ML20028D046
| ML20028D046 | |
| Person / Time | |
|---|---|
| Issue date: | 10/22/1982 |
| From: | Chamberlain D, Hale C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028D038 | List: |
| References | |
| REF-QA-99900509 NUDOCS 8301140436 | |
| Download: ML20028D046 (50) | |
Text
1 ORGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION BOSTON, MASSACHUSETTS l
REPORT INSPECTION 8/16-20/82 &
INSPECTION NO.:
99900509/82-02 DATE(S) 8/30-9/3/82 ON-SITE HOURS:
116 CORRESPONDENCE ADDRESS: Stone and Webster Engineering Corporation ATTN: Mr. R. B. Kelly Vice President, Quality Assurance P. O. Box 2325 Boston, MA 02107 ORGANIZATIONAL CONTACT: Mr. F. B. Baldwin, Assistant QA Manager TELEPHONE NUMBER:
(617) 589-6566 PRINCIPAL PRODUCT: Architect Engineering Services NUCLEAR INDUSTRY ACTIVITY: Major active projects include Beaver Valley 2, River Bend 1, Shoreham, Nine Mile Point 2, Millstone 3, and North Anna 3.
In addition, there are 50 modification / repair / service contracts.
The aforementioned contracts cover work performed in the Boston, Cherry Hill, New York, and Denver offices.
ASSIGNED INSPECTOR:
$1 D. D.Nrlain, Reactor Systems Section Dats 1
(RSS)
OTHER INSPECTORS:
A. L. Smith, Equipment Qualification Section P. H Harrell RSS APPROVED BY:
o IO/2da.
C. J. g, ChieT,7SS Da'te INSPECTION BASES AND SCOPE:
)
A.
BASES: Stone and Webster (SW) Topical Report SWSQAP 1-74A and 10 CFR Part 50, Appendix B.
B.
SCOPE: Status of previous inspection findings (Boston and Cherry Hill offices), training (Boston office), audits (. Cherry Hill office), and j
l the following items:
(1) 10 CFR Part 50.55(e) Report (North Anna 3) - Pressurizer safety valve inlet piping design with large pressure drop could lead to valve chatter; (2)_ Region I Request (Beaver Valley 1) -
cont. next oaoe PLANT SITE APPLICABILITY: Docket Numbers 50-309, 50-334, 50-404, 50-410, 50-458, 50-280/281, and 50-338/339.
ON b() a]L}
l wwWC 8301140436 821118 77 PDR GA999 EECSW
- certifi, 99900509 PDR
ORGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION BOSTON, MASSACHUSETTS i
REPORT INSPECTION N0.: 99900509/82-02 RESULTS:
PAGE 2 of 7 B.
SCOPE: continued Errors in seismic calculations performed by S&W for 79-14 Bulletin activities; (3) 10 CFR Part 21 Report (Maine Yankee) - Potential failure of safety injection actuation system to operate due to single relay failure; (4) Region I Request (Nino Mile Point 2) - S&W design for cable tray sup-port locations failed to meet technical standard requirements; ud (5) 10 CFR Part 50.55(e) Report (River Bend 1) - Failure by S&W to provide class 1E switchgear redundancy in recirculation pump circuitry for containment penetration protection.
A.
VIOLATIONS:
None B.
NONCONFORMANCES:
Contrary to Criterion V of 10 CFR Part 50, Appendix B and Sections 8.2 and 8.3 of NUPIPE Stress Analysis and Supports Evaluation Procedure, activities affecting quality (preparation and control of pipe stress analysis and support calculation packages for Beaver Valley 1) were not accomplished in accordance with the prescribed procedure.
C UNRESOLVED ITEMS:
None D.
STATUS OF PREVIOUS INSPECTION FINDINGS:
1.
(Closed) Nonconformance (81-04):
Experience Records were not being updated on a yearly basis as required.
The Engineering Assurance Division conducted a series of reviews to verify that Stone and Webster (S&W) requirements for Experience Records have been met. The NRC inspector examined 12 randomly selected Experience Records and all of them were current.
2.
(Closed)Nonconformance(82-01):
Failure to meet a comitment to the NRC relative to the updating of Experience Records.
S&W commitments are tracked by an Action Log to assure that commitments are met.
The four outstanding NRC findings were listed on the current Action Log.
3.
(Closed) Nonconformance (82-01): An assumption made in calculation No. 12179-US (B)-221 was not confirmed and the assumption was not identified for later confirmation.
l
ORGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION BOSTON, NASSACHUSETTS 4
REPORT INSPECTION NO - 99900509/82-02 RESULTS:
PAGE 3 of 7 Problem Report (PR-NT-2) was issued to delineate the review required during analysis to verify the integrity of boundaries between areas isolated from the effects of High Energy Line Breaks (HELB) and adjacent areas subject to HELB effects. All S&W nuclear projects have i
responded to the Problem Report with either an interim or final response.
The NRC inspector will conduct a followup inspection of this area pending the S&W Engineering Assurance acceptance of all project responses. Also, NRC Region II will be notified of action taken by S&W for Surry 1 and 2 and North Anna 1 and 2 (S&W notified licensee of potential problem and offered to pursue matter further, if requested) for possible regional followup action with the licensee.
4.
(Closed) Nonconformance (82-01): HVAC Calculation PB-196 for control building cooling load contained input infonnation that was not con-firmed and "yes" was not checked to indicate confirmation was required at a later date.
The condition identified by the NRC inspector was also identified during an S&W internal audit. The closecut of the internal audit finding was reviewed and the closecut was satisfactory.
For preven-tive action, a memorandum was issued by the River Bend Project on May 17, 1982, imposing additional control requirements on preparers of power calculations and restating reviewer responsibilities.
E.
OTHER FINDNGS OR COMMENTS 1.
Potential CDR Pressurizer Safety Valve Problem at North Anna, Unit 3 (Followup on item in 82-01 report) - This item, which was a result of a 10 CFR Part 50.55(e) report submitted to Region II by Virginia Electric and Power Company (VEPC0), was initially examined during the 82-01 NRC inspection; however, it remained open since (a) the final Electric Power Research Institutes (EPRI) report had not been issued; and (b) a decision concerning increasing the height of the pressurizer at North Anna 3 (thus requiring a redesign of the inlet piping configuration) was pending.
During this inspection, it was determined that the pressurizer height will be increased by 10 feet, thus requiring a redesign of the inlet piping configuration.
VEPC0 has also directed S&W to incorporate additional block valves and power-operated relief valves in the pressurizer pressure relief design, as well as designating the specific make of valves to be I
used. S&W expects to complete the new valve and piping arrangement / design by the end of this year; however, the final stress analysis will not be completed until late next year.
l
\\
ORGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION BOSTON, MASSACHUSETTS REPORT INSPECTION NO.: 99900509/82-02 RESULTS:
PAGE 4 of 7 Based on the above information (a new design different from that which the 50.55(e) report concerned), this item is being closed.
The new design effort will be monitored and reviewed during future NRC inspections.
2.
Errors in Seismic Calculations Performed by S&W for 79-14 Bulletin Activities (Boston office) - This area of inspection resulted from a Region I request relative to licensee reported errors in seismic calculations performed by S&W on the Beaver Valley, Unit 1 project.
The licensee reported to Region I on August 14, 1981, that all IEB 79-14 reanalyses were satisfactorily completed.
S&W was respon-sible for a major portion of this effort and they had waived certain administrative requirements in order to complete the technical reanalyses requirements by August 14, 1981.
When the NRC was notified that IEB 79-14 work was completed, it was believed that the technical portion of the work was complete. A total of 22 nonconformances had been identified and resolved by S&W based on the 79-14 as-built review.
The NRC inspector was not able to examine the completed calculation packages for work performed prior to August 14, 1981, because S&W did not maintain the completed packages as permanent plant records. A nonconformance (see B. above) was issued for failure to prepare and control pipe stress analysis and support calculation packages in accordance with the NUPIPE Stress Analysis and Supports Evaluation Procedure as indicated by the following:
a.
Completed packages for work completed prior to August 14, 1981, did not become a permanent part of plant records, b.
No completed Form Z documents were available for NRC inspector review.
c.
The Engineering Assurance (EA) " Action Items Tracking Log - EA Audits Projects" listed 17 documents identifying unsatisfactory conditions or questions from EA audits of Beaver Valley 1 stress calculation packages as still partially unresolved as of August 19, 1982.
Subsequent to August 1981, it was decided (S&W and licensee) to incorporate various calculations that had been done and do a reverification of the calculations and to get the calculation packages in the required administrative format.
During this review, six additional nonconformances were identified (all of these have been reported to Region I by the licensee -
LER's82-007, 008, 011, 012, and 014). The NRC inspector examined samples of the completed packages from this verifi-cation effort and no additional problems were identified.
DRGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION l
BOSTON, MASSACHUSETTS i
REPORT INSPECIlON NO.:
99900509/82-02 RESULTS:
PAGE 5 of 7 S&W issued a letter to the licensee on May 26, 1982, which stated in part, "... The Stone & Webster effort associated with the response to IE Bulletin 79-14 has been completed.
QA Category I calculations have been completed which meet all of the requirements of our Engineering Assurance Procedure EAP 5.3...." However, certain EA audit items were still open as of August 19, 1982. The failure to close out the EA audit items was cited as part of the nonconform-ance identified in B above. NRC Region IV will follow up on the S&W corrective actions relative to the nonconformance identified during the next inspection at S&W-Boston.
3.
Potential Failure of Safety Injection Actuation System to Operate Due to a Single Relay Failure (Boston office) - This area of inspection resulted from a 10 CFR Part 21 report issued by S&W stating that a single relay failure or loss of relay circuit power would prevent the automatic actuation of safety injection on the Maine Yankee plant. A single relay provides the safety injection actuation signal due to low pressurizer pressure. This relay is controlled by a two-out-of-four logic composed of four independent pressurizer pressure signals.
Failure of this single relay or loss of power to the relay circuit will prevent automatic actuation of safety injection for those accidents resulting in loss-of-reactor coolant-system-pressure but not high containment pressure.
Apparently, the licensee notified the NRC of this condition in February 1982, and the NRC in turn contacted S&W by phone due to concern that this could be a generic problem. S&W initiated a 10 CFR Part 21 review and a Part 21 report was issued on May 7, 1982. The S&W review of this problem revealed that Maine Yankee was the only project with this design contained in the S&W scope of supply. S&W notified the Maine Yankee licensee of the defect and offered their assistance in resolving the problem. The licensee has not requested any assistance from S&W.
The S&W design error was apparently made in the 1969 to 1970 time-frame and no other errors of this type were found. This item will be closed based on the actions taken by S&W and on the 10 CFR Part 21 notification.
4.
S&W Design for Cable Tray Support Locations Failed to Meet Technical Standard Requirements (Cherry Hill office) - This area of inspection resulted from a Region I request for followup on a problem identified on the Nine Mile Point Unit 2 (NMP2) project relative to the S&W design for cable tray supports.
S&W cable tray support location drawings were issued and certain support locations did not meet Technical Standard ETS-AE11-1-1 requirements. The specific requirement violated was the installation of a support within one foot of the cable tray end. Apparently, S&W engineers were aware of L -
t)RGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION BOSTON, MASSACHUSETTS REPORT INSPECTION N0.: 99900509/82-02 RESULTS:
PAGE 6 of 7 the deficiencies and were planning to do additional analyses at a later date to qualify the supports as installed.
However, they were not formally tracking the deficiencies and no hold was placed on construction or installation.
S&W has reviewed all NMP2 cable tray supports which exceed the one-foot overhang criteria.
Design changes have been issued to place the supports on hold for final Field Quality Control signoff. Also, the NMP2 electrical division has committed to conduct a division level seminar by October 15, 1982, to give personnel instructions on use of the hold system.
Completion of this training will be verified during the next NRC inspection. The NRC inspecter reviewed the use of the hold system on NMP2 and River Bend 1 and concluded that the system in place provides a method for handling issues such as the cable tray support location problem.
The instructions to be provided on use of the hold system should help preclude problems of this type in the future.
During the NRC inspector review of this area, the use of drawing check sheets was reviewed. All divisions appear to have drawing check sheets as required, but each project / division appears to be issuing their own version of a check sheet.
An Engineering Department Technical Procedure (EDTP 3.3-0) was issued on May 7,1982, which states that Boston will provide drawing check sheets for all divisions. A followup inspection will be conducted at S&W-Boston regarding the implementation of procedure EDTP 3.3-0.
The specific Region I concern is considered closed with only the followup areas identified to be completed during a future inspection at S&W.
5.
Design Failure of S&W to Provide Class 1E Switchgear Redundancy in Recirculation Pump Circuitry (Cherry Hill office) - This area of inspection resulted from a 10 CFR Part 50.55(e) report from the River Bend Unit I licensee regarding the design failure of S&W to provide class 1E switchgear redundancy in recirculation pump circuitry for containment penetration protection. This problem was identified by a S&W responsible engineer during a review of one-line drawings for Regulatory Guide requirements.
Regulatory Guide 1.63, Revision 2, requires that the circuit overload protection system for containment electrical penetrations confonn to the criteria of IEEE Stand-ard 279-1971, Criteria for Protection Systems for Nuclear Power Generating Stations. The 4.16 KV switchgear for the reactor recircu-lation pump motors did not meet the single-failure, IEEE 279 criteria in that two redundant Class 1E circuit breakers were provided with only one set of sensing current transformers and associated relays used to trip both redundant breakers.
S&W has modified the River Bend design to provide for the addition of redundant overcurrent protection equipment for the 4.16 KV switchgear.
S&W has also revised
0RGANIZATION: STONE AND WEBSTER ENGINEERING CORPORATION BOSTON, MASSACHUSETTS REPORT INSPECTION NO.: 99900509/82-02 RESULTS:
DAGF 7 nf 7 the 480 V MCC specification for River Bend to require class IE certification for all Motor Control Centers that feed 480 V electrical
' equipment through containment penetrations. S&W has not completed their generic review of this problem, but the preliminary indication is that this is a plant specific problem.
This item will remain open pending S&W completion of the following:
a.
Complete the generic evaluation of the problem, b.
Address the NRC inspector question regarding the capability to test operability of sensors (current transformers) during reactor operation as required by paragraph 4.9 of IEEE 279.
6.
Training - S&W Quality Standard 2.12, " Qualification, Certification, Indoctrination and Continuing Education of Personnel," and eight associated S&W procedures were reviewed and evaluated to determine:
(a) compliance with applicable code / regulatory requirements; and (b) total quality assurance program comitments.
The training records of 36 employees and 11 S&W Construction Training Audit Reports were reviewed to verify implementation of the S&W program commitments. Within the scope of this inspection, the NRC inspector found no items of nonconformance.
7.
Audits - Topical Report SWSQAP 1-74A and applicable S&W procedures were examined to determine quality assurance program commitments.
To verify implementation of these commitments, the following EA documents were examined: 32 audit plans, 25 audit observations,
4 audit reports,13 requests for extension, 25 audit observation replies, 4 audit schedules, 4 overall audit plans, and 2 audit i
trend analyses.
Relative to the documents examined, the inspector i
found that the commmitted program is being implemented.
Inspector D. &MRtABERLAIM Scope / Module 5 TAT 05 of PREVloVS DOCUMENTS EXAMINED INSffCTIoM FlNO)NGS i
1 2
TITLE / SUBJECT 3
4 1
7 Gss - 3449 LETT6R FRorn Gf. - sob %c7 9LANT 5 /2 6/82 RL00\\REMENTS 2
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4 1HTtRHAL rA6tno.
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1.
Drawing 5.
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Sequential Item Number 2.
Specification 5
Internal Memo 2.
Type of Document 3.
Procedure 7.
Letter 3.
Date of Document 4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revisfor (If applicable)
Insp::ctor D. CHAM 8ERLAIN
$$* N lfs Scope / Module ACTION IT6r/l DOCUMENTS EXAMINED CABLE TRAY SUPPORTS 1
2 TITLE / SUBJECT 3
4 1
EL DcR 901316 HOLD CH CABL6 TRhY S0PPORTS 880/8'2.
2 TECMHIcAL STANDAR0 ETS-Afil-1-l SEISrnIt CAP >LE V25hl TRAY SOPPORTS NOTES 3
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Inspector D,
CHArA6ERl AIN Docket No.19900M
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R:: port No. 32-02 Scope / Module ACTION 176tA Page 2 of 4
DOCUMENTS EXAMINED CA8LE TRAT 50PPoRT,5 1
2 TITLE / SUBJECT 3
4 9
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- 4.. Revision (Ifapplicable$
Insp:ctor D, CH4M8ERLAIN Scope / Module ACTION IT6r/l DOCUMENTS EXAMINED CA6LE TRRY SUPPORTS 1
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et Insp:ctor D. Ct{hrd86RLAIN p
Scope / Module ACTIcN IT6rd DOCUMENTS EXA. MINED C ABLE TR61 5000R75 1
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Inspector D. CHA M bbNlblN Report No.
82-02 Pcge_$_cf 6
Scope / Modulo, ACTl0N
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1.
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Date of Document 4.
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Revision (If applicable)
D.
6HhM86RLAIN No.999doSM Insp:ctor Report No. 41.gz Scope / Module SCTldN 1T6ff)
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Inspector D.
GHAM86RLAIW aYp$N Yo~Dn scope / Module STATUS Of PRHlot)5 DOCUMENTS EXAMINED lHSPEC,7104 flN014GS 1
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4 1
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