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{{#Wiki_filter:.* \/ .. Public Service Electric and Gas Company Louis F. Storz Public SeNice Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 | {{#Wiki_filter:.* \/ .. Public Service Electric and Gas Company Louis F. Storz Public SeNice Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President | ||
Senior Vice President | -Nuclear Operations MAY 2 2 1996 | ||
-Nuclear Operations | * LR-N96132 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | ||
MAY 2 2 1996 * LR-N96132 | RESPONSE TO NRC NOTICE OF VIOLATION INTEGRATED INSPECTION REPORT 50-272/96-05, 50-311/96-05 SALEM GENERATING STATION UNIT NOS. l AND 2 DOCKET NOS. 50-272 AND 50-311 HOPE CREEK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-354 Inspection Report Nos. 50-272/96-05 and 50-311/96-05 for Salem Nuclear Generating Station Unit Nos. 1 and 2 was transmitted to Public Electric & Gas Company (PSE&G) on April 22, 1996. Within the scope of this report, a violation of NRC requirements was cited. Pursuant to the provisions of 10CFR2.201, PSE&G submits its response to the aforementioned violation in Attachment I to this letter. This response is applicable to both Salem and Hope Creek Generating Stations. | ||
United States Nuclear Regulatory | Should there be any questions this submittal, please do not hesitate to contact us. Sincerely, Attachment (1) Q Printedon | ||
Commission | * Recycled Paper 9607080388 960702 PDR ADOCK 05000272 G PDR | ||
Document Control Desk Washington, DC 20555 Gentlemen: | \/ .. | ||
RESPONSE TO NRC NOTICE OF VIOLATION | * Document Control Desk LR-N96132 c J Mr. T. T. Martin, Administrator | ||
INTEGRATED | -Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 MAY 2 2 1996 Mr. L. N. | ||
INSPECTION | Licensing Project Manager -Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike M.ail Stop 14E21 Rockville, MD 20852 Mr. D. Jaffe., Licensing Project Manager -Hope Creek U. s. Nuclear Regulatory Commission One White Flint North. 11555 Rockville Pike Mail stop 14E21 Rockville, MD 20852 Mr. c. Marschall | ||
REPORT 50-272/96-05, 50-311/96-05 | -Salem (X24) USNRC Senior Resident Inspector Mr. R. Summers (X24) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933 V. Attachment I LR-N96132 APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating station Units 1 and 2 Hope Creek Generating Station Docket Nos. 50-272 50-311 50-354 License Nos. DPR-70 DPR-75 DPR-57 During an NRC inspection conducted on February 2S, 1996 -April 6, 1996, a violation of NRC requirements was identified. | ||
SALEM GENERATING | In accordance with the "General statement of Policy and Procedure for NRC Enforcement Actions," (60 FR 34381; June 30, 1995), the violation is listed below: Unit 1 Technical Specification | ||
STATION UNIT NOS. l AND 2 DOCKET NOS. 50-272 AND 50-311 HOPE CREEK GENERATING | {TS) 6.5.2.2 and Unit 2 TS 6.5.2.2 require, in part, that each Salem unit will have an Offsite Safety Review staff {OSR) and an Onsite Safety Review Group (SRG), consisting of at least four dedicated, full-time engineers. | ||
STATION UNIT NO. 1 DOCKET NO. 50-354 Inspection | TS 6.5.2.2, for each unit, also requires that the SRG and OSR engineers meet or exceed the qualifications described in Section 4.4 and 4.7, respectively, of ANS 3.1-1981. | ||
Report Nos. 50-272/96-05 | Contrary to the above, during the inspection period the resident inspectors determined that each Salem unit did not have an OSR and SRG consisting of at least four dedicated, full-time engineers; and that the SRG and the OSR engineers did not meet or exceed the quelifications described in Section 4.4 and 4.7, respectively, of ANS 3.1-1981. | ||
and 50-311/96-05 | This is a Severity Level IV violation. | ||
for Salem Nuclear Generating | PSE&G concurs with the violation, in that not all Specification 6.5.2.2 requirements were met. | ||
Station Unit Nos. 1 and 2 was transmitted | * .. . * | ||
to Public | * Attachment LR-N96132 (1) The reason for the violation. | ||
Electric & Gas Company (PSE&G) on April 22, 1996. Within the scope of this report, a violation | The root cause of this violation is attributed to failure of management to: 1. Maintain the appropriate controls over organizational structure changes to validate compliance with the licensing bases, and 2. Ensure that all applicable requirements of the ANS Standard were reviewed to verify alignment with the appropriate Nuclear Administrative Procedure (i.e., NC.NA-AP.ZZ-0014(Q), (NAP-14) "Training, Qualification and Certification"). | ||
of NRC requirements | The 1981 Salem TS for both Units 1 and 2 contained an organizational chart identified as: nFIGURE 6.2-1 CORPORATE HEADQUARTERS AND ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT." This chart described the organizational structure -for both Salem Units 1 and 2, and showed a single "Safety Review Group" reporting to the General Manager -Nuclear Support. Since 1981 a number of License Change Requests (LCR) were submitted to clarify and modify the organizational chart. In 1984, PSE&G submitted LCR 84-24 which also affected TS Section 6. This LCR modified the Nuclear Safety Review organization by creating an Offsite Safety Review (OSR) group and an Onsite Safety Review group. The OSR group was segregated into a Boiling Water Reactor (BWR) group and a Pressurized Water_ Reactor (PWR) group. The NRC's Safety Evaluation Report (SER) for LCR 84-24 (Amendments 62 and 33, which was one report addressing both Salem Units 1 and 2, respectively) acknowledged the change in Safety Review department nomenclature, and stated, in part: 11 **** The SRG, which meets the staff's requirements for an Independent Safety Engineering Group, remains intact except that it now reports to the General Manager-Nuclear Safety Review ........ We find this change acceptable | ||
was cited. Pursuant to the provisions | ... "* Regarding the OSR group, these organizational changes resulted in inappropriately crediting the supervisor of the Off-Site Safety Review_Engineering Group as a "dedicated engineer" toward the safety review function, and also failed to maintain the segregation between the Salem and Hope Creek groups. This resulted in a lack of clear delineation of responsibilities, wnich led-to dedicate four full-time engineers to the Salem OSR group, and four full-time engineers to the Hope Creek OSR group . I I I | ||
of 10CFR2.201, PSE&G submits its response to the aforementioned | '.J .* * | ||
violation | * Attachment LR-N96132 Certain individuals assigned to.the OSR and SRG positions do not hold a Bachelor's Degree in Engineering or related sciences. | ||
in Attachment | Subsection 4.1 of the ANS standard, though not explicitly referenced in the Technical Specifications (TS) states that experience may be evaluated and used in lieu of a degree. PSE&G's position was that Subsection 4.1 may be used to establish alternative qualifications and compliance with other subsections of Section 4 of the ANS Standard. | ||
I to this letter. This response is applicable | This interpretation is supported by the intent of the ANS Standard, and by the generally accepted principles for inclusion of, and adherence to, "referenced" documents. | ||
to both Salem and Hope Creek Generating | Subsection 4.1 also states that, when experience is substituted for education, the other compensating factors must be documented and approved by the Plant Manager. Although the appropriate documentation was approved, the approval was not obtained as prescribed in the ANS Standard. | ||
Stations. | (2) The corrective steps that have been taken. 1. On April 19, 1996, the OSR organization was segregated and assigned into two separate groups of four dedicated, time engineers. | ||
Should there be any questions | One group is dedicated to Hope Creek; the other is dedicated to Salem Station. A single supervisor provides oversight and direction to both groups and reports to the Manager -Nuclear Safety Review. 2. A qualification matrix has been developed for OSR engineers identifying the specialty areas in which they possess the appropriate years of professional levei experience. | ||
this submittal, please do not hesitate to contact us. Sincerely, Attachment | : 3. The SRG and OSR staff engineer's education equivalency forms have been approved by the Salem and Hope Creek Plant Managers. | ||
(1) Q Printedon | : 4. Prior to the issuance of this violation, PSE&G submitted two LCRs, on January 11, 1996, to relocate the review and audit functions of Section 6.5 of the Salem and Hope Creek Generating Stations Technical Specifications to the PSE&G QA program. (3) The corrective steps that will be taken to avoid further violations. | ||
* Recycled Paper 9607080388 | : 1. A sampling review of previously reviewed material for which the qualifications of the original reviewer have been called into question will be conducted. | ||
960702 PDR ADOCK 05000272 G PDR | The results of this review will be used to determine additional corrective actions. The review will be completed by June 28, 1996 . | ||
\/ .. * Document Control Desk LR-N96132 | ... *'* . | ||
-Region I U. s. Nuclear Regulatory | * Attachment LR-N96132 -4 2. PSE&G will evaluate NAP-14 to assure that qualification and* documentation approval requirements, as specified in the ANS Standard, are clearly reflected within the procedure. | ||
Commission | This action will be completed by July 1, 1996. 3. The lessons learned from this event will be communicated to the appropriate Nuclear Business Unit personnel to emphasize the need to assure that organizational structural changes are made consistent with the facility licensing bases. This will be completed by June 15, 1996. (4) The date when full compliance will be achieved. | ||
475 Allendale | PSE&G achieved partial compliance with the Salem Technical Specifications on April 19, 1996, when the OSR group was segregated and four dedicated, full-time engineers were assigned to the Salem OSR group. The Hope Creek Station OSR group has three dedicated, full-time engineers assigned to it with the fourth position to be filled; This vacant position is expected to be filled by June 30, 1996. In addition, PSE&G is also requesting*to change the Quality Assurance program via 10CFR50.54a to allow realignment of the Quality Assurance (QA), NSR, and Nuclear Review Board (NRB) functions. | ||
Road King of Prussia, PA 19406 MAY 2 2 1996 Mr. L. N. | It is expected that this request will be submitted by May 31, 1996. This request will also specify that QA. (only those assigned to perform the independent review function) , and NRB personnel will meet or exceed the qualification requirements of applicable sections of ANSI/ANS 3.1 -1981, "American National Standard for Selection, Qualification and Training of Personnel for Nuclear Power Plants." By this action the appropriateness of applying Section 4.1 to other subsections of. Section 4 of *the ANS Standard will be clearly established. | ||
Licensing | .... ,. -The following lists all commitments made by PSE&G, in letter LR-N96132, with their respective due dates. 1. A sampling review of previously reviewed material for which the qualifications of the original reviewer have been called into question will be conducted. | ||
Project Manager -Salem U. s. Nuclear Regulatory | The results of this review will be used to determine additional corrective actions. The review will be completed by June 28, 1996. 2. PSE&G will evaluate NAP-14 to assure that qualification and documentation approval requirements, as specified in the ANS standard, are clearly reflected within the procedure. | ||
Commission | This action will be completed by July l, 1996. 3. The lessons learned from this event will be communicated to the appropriate Nuclear Business Unit personnel to emphasize the need to assure that organizational structural changes are made consistent with the facility licensing bases. This will be completed by June 15, 1996. 4. PSE&G achieved partial compliance with the Salem Technical Specifications on April 19, 1996, when the OSR group was | ||
One White Flint North 11555 Rockville | * segregated and four dedicated, full-time engineers were assigned to the Salem OSR group. The Hope Creek Station OSR group has three dedicated, full-time engineers assigned to it with the fourth position to be filled. This vacant position is expected to be filled by June 30, 1996.}} | ||
Pike M.ail Stop 14E21 Rockville, MD 20852 Mr. D. Jaffe., Licensing | |||
Project Manager -Hope Creek U. s. Nuclear Regulatory | |||
Commission | |||
One White Flint North. 11555 Rockville | |||
Pike Mail stop 14E21 Rockville, MD 20852 Mr. c. Marschall | |||
-Salem (X24) USNRC Senior Resident Inspector | |||
Mr. R. Summers (X24) USNRC Senior Resident Inspector | |||
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering | |||
33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933 | |||
V. Attachment | |||
I LR-N96132 | |||
Public Service Electric and Gas Company Salem Nuclear Generating | |||
station Units 1 and 2 Hope Creek Generating | |||
Station Docket Nos. 50-272 50-311 50-354 License Nos. DPR-70 DPR-75 DPR-57 During an NRC inspection | |||
conducted | |||
on February 2S, 1996 -April 6, 1996, a violation | |||
of NRC requirements | |||
was identified. | |||
In accordance | |||
with the "General statement | |||
of Policy and Procedure | |||
for NRC Enforcement | |||
Actions," (60 FR 34381; June 30, 1995), the violation | |||
is listed below: Unit 1 Technical | |||
Specification | |||
{TS) 6.5.2.2 and Unit 2 TS 6.5.2.2 require, in part, that each Salem unit will have an Offsite Safety Review staff {OSR) and an Onsite Safety Review Group (SRG), consisting | |||
of at least four dedicated, full-time | |||
engineers. | |||
TS 6.5.2.2, for each unit, also requires that the SRG and OSR engineers | |||
meet or exceed the qualifications | |||
described | |||
in Section 4.4 and 4.7, respectively, of ANS 3.1-1981. | |||
Contrary to the above, during the inspection | |||
period the resident inspectors | |||
determined | |||
that each Salem unit did not have an OSR and SRG consisting | |||
of at least four dedicated, full-time | |||
engineers; | |||
and that the SRG and the OSR engineers | |||
did not meet or exceed the quelifications | |||
described | |||
in Section 4.4 and 4.7, respectively, of ANS 3.1-1981. | |||
This is a Severity Level IV violation. | |||
PSE&G concurs with the violation, in that not all | |||
Specification | |||
6.5.2.2 requirements | |||
were met. | |||
* .. . * * Attachment | |||
LR-N96132 | |||
The root cause of this violation | |||
is attributed | |||
to failure of management | |||
to: 1. Maintain the appropriate | |||
controls over organizational | |||
structure | |||
changes to validate compliance | |||
with the licensing | |||
bases, and 2. Ensure that all applicable | |||
requirements | |||
of the ANS Standard were reviewed to verify alignment | |||
with the appropriate | |||
Nuclear Administrative | |||
Procedure (i.e., NC.NA-AP.ZZ-0014(Q), (NAP-14) "Training, Qualification | |||
and Certification"). | |||
The 1981 Salem TS for both Units 1 and 2 contained | |||
an organizational | |||
chart identified | |||
as: nFIGURE 6.2-1 CORPORATE | |||
HEADQUARTERS | |||
AND | |||
ORGANIZATION | |||
FOR MANAGEMENT | |||
AND TECHNICAL | |||
SUPPORT." This chart described | |||
the organizational | |||
structure -for both Salem Units 1 and 2, and showed a single "Safety Review Group" reporting | |||
to the General Manager -Nuclear Support. Since 1981 a number of License Change Requests (LCR) were submitted | |||
to clarify and modify the organizational | |||
chart. In 1984, PSE&G submitted | |||
LCR 84-24 which also affected TS Section 6. This LCR modified the Nuclear Safety Review organization | |||
by creating an Offsite Safety Review (OSR) group and an Onsite Safety Review group. The OSR group was segregated | |||
into a Boiling Water Reactor (BWR) group and a Pressurized | |||
Water_ Reactor (PWR) group. The NRC's Safety Evaluation | |||
Report (SER) for LCR 84-24 (Amendments | |||
62 and 33, which was one report addressing | |||
both Salem Units 1 and 2, respectively) | |||
acknowledged | |||
the change in Safety Review department | |||
nomenclature, and stated, in part: 11 **** The SRG, which meets the staff's requirements | |||
for an Independent | |||
Safety Engineering | |||
Group, remains intact except that it now reports to the General Manager-Nuclear | |||
Safety Review ........ We find this change acceptable | |||
... "* Regarding | |||
the OSR group, these organizational | |||
changes resulted in inappropriately | |||
crediting | |||
the supervisor | |||
of the Off-Site Safety Review_Engineering | |||
Group as a "dedicated | |||
engineer" toward the safety review function, and also failed to maintain the segregation | |||
between the Salem and Hope Creek groups. This resulted in a lack of clear delineation | |||
of responsibilities, wnich led- | |||
to dedicate four full-time | |||
engineers | |||
to the Salem OSR group, and four full-time | |||
engineers | |||
to the Hope Creek OSR group . I I I | |||
'.J .* * * Attachment | |||
LR-N96132 | |||
assigned to.the OSR and SRG positions | |||
do not hold a Bachelor's | |||
Degree in Engineering | |||
or related sciences. | |||
Subsection | |||
4.1 of the ANS standard, though not explicitly | |||
referenced | |||
in the Technical | |||
Specifications (TS) states that experience | |||
may be evaluated | |||
and used in lieu of a degree. PSE&G's position was that Subsection | |||
4.1 may be used to establish | |||
alternative | |||
qualifications | |||
and compliance | |||
with other subsections | |||
of Section 4 of the ANS Standard. | |||
This interpretation | |||
is supported | |||
by the intent of the ANS Standard, and by the generally | |||
accepted principles | |||
for inclusion | |||
of, and adherence | |||
to, "referenced" documents. | |||
Subsection | |||
4.1 also states that, when experience | |||
is substituted | |||
for education, the other compensating | |||
factors must be documented | |||
and approved by the Plant Manager. Although the appropriate | |||
documentation | |||
was approved, the approval was not obtained as prescribed | |||
in the ANS Standard. | |||
(2) The corrective | |||
steps that have been taken. 1. On April 19, 1996, the OSR organization | |||
was segregated | |||
and assigned into two separate groups of four dedicated, time engineers. | |||
One group is dedicated | |||
to Hope Creek; the other is dedicated | |||
to Salem Station. A single supervisor | |||
provides oversight | |||
and direction | |||
to both groups and reports to the Manager -Nuclear Safety Review. 2. A qualification | |||
matrix has been developed | |||
for OSR engineers | |||
identifying | |||
the specialty | |||
areas in which they possess the appropriate | |||
years of professional | |||
levei experience. | |||
3. The SRG and OSR staff engineer's | |||
education | |||
equivalency | |||
forms have been approved by the Salem and Hope Creek Plant Managers. | |||
4. Prior to the issuance of this violation, PSE&G submitted | |||
two LCRs, on January 11, 1996, to relocate the review and audit functions | |||
of Section 6.5 of the Salem and Hope Creek Generating | |||
Stations Technical | |||
Specifications | |||
to the PSE&G QA program. (3) The corrective | |||
steps that will be taken to avoid further violations. | |||
1. A sampling review of previously | |||
reviewed material for which the qualifications | |||
of the original reviewer have been called into question will be conducted. | |||
The results of this review will be used to determine | |||
additional | |||
corrective | |||
actions. The review will be completed | |||
by June 28, 1996 . | |||
... *'* . * Attachment | |||
LR-N96132 -4 2. PSE&G will evaluate NAP-14 to assure that qualification | |||
and* documentation | |||
approval requirements, as specified | |||
in the ANS Standard, are clearly reflected | |||
within the procedure. | |||
This action will be completed | |||
by July 1, 1996. 3. The lessons learned from this event will be communicated | |||
to the appropriate | |||
Nuclear Business Unit personnel | |||
to emphasize | |||
the need to assure that organizational | |||
structural | |||
changes are made consistent | |||
with the facility licensing | |||
bases. This will be completed | |||
by June 15, 1996. (4) The date when full compliance | |||
will be achieved. | |||
PSE&G achieved partial compliance | |||
with the Salem Technical | |||
Specifications | |||
on April 19, 1996, when the OSR group was segregated | |||
and four dedicated, full-time | |||
engineers | |||
were assigned to the Salem OSR group. The Hope Creek Station OSR group has three dedicated, full-time | |||
engineers | |||
assigned to it with the fourth position to be filled; This vacant position is expected to be filled by June 30, 1996. In addition, PSE&G is also requesting*to | |||
change the Quality Assurance | |||
program via 10CFR50.54a | |||
to allow realignment | |||
of the Quality Assurance (QA), NSR, and Nuclear Review Board (NRB) functions. | |||
It is expected that this request will be submitted | |||
by May 31, 1996. This request will also specify that QA. (only those assigned to perform the independent | |||
review function) , and NRB personnel | |||
will meet or exceed the qualification | |||
requirements | |||
of applicable | |||
sections of ANSI/ANS 3.1 -1981, "American | |||
National Standard for Selection, Qualification | |||
and Training of Personnel | |||
for Nuclear Power Plants." By this action the appropriateness | |||
of applying Section 4.1 to other subsections | |||
of. Section 4 of *the ANS Standard will be clearly established. | |||
.... ,. -The following | |||
lists all commitments | |||
made by PSE&G, in letter LR-N96132, with their respective | |||
due dates. 1. A sampling review of previously | |||
reviewed material for which the qualifications | |||
of the original reviewer have been called into question will be conducted. | |||
The results of this review will be used to determine | |||
additional | |||
corrective | |||
actions. The review will be completed | |||
by June 28, 1996. 2. PSE&G will evaluate NAP-14 to assure that qualification | |||
and documentation | |||
approval requirements, as specified | |||
in the ANS standard, are clearly reflected | |||
within the procedure. | |||
This action will be completed | |||
by July l, 1996. 3. The lessons learned from this event will be communicated | |||
to the appropriate | |||
Nuclear Business Unit personnel | |||
to emphasize | |||
the need to assure that organizational | |||
structural | |||
changes are made consistent | |||
with the facility licensing | |||
bases. This will be completed | |||
by June 15, 1996. 4. PSE&G achieved partial compliance | |||
with the Salem Technical | |||
Specifications | |||
on April 19, 1996, when the OSR group was * segregated | |||
and four dedicated, full-time | |||
engineers | |||
were assigned to the Salem OSR group. The Hope Creek Station OSR group has three dedicated, full-time | |||
engineers | |||
assigned to it with the fourth position to be filled. This vacant position is expected to be filled by June 30, 1996. | |||
}} |
Revision as of 20:08, 31 July 2019
ML18102A236 | |
Person / Time | |
---|---|
Site: | Salem, Hope Creek |
Issue date: | 05/22/1996 |
From: | Storz L Public Service Enterprise Group |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML18102A235 | List: |
References | |
2.201, LR-N96132, NUDOCS 9607080388 | |
Download: ML18102A236 (7) | |
Text
.* \/ .. Public Service Electric and Gas Company Louis F. Storz Public SeNice Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President
-Nuclear Operations MAY 2 2 1996
- LR-N96132 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RESPONSE TO NRC NOTICE OF VIOLATION INTEGRATED INSPECTION REPORT 50-272/96-05, 50-311/96-05 SALEM GENERATING STATION UNIT NOS. l AND 2 DOCKET NOS. 50-272 AND 50-311 HOPE CREEK GENERATING STATION UNIT NO. 1 DOCKET NO. 50-354 Inspection Report Nos. 50-272/96-05 and 50-311/96-05 for Salem Nuclear Generating Station Unit Nos. 1 and 2 was transmitted to Public Electric & Gas Company (PSE&G) on April 22, 1996. Within the scope of this report, a violation of NRC requirements was cited. Pursuant to the provisions of 10CFR2.201, PSE&G submits its response to the aforementioned violation in Attachment I to this letter. This response is applicable to both Salem and Hope Creek Generating Stations.
Should there be any questions this submittal, please do not hesitate to contact us. Sincerely, Attachment (1) Q Printedon
\/ ..
- Document Control Desk LR-N96132 c J Mr. T. T. Martin, Administrator
-Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 MAY 2 2 1996 Mr. L. N.
Licensing Project Manager -Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike M.ail Stop 14E21 Rockville, MD 20852 Mr. D. Jaffe., Licensing Project Manager -Hope Creek U. s. Nuclear Regulatory Commission One White Flint North. 11555 Rockville Pike Mail stop 14E21 Rockville, MD 20852 Mr. c. Marschall
-Salem (X24) USNRC Senior Resident Inspector Mr. R. Summers (X24) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933 V. Attachment I LR-N96132 APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating station Units 1 and 2 Hope Creek Generating Station Docket Nos. 50-272 50-311 50-354 License Nos. DPR-70 DPR-75 DPR-57 During an NRC inspection conducted on February 2S, 1996 -April 6, 1996, a violation of NRC requirements was identified.
In accordance with the "General statement of Policy and Procedure for NRC Enforcement Actions," (60 FR 34381; June 30, 1995), the violation is listed below: Unit 1 Technical Specification
{TS) 6.5.2.2 and Unit 2 TS 6.5.2.2 require, in part, that each Salem unit will have an Offsite Safety Review staff {OSR) and an Onsite Safety Review Group (SRG), consisting of at least four dedicated, full-time engineers.
TS 6.5.2.2, for each unit, also requires that the SRG and OSR engineers meet or exceed the qualifications described in Section 4.4 and 4.7, respectively, of ANS 3.1-1981.
Contrary to the above, during the inspection period the resident inspectors determined that each Salem unit did not have an OSR and SRG consisting of at least four dedicated, full-time engineers; and that the SRG and the OSR engineers did not meet or exceed the quelifications described in Section 4.4 and 4.7, respectively, of ANS 3.1-1981.
This is a Severity Level IV violation.
PSE&G concurs with the violation, in that not all Specification 6.5.2.2 requirements were met.
- .. . *
- Attachment LR-N96132 (1) The reason for the violation.
The root cause of this violation is attributed to failure of management to: 1. Maintain the appropriate controls over organizational structure changes to validate compliance with the licensing bases, and 2. Ensure that all applicable requirements of the ANS Standard were reviewed to verify alignment with the appropriate Nuclear Administrative Procedure (i.e., NC.NA-AP.ZZ-0014(Q), (NAP-14) "Training, Qualification and Certification").
The 1981 Salem TS for both Units 1 and 2 contained an organizational chart identified as: nFIGURE 6.2-1 CORPORATE HEADQUARTERS AND ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT." This chart described the organizational structure -for both Salem Units 1 and 2, and showed a single "Safety Review Group" reporting to the General Manager -Nuclear Support. Since 1981 a number of License Change Requests (LCR) were submitted to clarify and modify the organizational chart. In 1984, PSE&G submitted LCR 84-24 which also affected TS Section 6. This LCR modified the Nuclear Safety Review organization by creating an Offsite Safety Review (OSR) group and an Onsite Safety Review group. The OSR group was segregated into a Boiling Water Reactor (BWR) group and a Pressurized Water_ Reactor (PWR) group. The NRC's Safety Evaluation Report (SER) for LCR 84-24 (Amendments 62 and 33, which was one report addressing both Salem Units 1 and 2, respectively) acknowledged the change in Safety Review department nomenclature, and stated, in part: 11 **** The SRG, which meets the staff's requirements for an Independent Safety Engineering Group, remains intact except that it now reports to the General Manager-Nuclear Safety Review ........ We find this change acceptable
... "* Regarding the OSR group, these organizational changes resulted in inappropriately crediting the supervisor of the Off-Site Safety Review_Engineering Group as a "dedicated engineer" toward the safety review function, and also failed to maintain the segregation between the Salem and Hope Creek groups. This resulted in a lack of clear delineation of responsibilities, wnich led-to dedicate four full-time engineers to the Salem OSR group, and four full-time engineers to the Hope Creek OSR group . I I I
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- Attachment LR-N96132 Certain individuals assigned to.the OSR and SRG positions do not hold a Bachelor's Degree in Engineering or related sciences.
Subsection 4.1 of the ANS standard, though not explicitly referenced in the Technical Specifications (TS) states that experience may be evaluated and used in lieu of a degree. PSE&G's position was that Subsection 4.1 may be used to establish alternative qualifications and compliance with other subsections of Section 4 of the ANS Standard.
This interpretation is supported by the intent of the ANS Standard, and by the generally accepted principles for inclusion of, and adherence to, "referenced" documents.
Subsection 4.1 also states that, when experience is substituted for education, the other compensating factors must be documented and approved by the Plant Manager. Although the appropriate documentation was approved, the approval was not obtained as prescribed in the ANS Standard.
(2) The corrective steps that have been taken. 1. On April 19, 1996, the OSR organization was segregated and assigned into two separate groups of four dedicated, time engineers.
One group is dedicated to Hope Creek; the other is dedicated to Salem Station. A single supervisor provides oversight and direction to both groups and reports to the Manager -Nuclear Safety Review. 2. A qualification matrix has been developed for OSR engineers identifying the specialty areas in which they possess the appropriate years of professional levei experience.
- 3. The SRG and OSR staff engineer's education equivalency forms have been approved by the Salem and Hope Creek Plant Managers.
- 4. Prior to the issuance of this violation, PSE&G submitted two LCRs, on January 11, 1996, to relocate the review and audit functions of Section 6.5 of the Salem and Hope Creek Generating Stations Technical Specifications to the PSE&G QA program. (3) The corrective steps that will be taken to avoid further violations.
- 1. A sampling review of previously reviewed material for which the qualifications of the original reviewer have been called into question will be conducted.
The results of this review will be used to determine additional corrective actions. The review will be completed by June 28, 1996 .
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- Attachment LR-N96132 -4 2. PSE&G will evaluate NAP-14 to assure that qualification and* documentation approval requirements, as specified in the ANS Standard, are clearly reflected within the procedure.
This action will be completed by July 1, 1996. 3. The lessons learned from this event will be communicated to the appropriate Nuclear Business Unit personnel to emphasize the need to assure that organizational structural changes are made consistent with the facility licensing bases. This will be completed by June 15, 1996. (4) The date when full compliance will be achieved.
PSE&G achieved partial compliance with the Salem Technical Specifications on April 19, 1996, when the OSR group was segregated and four dedicated, full-time engineers were assigned to the Salem OSR group. The Hope Creek Station OSR group has three dedicated, full-time engineers assigned to it with the fourth position to be filled; This vacant position is expected to be filled by June 30, 1996. In addition, PSE&G is also requesting*to change the Quality Assurance program via 10CFR50.54a to allow realignment of the Quality Assurance (QA), NSR, and Nuclear Review Board (NRB) functions.
It is expected that this request will be submitted by May 31, 1996. This request will also specify that QA. (only those assigned to perform the independent review function) , and NRB personnel will meet or exceed the qualification requirements of applicable sections of ANSI/ANS 3.1 -1981, "American National Standard for Selection, Qualification and Training of Personnel for Nuclear Power Plants." By this action the appropriateness of applying Section 4.1 to other subsections of. Section 4 of *the ANS Standard will be clearly established.
.... ,. -The following lists all commitments made by PSE&G, in letter LR-N96132, with their respective due dates. 1. A sampling review of previously reviewed material for which the qualifications of the original reviewer have been called into question will be conducted.
The results of this review will be used to determine additional corrective actions. The review will be completed by June 28, 1996. 2. PSE&G will evaluate NAP-14 to assure that qualification and documentation approval requirements, as specified in the ANS standard, are clearly reflected within the procedure.
This action will be completed by July l, 1996. 3. The lessons learned from this event will be communicated to the appropriate Nuclear Business Unit personnel to emphasize the need to assure that organizational structural changes are made consistent with the facility licensing bases. This will be completed by June 15, 1996. 4. PSE&G achieved partial compliance with the Salem Technical Specifications on April 19, 1996, when the OSR group was
- segregated and four dedicated, full-time engineers were assigned to the Salem OSR group. The Hope Creek Station OSR group has three dedicated, full-time engineers assigned to it with the fourth position to be filled. This vacant position is expected to be filled by June 30, 1996.