IR 05000454/1980013
| ML19332A388 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 08/14/1980 |
| From: | Clint Jones, Konklin J, Naidu K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19332A387 | List: |
| References | |
| 50-454-80-13, 50-455-80-12, 50-456-80-07, 50-456-80-7, 50-457-80-07, 50-457-80-7, NUDOCS 8009110675 | |
| Download: ML19332A388 (9) | |
Text
._
_
_
i CJ
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
'
Report Nos. 50-454/80-13; 50-455/80-12;
50-456/80-07; 50-457/80-07 Docket Nos. 50-454; 50-455 License No. CPPR-130; CPPR-131 50-456; 50-457 CPPR-132; CPPR-133 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name: Byron Nuclear Generating Station, Units 1 and 2 Braidwood Nuclear Generating Station, Units 1 and 2 Inspection At: CECO Corporate Offices, Chicago, IL Inspection Condutved: July 22, 24-25, 1980 9/N///
Inspectors:
E. R. Schweibinz " -
(July 22 and
, 1980) g
/
/
hw C. E.
ones 7-/.3 - Fo (July 22 and 24, 1980)
/
' /'
J. E. Konklin
/'
///J/fd.
(July 22 an
, 1980)
'
/
K. R. Naidu (44'
(July 25, 1980)
Accompanying Personnel:
J. H. Neisler (July 24, 1980 C. C. Williams h e. g (July 24, 1980)L Approved By: C. C. Williams, Chief 8 /f
'
'
Projects Section 2 scoenog p
-
.
Inspection Summary Inspection on July 22, 24-25, 1980 (Report No. 50-454/80-13; 50-455/80-12; 50-456/80-07; 50-457/80-07)
Areas Inspected: Licensee actions relative to the control of IE Bulletins and IE Circulars and a management meeting. This inspection involved a total of 43 inspector-hours at the CECO Corporate Office by six NRC inspdctors.
Resul,ts: No items of noncompliance or deviations were identified.
i i
l l
l l
l
.
S-2-
.
...
,,.
-., -.,...
.,
.-.
.
-
.
.
/
DETAILS 1.
Management Meeting Attendees (July 24, 1980) CECO C. Reed, Vice President, Nuclear Operations A. Kleinrath, Manager, Station Construction
-
,
NRC C. C. Williams, Chief, Projects Section 2 J. E. Konklin, Project Inspector, Byron J. H. Neisler, Project Inspector, LaSalle E. R. Schweibinz, Project Inspector, Braidwood 2.
Management Meeting This meeting was conducted to elicit a commitment from Commonwealth Edison to perform an in-depth examination and evaluation of their design / engineering organizations and function, and to provide a comprehensive evaluation of the conditions and circumstances which have led to certain areas of significant construction re-work at Byron and in part, at the Braidwood and LaSalle power plants.
These discussions concluded with a commitment by Mr. C. Reed to perform and report such an evaluation, which is to be completed within the next two to three months. The initiating plans and considerations regarding this commitment are to be delineated in a CECO letter to NRC RIII within the next several weeks.
(
3.
Persons Contacted During Inspection l
Principal Licensee Employees
+*E. Martin, QA Coordinator, SNED i
l G. Marcus, Director, Construction QA
- L. Holden, Mechanical Engineer, SNED
'
i
- R. Janecek, Nuclear Licensing Administrator
+W. Naughton, Nuclear Licensing Administrator The inspectors also contacted other licensee personnel, including QA and engineering staff members.
- Denotes those attending the exit meeting on July 24, 1980.
+ Denotes those attending the exit meeting on July 25, 1980.
4.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (IE Inspection Reports No. 454/79-15-01; No. 455/79-15-01; No. 456/79-13-01; No. 457/79-13-01). Lack of j
procedures for the control of IE Bulletins and IE Circulars.
.
-3-
l-
-
- _ w --- - ~.
.
..,,
.
_ _ _
.
The inspectors reviewed the corrective actions described in the
CECO letter dated November 28, 1979, including Station Nuclear Engineering Department (SNED) Procedure Q.39 Revision 0, issued January 9,1980 and Revision 1 issued March 31, 1980. The purpose of SNED Procedure Q.39 is "to establish the method for control of and response to the Nuclear Regulatory Commission's IE Bulletins,
,
Circulars, and Information Notices." All items reviewed were found
'
to be acceptable. This item is closed.
(Closed) Follow-up item (licensee evaluation of IE Circular 78-16).
The licensee requested Sargent and Lundy (S&L) to evaluate all Limitorque valve actuators covered by IE Circular 78-16.
The original evaluation add-2 sed only " motor operators on valves whose service called for throttling which must be done manually if the motor is wired for simple open-close operation." The inspector reviewed S&L reponse dated December 7, 1979 which determined that no safety-related valves of this description are being or will be used for the Byron and Braidwood plants. This item is closed.
5.
Functicnal or Program Areas Inspected Details of the functional or program areas inspected are discussed in Sections I and II of this report.
.
-4-
.
,, _,....... - -. _. -.
.
_
.
_
__
,
__
__.
_
.
Se: tion I
'
Prepared By:
C. E. Jones J. E. Konklin E. R. Schweibinz
.
Reviewed By:
C. C. Williams, Chief Projects Section 2 1.
Review of Licensee Actions Relative to Selected IE Bulletins and Circulars The Region III inspectors reviewed the licensee's corrective action as described in their November 28, 1979 response to a previous item of noncompliance. Their implementing procedure (SNED Procedure Q.39)
,
and the impicmentation of this method for controlling the review of Bullet'ns, Circulars, and Information Notices were found to be accept-able. The review included discussions with Ceco QA, licensing, and Station Nuclear Engineering Department (SNED) personnel.
The inspectors reviewed the documentation for the following Bulletins and Circulars received by Ceco to determine whether distribution was made to the appropriate persons, whether the required evaluations were performed, whether timely responses were sent to NRC when required, and whether the responses addressed the appropriate technical questions.
i IE Bulletin 79-13, Revision 2, October 16, 1979.
IE Bulletin 79-15, July 11, 1979.
IE Bulletin 79-17, July 26, 1979.
IE Bulletin 80-03, February 6,1980.
IE Bulletin 80-05, March 10, 1980.
- IE Bulletin 80-09, April 17, 1980.
IE Bulletin 80-11, May 8, 1980.
- IE Bulletin 80-12, May 9, 1980.
IE Circular 77-01, January 4, 1977.
IE Circular 77-10, July 18, 1977.
IE Circular 78-02, April 21, 1978.
IE Circular 78-05,llay 26, 1978.
l IE Circular 78-06, May 31, 1978.
IE Circular 78-13, July 10, 1978.
IE Circular 78-16, July 26, 1978.
l IE Circular 78-19, December 29, 1978.
l
- IE Circular 79-1C, June 26, 1979.
IE Circular 19-11, June 27, 1979.
IE Circular 79-12, June 28, 1979.
IE Circular 79-13, July 13, 1979.
IE Circular 79-18, September 10, 1979.
IE Circular 79-19, September 13, 1979.
IE Circular 79-22, November 16, 1979.
l
'
!
l-5-
-
_ _ _.... _ _ _ _. -
.
.
.
'
.
IE Circular 79-23, November 26, 1979.
-
IE Circular 79-24, November 26, 1979.
IE Circular 80-04, March 14, 1980.
- IE Circular 80-05, April 1, 1980.
IE Circular 80-07, April 3, 1980.
- IE Circular 80-09, April 28, 1980.
- IE Circular 80-10, April 29, 1980.
-
IE Circular 80-11, May 13, 1980.
,
- IE Circular 80-12, May 14, 1980.
- IE Circular 80-13, May 28, 1980.
- Denotes those Bulletins or Circulars in which the licensee's review is not yet complete, therefore these items will remain open.
(50-456/
80-07-01; 50-457/80-07-01).
- Denotes those Circulars that have been reviewed by the licensee for
the Byron Station, but not for the Braidwood Station as the review had been delayed during the extended construction delay at the Braidwood Station. These items are closed for the Byron Station, but remain open for the Braidwood Station (50-456/80-07-02; 50-457/80-07-02).
The remaining Bulletins and Circulars listed above are closed with regard to IE review, although the licensee actions are continuing relative to specific items associated with some of these Bulletins and Circulars.
2.
Verification of Licensee's ASME Certificate of Authorization The RIII inspectors verified the existence of the following documents:
The American Society of Mechanical Engineers, Certificate of a.
Authorization, No. N-1331, for Braidwood Station, Unit #1.
This authorization expires on April 21, 1982 and was origin-ally authorized on April 21, 1976. The expiration date was extended on February 10, 1979.
b.
The above dates including the extensions apply to all four units. The Certificate of Authorization number for Braidwood Station Unit #2 is N-1332, for Byron Station Unit #1 it is N-1366, for Byron Unit #2 it is N-1367.
l Commonwealth Edison Company, Station Nuclear Engineering Depart-c.
ment, Certificate of Authorization, No. N-2020, was authorized
'
on February 3, 1978 and expires on February 3, 1981.
i e-6-
........_,,,_,_____.m..
_._
.,
-
,_ _
.
.
.
f*
Section II Prepared By:
K. R. Naidu Reviewed By:
D. W. Hayes, Chief l
Engineering Support Section 1
-
\\
1.
The inspector reviewed licensee's action taken on the following IE Bulletins which included review of specifications and purchase orders by Sargent & Lundy and NSSS vendor. Based on these reviews and discussions with licensee personnel, the following IE Bulletin status was established. The results of previous reviews are docu-l mented in IE Reports No. 50-454/79-15, No. 50-455/79-15, No. 50-456/
79-13, 50-457/70-13. See previous RIII Report No. 50-454/79-11; No. 50-455/79-11 for discussion of site observations regarding Bulletins No. 76-02, No. 76-03, No. 76-05, and No. 77-01.
(Closed) 76-02 - Failure of GE type relay coils HEA, HGA, HKA, HMA.
l Licensee's letter dated May 12, 1976 indicates that the licensee will instruct the supplier of these relays to certify that Lexan bobbins
will be used instead of nylon bobbins for these plants.
'
(Closed) 76-03 - Malfunction of GE type relays STD. Licensee's letter dated May 12, 1976 indicates that these relays will not be used in these plants.
(Closed) 76-05 - Failure of Westinghouse relays type BFD. Licensee's letter dated May 13, 1976 indicates that this type of relay will not be used in these plants.
(Closed) 77-01 - Drift in Pneumatic Setpoint in ITE Imperial relays catalog J20T3/J13P20 or J20T3/J13P30. An attachment to the licensee's letter dated July 15, 1977 states that a review of the purchase docu-ments indicated that this type of time delay relays were not used in l
-
these plants.
(0 pen) 77-03 - On-line testing of the Westinghouse Solid State Protection Systems. Licensee's letter dated November 10, 1977 states that these plants will be installing WSSPS and that the l
!
preoperational and operating procedures will contain provisions to verify proper operation of the protection system; Westinghouse
[
Technical Bulletin NSD TB-77 will be used to prepare the procedures.
l, (Closed) 77-05 and 77-05A - Electrical connector assemblies. The licensee in a letter dated January 12, 1978 states that this type of connector mentioned in the bulletin is not used in these plants.
The (0 pen) 77-07 - Containment Electrical Penetration Assemblies.
licensee in a letter dated January 20, 1978 states that penetrations manufactured by Conax were being considered which use a pressure fitting and does not use the epoxy seal described in the bulletin.
.
-7-
..
.
-
-
,..
.. -
-. :.:. 7
..
_
_
_
P A second type manufactured by Banker Ramo's Amphenol Sams Division
was also being considered; this type uses the epoxy seal (mentioned in the bulletin) with a pressure barrier. During an inspection in July, it was determined that the Sams Amphenol penetrations were under 15 psi nitrogen pressure during storage.
(Closed) 78-02 - Terminal block qualification. Licensee's letter dated February 27, 1978 states that all terminal blocks which must function in a post-accident environment will be installed in pro-tecting enclosures.
(Open) 78-04 - Environmental qualification of certain stem mounted
,
~
limit switches inside reactor containment. The licensee's letter i
dated April 20, 1978 states that the above type of switches are being used in 35 air-operated safety related valves for isolating the containment under accident conditions specifically to " seal in" the valve control circuit and to provide valve position indication on the main enontrol board. Furthermore, it states that the plant is designed to eliminate any requirement that these limit switches perform a safety related function. Specifically, the design will incorporate a separate containment isolation signal; i.e., resetting i
safety injection will not reset the containment isolation signal.
Qualified stem mounted limit switches will be used on safety related motor operated valves in the primary containment.
(Open) 79-09 - Failure of GE breakers type AK2. The licensee in a l
letter dated June 18, 1979 states that these type of breakers are used in the DC panels for the 125 volt DC ESF buses; these breakers
!
are tripped by over current devices and not under-voltage trip devices. A preventive maintenance program is to be developed and implemented prior to fuel loading, using the contents of GE's service advice letter No. 175. This will be verified during a subsequent inspection.
(Closed) 79-11 - Faulty overcurrent trip device in Westinghouse type DB-50 and DB-75 circuit breakers. Licensee's letter dated July 19, 1979 states that breakers of this type are not being used in these l
'
plants.
(Closed) 79-23 - Potential Failure of " Emergency Diesel Generator Field Exciter Transformer." Licensee's letter dated October 26, 1979 states that the potential transformers used for voltage regulation and field excitation do not have a common neutral with the generators and that they are not grounded; there is no connec-tion between the' generator windings and the exciter control circuit through the grounding system or otherwise. The Diesel Genere*. ors in these plants have pilot exciters.
(Closed) 79-25 - Failures of Westinghouse relays type BFD.
Licensee's letter dated February 6, 1980 states that 70 NBFD four pole relays have been used in the 4.16 KV switchgear; NBFD relays f
-8-
- _..,. _, _ _ _ _ _,.. _,
_
1._,
a
.-.. -
.
O are not subject to either " sticking" or "insufficent over travel"
as addressed in Westinghouse technical bulletins NSD-TB-78-16 and NSD-TB-79-05 respectively.
(Closed) 79-27 - Eoss of nonclass IE instrumentation and control power system bus. As requested in the IE:III cover letter dated November 30, 1979, the licensee will address this as part o,f the
'
licensing process.
This matter is being transferred to RONS Branch for followup.
(Open) 79-28 - Possible malfunction of NAMCO Model EA180 limit switches at elevated temperatures. Examine if the four digits fall between 02-79 and 08-79; if they do, replace the top gasket of the switch. The licensee, in letters dated February 1980 and May 30, 1980 states that'these type of switches are used inside the containment. The cover gaskets on all NAMCO EA-180 will be replaced when the cable is terminated to the switch; the licensee instructed their construction department to replace the gaskets.
2.
The inspector reviewed licensee's action taken on the following IE Circulars:
(Closed) 80-01 - Service advice for General Electric Induction Disc Relays type 1AC, ICR, or IJCV. Number should be less than 50 and first letter followed by HJKL and M or AN, BN, CN, DN, EN, DG, EG, FG, GG.
No response from the licensee was required. Documents indicate that this type of relay was specified to be used in the Emergency Diesel Generator Control panels; upon verification with Cooper-Bessemer, it was determined that Westinghouse type SSV-T relays were substituted.
Exit Meeting The inspectors met with licensee representatives (denoted under Persons Contacted paragraph) at the conclusion of the inspection on July 24 and 25, 1980. The inspectors summarized the scope and findings of the inspection.
.
_9
--
- _, -
.... ~
.
-. - -
-
--