.
(9) Control room staffing - as required.
(10) Fire protection equipment operable - as required.
The inspector observed a shift turnover in the control room and had no further questions.
No items of noncompliance or deviations were identified.
6.
Review of Containment Purge Controls - Unit 1 The inspector verified licensee comments made in letter serial number 729/121178 dated January 17, 1979 concerning containment purge controls to the Office of Nuclear Reactor Regulation (ONRR), NRC. The letter was in response to an ONRR questionaire concerning the issues of 1) indis-criminate purging during power operation, 2) design controls of contain-ment purge valves to insure they close in the event of an accident and 3) design and administrative controls to assure safety circuits are not bypassed to conduct purging operativas. Since Technical Specification 3.6 requires the licensee to maintain sub-atmospheric pressure in
.ontainment during Mode 1, 2, 3, and 4 operations, administrative
controls in operating procedures ellow containment purging only in Modes 5 and 6.
The inspector then verified design controls to assure purge valve closure in the event of an accident and had no further questions in this area.
7.
IE Balletin 78-14 - Units 1 and 2 IEB 78-14 dated December 19, 1978 was addressed to all licensees for information, but required written response only from Boiling Water Reactor facilities. The inspector noted that IEB 78-14 had not been reviewed, distributed or evaluated for applicability, and, therefore shall review this area again in future inspections.
Due to lack of timely response and ineffective tracking system afforded this bulletin, the inspector shall review the licensee's tracking system in future inspections.
(338/79-10-02). This area.s discussed further in paragraph 8.
2252 246
.
....
-
.
-
.
-4-8.
IE Circulars and Notices - Units 1 and 2
.
a.
IE Circulars The inspector reviewed the following IE Circulars to insure that the licensee had received them, reviewed them for applicability and taken or planned corrective action, as necessary:
(1)
IEC 78-13 dated July 10, 1978 concerned operability of service water pumps. This matter was indicated as closed on the licensees tracking system, having been reviewed by the Station Nuclear Safety and Operating Committee (SNSOC) on July 17, 1978. Licensee management, at the inspector's request, produced a written analysis which indicated that the conditions discussed in the circular are not applicable to this site. The inspector had no further questions in this area.
(2) IEC 78-19, dated December 29, 1978 concerned manual bypass of safety actuation signals. The issue was reviewed as described in paragraph 6 above for Unit I and Unit 2 as well. The inspector had no further questions in this area.
(3)
IEC 79-02, dated January 16, 1979, was received, but not reviewed or distributed, and hence, remains open.
b.
IE Notices This relatively new communication medium is used by NRC to provide early information of possibly significant matters. The inspector reviewed the following Notices to insure licensee receipt, review, and action taken or planned, as necessary.
(1)
IEN 79-01 dated February 2,1979 (2)
IEN 79-03 dated February 9, 1979 (3)
IEN 79-04 dated February 16, 1979 All three notices had been received, but not routed or reviewed.
Licensee management committed to incorporate IEN in the licensee committment tracking system and treat them as IE Circulars have in the past. The inspector will review this area in future inspec-tions as noted in paragraph 7.
above.
9.
Review of Preoperational Test Procedures Preoperational tests were reviewed for conformance to FSAR Sections 3A.9, 3A.79, 6.2.2, 6.3.4.2, 7.2, 7.3 and 8.31; FSAR Supplement Sections 6, 7 and 8; FSAR Table 14.1-1; and proposed Technical Specifications 3/4.3.1 and 3/4.3.2.
2252 247
.
- 9
.
-
.
-5-No discrepancies were noted during review of the following a.
procedures:
(1) 2-P0-61: Feedwater Isolation. Approved June 21, 1978 (2) 2-P0-62: Engineered Safety Features and Feedwater Isolation Logic Test. Approved Juny 5, 1978 (3) 2-P0-63: Engineered Safety Features Functional Test -
Containment Depressurization Actuation.
Approved August 9, 1978 (4) 2-P0-64: Reactor Protection System Logic Test. Approved May 12, 1978 (5) 2-PO-65.1: Reactor Protection and Engineered Safety Features Response Time Testing - Sensors. Approved May 10, 1978 (6) 2-P0-65.2: Reactor Protection and Engineered Safety Features Response Time Testing-Circurity. Approved June 22, 1978 (7) 2-P0-65.3: Engineered Safety Features Equipment and Contain-ment Isolation Valve Response Times.
Approved July 17, 1978 (8) 2-PO-65.4: Reactor Protection and Engineered Safety Features Response Time Testing - Slave Relays. Approved May 26, 1978 (9) 2-PO-65.5: Reactor Protection Response Time Testing - UV Coil, Breaker and Gripper Coil. Approved May 22, 1978 (10) 2-P0-65.6: Reactor Protection and Engineered Safety Features -
Total Response Times. Approved June 21, 1978 (11) 2-P0-73: Reactor Protection System Loss of Power Fail Safe Test. Approved July 17, 1978 (12) 2-P0-78: Rod Control System Inhibit Functions Test.
Appro ed December 18, 1978
/j
,
b.
Discrepancies were noted during review of the following procedures which were resolved, or will require resolution prior to implementation of the' procedures.
I 2252 248
-
.
-
,
.
-6-(1) 2-PO-30.4: Fuel Transfer System Manipulator Crane. Approved April 21, 1978. The procedure as presently written does not verify the manual operating features of the manipulator crane.
(339/79-15-01)
(2) P0-36.3: Safety Injection System Functional Test Pump Performance Verification. Approved December 26, 1978. The inspector noted that testing did not call for a drawdown verification on the refueling water chemical addition tank. A procedure deviation was processed to include a drawdown of the spray additive tank.
Portions of P0-36.3 were witnessed in conjunction with the resident inspector.
(3) 2-P0-38.3: Casing Cooling System. Approved February 21, 1978 The valve lineup does not establish a flow path prior to commencing the test.
(339/79-15-02)
(4) 2-P0-70: Emergency Diesel Load Test During Simulataneous Safety Injection and Loss of Normal Emergency Power. Approved February 21, 1979. The procedure does not call for attachments 6.3 H and 6.3 J (verification that non-essential trips are bypassed) to be performed.
(339/79-15-03)
No items of noncomplainee or deviations were identified.
10.
Preoperational Test Procedure Verification The following procedures were reviewed to verify that management approval was in accordance with the " Nuclear Power Station Quality Assurance Manual" Section 5 and that the test objectives were consistent with the test title:
Test Description Approval Date (a) 2-PO-1 Emergency Power System 11-27-78 (b)
2-P0-2.2 Fire Protection System - Hose Racks 03-30-78 (c)
2-PO-3.2 Fire Protection System - Low 03-30-78 Pressure Carbon Dioxide (d)
2-P0-3.3 Fire Protection System - Smoke 03-30-78 Detectors 2252 249
.
. -...
.-
-
.
.
-7-(e)
2-P0-3.4 Fire Protection - Reactor Coolant 03-30-78 Pump Radiant Heat Detectors (f) 2-PO-4 Fire Protection System - Halon 1301 04-21-78 (g) 2-PO-6 Service Water System 09-18-78 (b) 2-P0-7 Instrument Air Subsystes Bottles 05-12-78 (i) 2-PO-8 Communications Systems 07-17-78 (j)
2-P0-11.1 Compcaent Cooling System Test 03-30-78 at Ambient Plant Conditions (k)
2-P0-11.4 Component Cooling System Test 04-21-78 at Hot Plant Conditions (1) 2-P0-12 Neutron Shield Tank Cooling System 03-30-78 (m) 2-P0-17 Containment Ventilation System 04-21-78 (n) 2-P0-18 Heating and Ventilation Systems Test 04-21-78 (o) 2-P0-19 Hydrogen Removal System Test 12-06-78 (p) 2-P0-21 Control Rod Drive Mechanism 06-13-78 Cooling System (q) 2-PO-29 Reactor Coolant and Associated 12-12-78 Systems Piping Vibrational Test (r) 2-PO-30.3 Fuel Transfer System Transfer 03-30-78 Canal (s) 2-P0-30.4 Fuel Transfer System Manipulator 04-21-78 Crane (t) 2-PO-31.2 Fuel Handling Tools and Fixtures 06-20-78 in the Containment (u) 2-PO-33 Chemical and Volume Control System 09-18-78 Test During Hot Functionals (v) 2-P0-34 Boric Acid Tranisfer System 06-27-78 (w) 2-PO-36.1 Safety Injection System 06-22-78 Functional Test Breakers and Valves 2252 250
._.
.
_g.
(x) 2-PO-36.2 Safety Injection System Functional 05-31-78 Test Passive System (Accumlators)
(y) 2-P0-36.3 Safety Injection System Functional 12-26-78 Test Pump Performance Verification (z) 2-P0-36.4 Safety Injection System Hot 07-07-78 Functional Test (aa) 2-P0-37.1 Quench Spray System Pump Performance 03-30-78 Testing (bb) 2-P0-37.2 Quench Spray Systems Spray Nozzles 03-30-78 Testing (cc) 2-P0-38.1 Recirculation Spray System Pump 06-21-78
'
'
Performance Testing (dd) 2-P0-38.2 Recirculation Spray System Spray 03-30-78 Nozzles Testing (ee) 2-P0-38.3 Casing Cooling System 02-21-79 (ff) 2-PO-39.1 Residual Heat Removal System 05-12-78 Testing at Cold Conditions (gg) 2-P0-39.2 Residual Heat Removal System 05-13-78 Heat Removal Capability Test (hh) 2-P0-39.3 Residual Heat Removal System - Valve 04-19-78 Interlocks Test (ii) 2-P0-40 Hydrostatic Test of Reactor Coolant 09-11-78 System and Associated High Pressure Auxiliary Systems (jj) 2-P0-44 Reactor Internals Inspection 03-30-78 (kk) 2-P0-45 RCS - Heatup for Hot Functionals 12-18-78 (11) 2-P0-46 RCS - At Temperature for Hot 01-9-79 Functionals (mm) 2-PO-47 RCS - Cooldown from Hot Functionals 12-06-78 (nn) 2-PO-48.1 Reactor Coolant and Associated 12-12-78 Systems Thermal Expansion and Restraint Test 2252 251
-
,
.........
..
.
.
_g_
(oo) 2-PO-48.3 Pipe Rupture Restraint Hot Gap 12-12-78 Measurement (pp) 2-P0-48.4 Bumper Gap Measurements Hot, Cold 12-12-78 and Crossover Legs (qq) 2-P0-51 Pressurizer Code Safety Valve Setpoint 05-22-78 Verification (rr) 2-PO-52.1 Pressurizer Relief Tank Test 05-12-78 at Cold Conditions (ss) 2-P0-52.2 Pressurizer Relief Tank Test 09-18-78 During Hot Functionals (tt) 2-P0-54 Turbine Runback Control System 12-06-78 (uu) 2-P0-55 Initial Turbine Roll During Hot 01-08-79 Functionals (vv) 2-P0-56 Main Steam Decay Heat Release 04-19-78 and Atmospheric Steam Dump Valves (ww) 2-P0-57 Main Steam Safety Valve Setpoint 04-19-78 Verification (xx) 2-P0-58.1 Main Steam Line Trip Valves 04-19-78 Test at Cold Plant Conditions (yy) 2-PO-58.2 Main Steam Line Trip Valves 09-18-78 Test at Hot Plant Conditions (zz) 2-P0-59 Condenser Steam Dump Control 01-08-79 (aaa) 2-PO-63 Engineered Safety Features Functional 08-09-78 Test-containment Depressurization Actuation (bbb) 2-P0-64 Reactor Protection System Logic Test 05-12-78 (ccc) 2-PO-65.5 Reactor Protection Response Time 05-22-78 Testing - UV Coil, Breaker and Gripper Coil (ddd) 2-P0-66 D. C. Power System Test 05-15-78 (eee) 2-PO-67 125 VDC Power Supply Independence 05-31-78 Test 2252 252
.
.-
.
.. -
-
.
.
-10-(fff) 2-PO-68 120 V AC Vital Bus Test 09-18-78 (ggg) 2-PO-69 Station Blackout Test at Shutdown 12-18-78 Conditions (hhh) 2-PO-70 Emergency Diesel Load Test During 02-21-79 Simultaneous Safety Injection and Loss of Normal Emergency Power (iii) 2-P0-74 Containment Structural Acceptance 12-19-78 Test (jjj) 2-P0-78 Rod Control System Inhibit 12-18-78 Functions Test No items of noncompliance or deviations were identified.
11.
St.artup Procedure Verification The following procedures were reviewed to verify that management approval was in accordance with the " Nuclear Power Station Quality Assurance Manual" Section 5 and that the test objectives were consistant with the test title:
Test Description Approval Date (a) SU-6 Initial Core Loading 12-04-78 (b) SU-7 Incore Moveable Detectors 12-12-78 (c) SU-8 Containment Shielding and Radiation 12-18-78 Survey (d) SU-11 Rod Drop Time Measurement 12-04-78 (e) SU-13 Rod Position Indication 12-04-78 (f) SU-14 Pressurizer Spray and Heater Capability 12-12-78 and Setting Continuous Spray Flow (g) SU-16 Reactor Coolant System Flow Coastdown 12-04-78 Measurement (b) SU-17 Initial Criticality 01-08-79 (i) SU-18 Nuclear Design Check Test 01-08-79 2252 253
-
,
.
-11-(j) SU-19 Rod and Boron Worth Measurements 12-04-78 during Boron Dilution (k) SU-20 Rod and Boron Worth Measurements 12-04-78 during Boron Addition (1) SU-21 RCC Assembly Pseudo Ejection Test 12-12-78 (m) SU-24 Automatic Reactor Control 12-18-78 (n) SU-27 Power Coefficient and Integral Power 12-18-78 Defect Measurements (0) SU-29 Static RCCA Rod Drop and RCCA Below 01-02-79 Bank Position (p) SU-30 Incore - Excore Detector Calibration 01-08-79 (q) SU-31 Nuclear and Temperature Instrumentation 01-08-79 Calibration and Thermal Power Measurements (r) SU-32 Chemical Analysis of the Reactor 09-02-79 Coolant System (s) EU-35 Rod Group Drop and Plant Trip 01-08-79 (t) SU-36 Unit Shutdown From Outside The 01-02-79 Control Room (u) SU-37 Unit Trip from 100 Percent Power 01-08-79 (v) SU-38 Station Blackout Test 01-08-79 (w) SU-41 Process Computer 01-08-79 No items of noncompliance or deviations were identified.
12. Fuel Receipt and Storage The inspector witnessed the receipt of tw fuel elements to verify conformance to the Special Nucle.
3 rials (SNM) license application and Operating Procedure 4.2 (!..* Fuel Handling).
The inspector verified such' /tems as:
\\<
(a) Area and personnel mon'itoring Al 2252 254 i
.
.
.
.
-12-(b) Fire protection equipment availability (c) Cleanliness controls (d) Health Physics coverage (e) Retention of shipping, QA/QC, and inspections records (f) Fuel inspection No items of noncompliance or deviations were identified.
13.
Comparison of As-Bailt to FSAR: Attxiliary Feedwater System - Unit 2 The inspector walked-down the Auxiliary feedwater system and compared the as-built system to Stone and Webster drawing number 12050-FM-74A-10 and subsequently to the Final Safety Analysis Report (FSAR) figure 10.4.3-4, " Feed Water System" dated November 3, 1978. Two deficiencies were noted and subsequent to the inspection reported to licensee manage-ment.
(a) The FSAR figure 10.4.3-4 shows the discharge from pump 1-FW-P-2 branching to a discharge line to A steam generator before splitting to feed the two common discharge leaders capable of supplying all three steam generators. The as-built system conforms to drawing 12050-FM-74A-10 which shows the separate A steam generator line tapping off after the split in the pump discharge line to feed the common discharge leaders. Licensee management committed to analyze and correct this disparity. The inspector will review this area in future inspections (339/79-15-04).
(b) Neither the FSAR figure nor the referenced drawing show a drain valve (2-FW-189) coming off the bypass line to the recirculation filter (2-FW-FL-1), which exists on the system. As above, licensee management committed to review and correct this item and it will be followed up in future inspections (339/79-17-05).
No items of noncompliance or deviations were identified.
14.
Previous Inspector Identified Areas of Concern on Unit No. 2 (a)
78-29-01 (Closed) Test of diesel lube oil system at fuit load.
(b)
78-29-02 (Closed) Test of diesel cooling system at full load.
(c)
78-29-04 (Closed) Flow path verification from all fuel oil sources to the diesels.
2252 255
,.
a
.
-13-The inspector reviewed the test results of 2-P0-1 (Emergency Power System) and the fuel oil system valve lineup to verify that the lube oil and cooling systems were tested and that flow paths from all fuel oil sources were established.
(d) 78-29-07 (Closed) Operability of check valves 92, 100, 106, 113, 118, and 125. 2-PO-36.4 (Safety Injection System Hot Functional Test) required that stable flow be established to insure that the check valves were operable.
(e) 78-29-08 (Closed) Safety inspection and accumulator lines require filling and venting prior to test (2-PO-36.4). This was performed as part of the instrument departments verification that the flow instruments on each line were filled and vented prior to commencing the test.
(f) 78-29-09 (Closed) Throttle safety injection flow path to prevent robbing charging and seal line flows.
Operators were cautioned prior to test performance. No problems were encountered.
15.
Previous Inspector Identified Areas of Concern on Unit 1 (a) 78-32-03 (Closed) Licensee revision to electrical and mechanical maintenance procedure for valves to include TS Table 6.3-1 stroking requirements. The licensee revised procedures MMP-C-GV-1, EMP.C-LS-1, EMP-C-MOV-1, and EMP-C-SOV-2 on January 2, 1979 to include require-ments for valve stroking as required by TS.
The inspector had no further questions.
(b) 78-25-04 (Closed) Inclusion of mobile fire extinguishers in periodic test procedures for routine inspections. The licensee revised Procedure PT-105.2.2 on February 24, 1979 to include mobile fire extinguishers. The inspector had no further questions.
2252 256
.
...
e.#