ML20245L698
| ML20245L698 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/15/1989 |
| From: | Blount J SYSTEM ENERGY RESOURCES, INC. |
| To: | |
| Shared Package | |
| ML20245L696 | List: |
| References | |
| NUDOCS 8908220254 | |
| Download: ML20245L698 (79) | |
Text
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PCOL-89/07-UNITED: STATES OF AMERICA NUCLEAR REGULATORY COMMISSION-2 In thelMatter of
)
. Docket No. 50-416 i
SYSTEM ENERGY RESOURCES, INC.
)
1 SOUTH MISSISSIPPI ELECTRIC POWER g
ASSOCIATION
)
MISSISSIPPI POWER & LIGHT ~ COMPANY
)
)
(Grand Gulf Nuclear Station, Unit 1)
)
APPLICATION TO AMEND FACILITY OPERATING LICENSE NO. NPF-29 System Energy Resources, Inc., (" System Energy"), South Mississippi Electric Power Association ("SMEPA") and Mississippi Power & Light _ Company ("MP&L") (collectively " Joint Licensees")
are the holciers of Facility. Operating License No. NPF-29 for Grand Gulf. Nuclear Station (" Grand Gulf"), Unit 1.
The operating license
. presently' authorizes System Energy and SMEPA to possess Grand Gulf Unit.11as joint owners.and authorizes System Energy to possess, use andLoperate Grand Gulf Unit 1 in accordance with the terms and conditions of the license.
System Energy is a wholly-owned subsidiary of Entergy
- Corporation ("Entergy").
Entergy also owns the common stock of Arkansas Power & Light Company ("AP&L"), Louisiana Power & Light Company ("LP&L") and MP&L.
AP&L is licensed by the Nuclear Regulatory Commission ("NRC") to possess, u'se and operate Arkansas 8908220254 890815 DR ADOCK 0500 g6 NLSRPT88051701 - 1
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=.2-Nuclear-One, Units'1 and 2;("ANO-1" and "AND-2").
LP&L.is licensed to-possess, use and' operate Waterford Steam Electric Station, Unit 3 ("Waterford 3".).
MP&L was originally-licensed to possess, use'and operate Grand Gulf Unit I prior to transfer of
. such rights to System Energy in 1986 and remains subject to.the antitrust. conditions of Facility Operating License No. NPF-29.
In requests to the NRC dated July 1, 1988, AP&L and LP&L-submitted proposed ~ license = amendments to designate System Energy
- as the licensed operator for ANO and Waterford 3, respectively.
Entergy now plans for a new company to be called Entergy-Operations, Inc..("E01")-.to become its system-wide nuclear operating company.
As such, E01 would assume operating responsibility for'-- but not ownership of -- Waterford 3, ANO-1, ANO-2, and Grand Gulf, Unit 1.
This assumption.of operating
. responsibility will be accomplished by operating agreements between LP&L and EDI, between AP&L.and E0I, and between System Energy.and E01, each agreement designating E0I as the agent for the owner or owners, as the case may be, and authorizing E01 to operate its plant or plants.
The assumption of operating responsibility by E01 for Waterford 3, ANO-1, ANO-2, and Grand Gulf Unit I will not impact existing plant ownership or entitlement to capacity and energy.
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Upon receipt of'necessary. regulatory approvals and transfer to.E01;of System Energy' personnel E01 will succeed System Energy as operator of' Grand Gulf Unit 1.
This amendment application requests that the NRC amend Operating License No. NPF-29 to
' authorize and reflect in'the license the change from System Energy to E01 as the licensee. authorized _to possess, use and operate Grand Gulf Unit'1. 1/
Ownership of Grand Gulf Unit I wi'11 remain unchanged with SMEPA retaining its ten percent undivided ownership interest and System Energy retaining its ninety percent ownership and leasehold interest. 2/-
1/
The proposed changes to the Grand Gulf Unit 1 Operating License to reflect the establishment of E01 as licensee responsible for the operation of Grand Gulf Unit 1 are
. included in Attachment 1.
Other than submittals currently pending NRC approval, this amendment application involves no additional changes to the Technical Specifications.
-2/
On December 19, 1988, the NRC issued Amendment No. 54 to Facility Operating License No. NPF-29 for Grand Gulf Unit 1.
This Amendment authorized System Energy to sell and leaseback a portion of its 90 percent undivided interest in the facility.
The assumption of operating responsibility by l
E01 does not impact this authorization or the agreements 3
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executed by System Energy under that authorization.
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Specifically,1 pursuant to 10~C.F.R.-E 50.90,-the Joint Licensees hereby request;that'the NRC amend' Operating License No. NPF-29 to 7 change the name of the licensees for Grand Gulf Unit 1, such that:
(1)
EDI, pursuant to section 103 of the Atomic Energy Act of u
' :c:
1954, as amended, ("the Act") and 10 C.F.R. Part 50
" Domestic Licensing of Production and Utilization Facilities," is licensed to possess, use and operate Grand Gulf Unit I at the designated location in-Claiborne-County, Mississippi, in accordance with the procedures and limitations set forth in the License; (2)
System Energy and SMEPA, pursuant to the Act and 10 C.F.R. Part 50, are licensed to possess Grand Gulf Unit-1 at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in the License; (3)
E01, pursuant to the Act and 10 C.F.R. Part 70, is licensed to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
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(4). EDI, pursuant to the Act.and 10 C.F.R. Parts 30, 40 and 70, is licensed to receive, possess, and use at any time any byproduct, source and special nuclear material.as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5).
E01, pursuant to the Act and 10 C.F.R. Parts 30, 40 and 70, is licensed to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
E01, pursuant to the Act and 10 C.F.R. Parts 30, 40 and 70, is licensed to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Grand Gulf Unit 1.
(7)
(a)
System Energy is authorized to transfer up to 15 percent of its 90.0% ownership share in Grand Gulf Nuclear Station, Unit 1 (GGNS Unit 1), to certain equity investors identified in the submissions of October 31, 1988 and November 11, 1988, and at the same time to lease back from such purchasers such interest sold in the f
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m facility.
The-term of the lease is for approximately 26 years subject to a right1of
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renewal.
'Such sale'and-leaseback transactions are
. subject to the condition that lessors and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over (i) GGNS Unit 1 (ii) power or energy produced by GGNS Unit 1, or (iii) the licensees of GGNS Unit 1.
Further, any rights acquired under this authorization may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the Commission's regulations.
For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently amended, are fully applicable to the lessors and any successors in interest to those lessors, as long as the license for GGNS Unit I remains in-effect.
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- (b). System Energy is required to notify the.NRC.in-writing prior to any change in.(i) the terms or conditions of any new or existing sale or lease agreements executed as.part of the above authorized financial transactions ~, (ii) the GGNS Unit--I operating: agreement, (iii) the existing property.
insurance coverage for GGNS Unit 1 that would materially alter the representations and conditions
. set forth in the staff's' Safety. Evaluation Report dated December 19, 1988 attached to Amendment No. 54.
.In addition, System Energy is required to notify the NRC'of any action by a. lessor or other successor in interest to System Energy that may have an effect on the operation of the facility.
-0ther conforming license changes are noted in the attachments to this Application. 3/- Set forth below is the information in support of the-Application to Amend Facility Operating License No.
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Conforming changes, if necessary, in insurance and indemnity agreements will be made in due course by separate correspondence.
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GENERAL INFORMATION CONCERNING LICENSE AMENDMENT A.
P,roposed Ad"ditional Licensee:
Entergy Operations, Inc..
- B.
' Address:
Echelon One 1340 Echelon Parkway Jackson, MS-39213 C.
Description _of' Business or Occupation Prior to issuance of this license amendment, E01 will be organized as a wholly-owned subsidiary of Entergy and will take necessary corporate action to authorize it to operate Waterford 3, ANO-1, ANO-2, and Grand Gulf Unit 1.
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'After. approval of this requested amendment and a similar amendment' to the Operating Licenses for ANO-1, ANO-2, and Waterford 3. E01-will be responsible for the operation and maintenance of all nuclear. plants in the Middle _ South Electric System, including I
Grand Gulf Unit 1.
Upon receipt of necessary regulatory approvals,
.E01,.as distinct from' System Energy as a co-owner of the facility.
will'have responsibility for and control over the physical construction, operation, and maintenance of the facility.
D.
Organization and Management of Operating Corporation E01'is a corporation to be organized and' existing under the laws of the state of Delaware.
Its principal office will be located in Jackson, Mississippi.
The corporation will be neither owned, controlled nor dominated by an alien, a foreign corporation, nor a foreign government.
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'All-prospective directors and principal officers of E01 are citizens of the United States.
Their names and addresses are as
~
follows: 4/
Directors Mr. Edwin A..Lupberger Chairman of the Board Entergy Operations, Inc.
P. O. Box 61005 New Orleans, LA 70161 Mr. William Cavanaugh, III President'& Chief Executive Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Mr. James M. Cain Chairman and Chief Executive Officer Louisiana Power & Light Company P. O. Box 60340 New Orleans, LA 70160 Dr. Joseph M. Hendrie Nuclear Engineering Consultant 50 Bellport Lane Bellport, NY 11713 Senior Scientist; Research and Development Brookhaven National Laboratory Mr. Jerry L. Maulden President and Chief Executive Officer Arkansas Power & Light Company P. O. Box 551
-Little Rock, AR 72203 i
-4/
Additional directors and officers may be named at a later
-date.
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i s n LUpontissuance-ofttheL0perating-License amendment,'it is n
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-j-(anticipated?that*al11 officers:of, System Energy will become i
-officers of E01candicertain officers 1of AP&L and LP&L will'become officersiof1E01.,
I
. E. -.
l Technical-Qualifications-
-TheLtechhical; qualificationsof.E0IL to carry out' its
,J responsibilities under.the Operating License for Grand Gulf Unit l',Lastamended;:will' meet or e'ceed the present technical x
- qualificationsfof1 System Energy.
System Energy.will continue.to-
~
y act!as the operator.of-Grand Gulf Unit 1, pending-issuance ofJthe proposed' amendment ofmthe Operating License.
When the. amendment-becomes effective,'E01 will assume responsibility for,'and control s
over, the physical. construction, operation, and' maintenance of the
- facility.
Theipresent Grand Gulf Unit 1 Nuclear Operations and Nuclear: Engineering & Support organizations wil1~be' transferred essentially intact to E0I'.
The. technical qualifications of.the sproposed-GrandiGulf. Unit 1 organization, therefore,:will be at l'
- least< equivalent to those of'the existing organization.
'Entergy has-expended substantial effort in planning a
. consolidated organization for operation of its nuclear units.
EDI has now been designated as the organization to fulfill that role.
-A central objective in planning the proposed consolidation and the transfer of employees and operating responsibilities from System. Energy to E01 has been to minimize disruption to the operationoof the plants and to respect the integrity of the h
NLSRPT88051701
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existing, successful organizations Therefore, in the proposed E011 organization, each nuclear organization ofsthe operating plants will be' preserved with the o'nly change that the senior nuclear executives from-the LP&L, AP&L and System Energy organizations will report directly to the Executive'Vice President and Chief Operating Officer who reports to the President and' Chief Executive Officer of EDI.
This organization is
. illustrated in Attachment 2.
Thus, for Grand Gulf Unit 1, W. T.
Cottle, Vice' President - Nuclear Operations'and T. H. Cloninger, Vice President - Engineering & Support, will report directly to the Er.ecutive.Vice President and Chief Operating Officer.
The Quality Programs Department for the plant will also have direct access to both the Executive Vice President and Chief Operating Officer and the President and-Chief Executive Officer of E01 on matters related to quality.
This organizational approach accommodates the current plant-specific structure of the System Energy organization.
This allows the transfer of System Energy nuclear personnel to E01 with virtual.ly.no organizational changes or disruption.
It also allows the management for Grand Gulf 1 to retain sufficient independence to address plant-specific needs and to maintain existing priorities aad ongoing plant improvement projects.
Importantly, and as discussed below, there will be in the near term no organizational
-or physical location changes to the existing, dedicated, f
organization. which would include the engineering, quality assurance, and licensing organizations supporting Grand Gulf Unit 1.
NLSRPT88051701 - 13
The.significant elements and advantages to the proposed E0I' organization can be' summarized as follows:
(1). The structure provides clear lines of authority _and responsibility while ensuring that essential nuclear support functions are dedicated to each project and e-report to a single responsible project executive.
(2)
The effectiveness of project quality assurance will not be. degraded.
(3). The project structure will continue to provide the
-project executive the flexibility necessary for managing his resources to achieve optimal results.
Ongoing plant
. improvement plans;will not be impacted.
( 4 )-
The project structure provides the flexibility necessary to adapt to different procedures and methods used at each plant.
This is particularly important initially, since most project nuclear activities will be transferred essentially "as is" to E0' (5)
The effectiveness of a dedicated nuclear support organization is enhanced by identity with and sharing of the E0I goals and objectives.
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- :The consolidation of System Energy, LP&L, and AP&L nuclear-organizations within E01 will be an evolutionary process.
The licensees will continue to study possible organizational and' programmatic changesLto enhance corporate objectives and to
' realize'the full' benefits of establishing E01.as_the company responsible for-nuclear operations in the Middle South Electric System.
Obviously, this Application cannot address all of the possible changes that may be made.
However, changes.will be made only after careful analysis.
Moreover, selected licensee programs are governed by formal plans which required NRC review and acceptance or approval.
The staff's review in this regard focuses on the specific plan and the
. technical qualifications of the organization which will be responsible for implementing'the plan.
Changes to.such plans that involve a decrease in effectiveness or level of commitment of the plan require prior NRC review and approval The Quality Assurance Program, the Emergency Plan, and the Security Plan are examples of such programs governed by appropriate regulations.
'Following issuance of the license amendments approving E01 as operator of ANO 1 and 2, Waterford 3 and Grand Gulf Unit 1, E01 will inform the NRC in advance and obtain prior NRC approval of I
planned changes to organizations covered by such formal plans where the changes involve centralization or consolidation of I
functions and/or personnel.
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w It :is envisioned that -this will be necessary for the' first schange' involving centralization or consolidation of functions covered by such formal plans.
For subsequent-changes, E01 will make aidetermination as to whether or not NRC review and prior (approval is required in accordance with'the appropriate provisions of 10 CFR 50.54-or other applicable regulations.
In addition, E01 intends to continue the current System Energy practices of informing the NRC and soliciting their comments on the significant organizational changes affecting Grand Gulf Unit 1.
Special emphasis will be given to any changes involving centralization' occurring as a resultHof the assumption of' operating responsibility by EDI for Grand Gulf Unit 1,
'Waterford 3, and ANO-1 and ANO-2.
F.
Statement of Purposes for the License Amendment The assumption of operational responsibility for Grand Gulf Unit 1, by E01 (along with responsibility for ANO-1, ANO-2, and Waterford 3) will provide benefits inherent to an integrated nuclear operating company.
Some of the expected benefits are as
- follows:
(1)
E01 as en operating company for multiple reactors, will i
have a repository of system nuclear operating expertise and experience.
Presently, there is a wealth of nuclear operations talent spread throughout the Middle South NLSRPT88051701 - 16
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Electric System.
Consolidation of this talent into one company should have a synergistic effect.
The change should enhance the already high level of public safety and cost-effective operations.
(2)
Consolidation of talent not only will result in a merger of expertise and experience for system-wide nuclear operations support, but also will permit the specialization.of expertise in certain areas that might not otherwise be developed if each of the companies continued to operate their: separate facilities.
..(3)
E01 will be.better able to provide a consistent vision for the philosophy of operation of the system nuclear units.
A company responsible for nuclear operations in the Middle South Electric System will allow development of a consistent philosophy which will be specifically designed for nuclear plant operations.
This focused philosophy can be used to maintain excellence in all aspects of nuclear operation.
(4)- As a result of the consolidation, there will be more effective communication and use of system nuclear I
operating experience.
For example, the system-wide nuclear operating company will allow " lessons learned" to be shared promptly, efficiently, and consistently among the units.
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1 (5)
Certain non-nuclear support functions will'become specialized and focused'on the requirements of the
. System's nuclear units and will'thereby be more effective.
L.
L (6)
Bringing the nuclear units in the' system under the l
management of one company will provide a broader base
.and more coinpetitive environment for upper management candidates who are specialized in nuclear power generation.
Further E01, in its role as a system-wide operating company,.should provide an environment in which all employees continue to be motivated toward high performance.
E01, with its expanded responsibilities, will also provide greater opportunity for career i
progression and thus greater opportunity to retain valued employees.
More specifically, as a result of this consolidation, salary structures, career path policies and human resource procedures will be consistent at each nuclear facility operated by E01.
G.
Financial Considerations E01 will be an operating company with no ownership interest in Grand Gulf Unit 1.
EDI, under an operating agreement with System Energy, will be authorized to operate the plant as the agent of System Energy and SMEPA.
Further, as discussed below System Energy and SMEPA are committed under the operating NLSRPT88051701 - 18
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! agreement to provide all funds necessary to continue safe operation of Grand Gulf Unit 1, to; shutdown Grand Gulf Unit 1, if necessary, and to maintain Grand Gulf Unit l'in a safe condition.
all in~conformance with NRC regulations.
System Energy's and
, SMEPA's.finencial. responsibility for Grand Gulf Unit 1 and their sources of' funds to support the facility will remain the same as underEthe present license.
To summarize, the following interrelations will be established by the operating agreement between System Energy, acting for
.itself and as agent for SMEPA, and E01:
1.
E01 will not have any ownership interest in Grand Gulf Unit'1; however, it will have overall responsibility for plant operations.
E01 will operate Grand Gulf Unit 1 in accordance with the Operating License and shall have exclusive responsibility for making safety decisions.
2.
System Energy will retain certain controls over ultimate spending limits, and will retain the authority to direct that Grand Gulf Unit 1 be shut down in an orderly fashion by-E01 (and in accordance with E01's safety judgment).
This retained authority will limit E01's i
spending authority, but will not encumber E01's ability to make operational safety decisions and will have no impact on safe operation of Grand Gulf Unit 1.
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3.
Pursuant to an operating agreement between System Energy y
and SMEPA, as co-owners, all costs for the operation,
,u maintenance, repair, decontamination and decommissioning of Grand Gulf Unit 1 incurred or accrued are liabilities of System Energy and SMEPA when incurred or accrued and are borne'in proportion to their respective ninety percent and ten percent undivided interests in Grand Gulf Unit 1.
Thus, the sources of funds for operating of Grand Gulf Unit I will remain unchanged.
Further, under 10 C.F.R.
6 50.33(f), a full financial qualifications review of either E01 or the co-owners is not necessary as a result of the proposed license amendment.
This is because, under the terms of the operating agreement, all costs associated with operating Grand Gulf Unit-I will be borne by the owners-and accordingly, EDI will have the same financial qualifications as.the present licensees, Those qualifications will be unchanged.
H.
Antitrust Considerations i
'The plan for EDI to operate Grand Gulf Unit I will not impact the existing ownership of Grand Gulf Unit 1 or existing 1
J entitlement to power.
Further, the proposed license amendment to designate E01 as the entity authorized to possess, use and operate
)
Grand' Gulf Unit I will not alter the existing antitrust license
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conditions applicable.to MP&L.
Those' conditions will remain applicable lto MP&L pending NRC action on an unrelated license-amendment request.
'Therefore, this proposed license amendment does not: require statutory antitrust review pursuant to Section 105 of.the Atomic Energy Act and 10 C.F.R. 5 2.101(e).
/
I 1.
-Restricted Data
{
i This' Application does not contain any Restricted Data or other defense information, and'it is not expected that any such
-information will'become involved in the licensed activities.
However, in the. event that such information does become 1:tvolved, E01 agrees that it will appropriately safeguard such information and?it will;not-permit any individual to have access to Restricted DataJuntil the Office of Personnel Management shall have made an
. investigation and report to the NRC on the character, associations and loyalty of such individual, and the NRC shall have determined that permitting such person to have access to Restricted Data will not. endanger the common defense and security.
II.
SPECIFIC INFORMATION REGARDING RELATED ISSUES A.
Emergency Planning Upon approval.of the license amendment to authorize operation of Grand Gulf Unit 1 by E01, E01 will assume authority and responsibility for functions necessary to fulfill the emergency NLSRPT88051701 - 21
planning requirements specified in 10 C.F.R. 5 50.47(b) and Part 50, Appendix E.
No substantive changes will be made to the existing Grand Gulf Unit 1 emergency plan presently implemented by System Energy.
In addition, there will be no changes to the existing Emergency Planning Organization.
Transition plans will be established to ensure that support described in the existing emergency plan will be maintained throughout the transition to E01 and'as needed following.the transition.
Appropriate action will be taken with respect to existing agreements for support from MP&L, as well as from organizations and agencies not affiliated with the licensees, to notify the parties to such. agreements of E01's agency relationship with the owners and E01's responsibility for management and operation of Grand Gulf Unit 1.
This will be accomplished by System Energy prior to the transfer of responsibility.
Following the transfer of employees and operating L
responsibility to E01, emergency planning support will be provided by System Energy and MP&L'as needed.
In essence, to the extent j
that personnel, resources, and facilities are not being transferred to E01, System Energy and MP&L will continue to fulfill selective emergency planning functions.
These functions have been thoroughly reviewed and the required support will be assured by the following measures:
- 1) a support agreement between System Energy and MP&L that will designate E01 as agent for System Energy and 2) as necessary, new support agreements will be-developed between System Energy and E01.
NLSRPT88051701 - 22 L=________-_-
Long-term utilization of System Energy and MP&L resources in these
. areas will be based on cost-effectiveness and existing relationships with'offsite organizations and agencies.
In sum, the pr'oposed license amendment will not impact compliance with the. emergency' planning requirements.
Because the effectiveness of the emergency plan will not be decreased, specific-emergency plan and procedure changes will be submitted to the NRC within 30 days after the changes are made, pursuant to 10 C.F.R. 9 50.54(q) and Appendix E,Section V.
B.
General Design Criterion 17 The amendment to authorize assumption of operating responsibility by E01 involves no changes in the ownership or
-design of the offsite power system for Grand Gulf Unit 1, or in its operation, maintenance or testing.
Upon approval of the i
amendment, MP&L will continue to fulfill its current responsibilities to System Energy with respect to compliance with l
General Design Criterion ("GDC") 17.
l.
GDC 17 specifically requires that there be an assured source I
of'offsite power to the plant.
Pursuant to this requirement, System Energy, E01 and MP&L will maintain and implement procedures and agreements specifying:
(1) the arrangements for provision of l
.a continued source of offsite power and (2) the arrangements for controlling operation, maintenance, repair, and other activities l
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- with res ct to:the: Switchyard.and the, transmission'. lines such that sadequate independentLsources~of offsite power will' continue to be.
providedt i
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' 'In essence,Lthe' written procedures and agreements will k,
' provide foritheLfuture interface between MP&L, System Energy and-R L
E01.
First,LMP&L has committed to providing.offsite power-to e
SystemJEnergy and~t'.E01, as agent for System Energy,- for Grand o
Gulf Unit:1.
Second, the. procedures and agreements will provide for'the~ continuation of current arrangements for the operation and maintenance-of the Switchyard and assaciated transmission f ac il i ti e s'.
The; procedures and-agreements will'also specify that i
MP&L will obtain approval'from E01 prior to-implementing any changes to.the1 equipment.in the Switchyard, which includes the l
Junit oil circuit breakers, switching disconnects, transmission lines and protective relaying which are directly adjacent to the Grand < Gulf Unit 1 protected area.
.In-addition, procedures will i
also?specify that MP&L will obtain concurrence from E01 pr;or to j
implementing any changesLto the 500 kv switchyard equipment i
dedicated.to Grand Gulf Unit 1.
C.
Exclusion Area Upon approva'l of the amendment providing for assumption of ope' rating responsibility by E01, E01 will have authority to determine all activities within the Grand Gulf Unit 1 exclusion area, to-the extent required by 10 C.F.R. Part 100.
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As stated in Section 2.1.2 of the UFSAR, System Energy controls all surface rights within the exclusion area boundary of-Grand' Gulf Unit 1.
SMEPA has a 10 percent undivided interest:in the power block
- area'within the plant exclusion area (a 94-acre tract containing the cooling towers, containment buildings, and other major plant structures) and a 10 percent undivided ownership interest in two very long and narrow strips of land (71 and 5 acres,~respectively) on which the water supply and discharge piping is located.
With respect to surface rights owned by System Energy, and owned by a-.
both. System Energy and SMEPA as-tenants in common, System Energy currently has authority, as SMEPA's general agent, to' exercise appropriate. exclusion area control and to designate an agent for System Energy and SMEPA that will exercise such exclusion area control.
Under the operating agreement to be entered into between System Energy, for itself and as agent for SMEPA, and EDI, it is expressly agreed that E01 will have unrestricted access to the property constituting the Grand Gulf site including all land, facilities, switchyard, equipment and personal property on the site.
The operating agreement also grants E01 authority to exercise complete control over the exclusion area as defined in the UFSAR and to determine all activities in that area.
MP&L owns the 52-acre plant switchyard area, which is partially located within the plant exclusion area.
- However, pursuant to a written agreement between MP&L and System Energy, i
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~ complete control and determine all activities on MP&L property and easements in the exclusion area including exclusion of MP&L personnel and third parties.
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E01 will-have' unrestricted access-to the switchyard arca.
MP&L performs all routine switchyard activities, excluding operation of the main generator breakers and 34.5KV breakers.
All switchyard equipment will be maintained by MP&L.
ESF 12 and the main transformers will be maintained by E01.
E01 is also-responsible for all security functions within MP&L yroperty at the Grand Gulf Nuclear Station.
LThis~au'thority granted to E01 under the operating agreement and theHseparate' agreement between MP&L and System Energy will allow'E01 to control-ingress and egress and to. order an evacuation if necessary.
To the extent practicable, E0I will, of-course,
-exercise this control in such a fashion that MP&L's access to the Switchyard and transmission facilities for proper operation and maintenance 'f the electric systems on the Grand Gulf Unit I site o
will not be unduly restricted.
With respect to the activities unrelated to plant operation that will occur in the exclusion area identified in Section 2.1.2 of the UFSAR, there will be no change.
E01 will assume responsi-bility for the Emergency Plan as discussed above.
In essence, there will be no changes to the Grand Gulf Unit 1 emergency plan other than the fact that it will become the responsibility of E01.
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D.-
Security.
'The proposed license amendment will not impact compliance
-withfthe physical security requirements of 10 C.F.R. Part 73.
'Upon assumption of operating responsibility, EDI will assume y
ultimate responsibility for implementation of all aspects of the present security program.
Appropriate action will be taken with respect to existing agreements for support from MP&L, as well as
.from organizations and agencies not affiliated with the licensees, to notify the parties to such agreements of EDI's agency relationship with System Energy and E01's responsibility for management and operation of Grand Gulf Unit 1.
Changes to the plans to. reflect this transition will not decrease the
'effectiventissfof the plans and wil1 be-submitted to the NRC within 30 days after the changes are made, in accordance with i
10 C.F.R. 6 50.54(p).
E.
Quality Assurance Program The proposed license amendment will not impact compliance with the quality assurance requirements of 10 C.F.R. 50, Appendix B, nor will it reduce the commitments in the NRC accepted quality assurance program description for' Grand Gulf Unit 1.
Upon assumption of operating responsibility, E01 will assume the ultimate responsibility for present-functions associated with the Grand Gulf Unit 1 quality assurance program.
The organization, function and structure of the Grand Gulf Unit 1 Quality Programs i
l NLSRPT88051701 - 27 l
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(department WillinotLbelaffected'by.this licenseLamendment.
m ';'JChanges1to'reflectfthe transition, which-will:be handledLin Jaccordancefwith' 10 C.F.R.L50.54(a). will'notLreduceithe icomm,itmentsxin the' quality assurance program description.
' F.
Final. Safety Analysis Report-
. With thelexception of. areas' discussed in.this license j;
Jamendment' application.the' proposed license amendment will not chang'eLor invalidate information presently appearing'in the' Grand' l'
Changes necessary to1 accommodate the proposed.
GulfL. Unit.1 UFSAR.
_ ilicense amendment.will be11 incorporated -into -the Grand-Gulf Unit 1 UFSA'R following:NRC; approval-of the license amendment application.
l iniaccordance:with'10,C.F.R. 50.71(e).:
- y G '.
?Trainini-1 1The p.roposed-license amendment will'not impact compliance with'the~ operator requalification program requirements of s;3 10fC.F.R..50.54 and..related' sections, nor maintenance of the r
Institute of Nuclear Power Operations accreditation for licensed and non-licensed training.
Upon assumption-of operating-
~
'rsp_onsibil.ity:for Grand Gulf Unit 1, E01 will assume ultimate e
" responsibility ~for implementation of present training programs.
. Changes 1to.the programs to reflect'the transition will.not 4
decrease the: scope of the approved operator requalification program;without the specific authorization of the NRC in y
-accordance with 10 C.F.R. 50.54(1).
- NLSRPT88051701 - 28.
V C
.' )
c I
k;:
H.
Engineerin3_ Support l
Currently the engineering support for Grand Gulf Unit 1 is provided by a dedicated engineering organization that is an integral part of the Nuclear Engineering & Support organization.
Because-the. existing Nuclear Engineering.& Support organization at System Energy will transfer virtually. intact to EDI upon approval of.this license amendment, there will be essentially no change in the engineering support provided and no change in the interfaces between the organizations responsible for engineering support, and maintenance and operations at Grand Gulf Unit 1.
Thus, there will be.no degradation of the engineering support-function and its integration with. maintenance and operations.
After issuance of the license amendment, as evolutionary changes are made to consolidate organizations within E01, E01 will ensure the continued integration of the engineering support function with the maintenance and operation function.
NLSRPT88051701 - 29
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2 III.. Nd LSIG'NIFICANTIHAZARDS. CONSIDERATION. EVALUATI0'N g
PURSUANT:TO 101C;F;R X50.92-c.,
A..
. Proposed Change
. The ; proposed;ameridment. would revise. Facility Operating
- License.No. NPF-29 for: Grand 7 Gulf Onit I to authorize ~E01 to act'
~
Ton behalf of the? owner's.of: Grand : Gulf Unit I with ~ respocsibil1ty-
'.forrand.'contbolfoverythefphysical construction, oper.ation, and
-maintenance;ofsthe., facility.
t-^,
- . B '. :
- Background' 1
. Prioroto' issuanceof this license ' amendment, E0I'will be organized as a' wholly-owned subsidiary of Entergy.
Under the c
- proposedramendment, E01 would assume all: responsibilities for l operating Grand Gulf Unit 1.
Under the current operating.-license for' Grand Gulf. Unit 1, these responsibilities are now held.by I'
System Energy, which also is a wholly-owned subsidiary of Entergy.
This applicationLis being filed simultaneously with a similar j
' application by AP&L to transfer to E01 operational responsibility L
for-ANO-1 and ANO-2, and by LP&L to transfer to E01 operational g
responsibility for Waterford 3.
l '.~
Under the terms of the proposed amendment, the operating license for Grand Gulf Unit I would recognize E01 as the legal t
LNLSRPT88051701 - 30 JLLx.L - _
__._------_-_a._
__._x.
( I entity w'hich will provide the technical and managerial resources for the continued safe operation of the facility, and as the entity with-exclusive authority to make operational safety decisions. 'The proposed license amendment involves no change in
'the ownership'of the facility and no physical changes to.the plant, and no substantive change to operating: procedures.
Funds Lfor~ operation of the plant'will continue to be provided by the
-owners.
'All of the current license conditions will remain in effect and_the Limiting Conditions for Operation, Limiting Safety System.
Settings, and Safety l'm4ts specified in the Technical Specifications will remain unchanged.
While the emergency plan,
-security plan,'and plant operating and emergency procedures may require administrative changes to reflect E01's role as agent for System-Energy and SMEPA and as operator of Grand Gulf Unit 1, no changes will b'e made that decrease the effectiveness of these plans and procedures.
Similarly, while the Quality Assurance Program may require administrative changes to reflect the role of E01, no changes will be made that reduce the commitments in the program.
A transition plan will ensure an orderly transfer of existing emergency preparedness responsibilities to E01.
Written
. procedures and agreements maintained and implemented by E01, MP&L and System Erm_F y wiil clearly ensure continued compliance with 9
Similarly, the operating agreement will ensure that E01 has authority to determine all activities within the exclusion
' area.
'NLSRPT88051701 - 31
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'TheLtechnical.a. qualifications'of E01zto car.ry out its
~
1responsibilitiesEunder the10perating License, as amended, will meet'-or exceed lthe present technical qualifications of System L
l,
Energy.: System 1 Energy-wi.11,. continue toDact.as..the operator of Grand" Gulf UnitL1',fpending'the amendmenttof:the Operating License.
Y When thecamendment becomes. effective, E01'will assume
?'
'tresponsibilitylfor, and control over, theLphysical construction, Toperation, and. maintenance.of the facility.
The present-Grand yL
~
h Gulf Unit--1 NuclearL0perations and-Nuclear Engineering & Support
. staffs'wi_11_be transferred essentially intac't to E01..The
~
- U
- techn'ica11 qualifications of.the E01 Grand. Gulf Unit.1 organization 3
0
.therefore:willibe"at least equivalent to those of the existing o
- organization.
a Thelt'ransferLof operational responsibility for Grand Gulf LunitJ1 from System Energy tole 01 (along with the transfer from AP&Lito'E01 of, responsibility for ANO-1 and ANO-2 and the transfer from LP&LJt' OLE 01 of responsibility for Waterford 3) will provide
. benefits inherent to an' integrated system-wide, management company 1 Some offthe' expected benefits are as follows:
(1)L E01, an operating company for multiple reactors, will
~.have a repository of system nuclear operating expertise 2.
and experience.
Presently, there is a wealth of nuclear operations talent spread throughout the Middle South Electric System.
Consolidation of this talent into one company should have a synergistic effect.
The change will enhance public safety and cost-effective operation.
"-NLSRPT88051701 - 32 z==_____-
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(2). Consolidation of : talent not: only will. result in' a merger-of' expert'ise and. experience-for system-wide nuclear.
s operational. support, but also-will permit ~the.
specialization of expertise in certain areas that might g
L notLotherwise be developed if each1of.the companies continued ~to operate their separate facilities.
~
.(3)
.EDILwill be better.able to provide a. consistent? vision
- for;the' philosophy of operation of the-' system nuclear
~ units.
A1 company: responsible-for nuclear operations in.
the Middle: South 1 Electric System will. allow development.
~
6 of aLconsistent. philosophy which will be specifically l designed for nuclear plant: operations..
This focused philosophy can'be'used to maintain excellence in all-aspects of nuclear operation.
(4)' Asea result of the consolidation, there will be more-effectiveLcommunication and-use of system nuclear operating experience.
For example, the system-wide 1
nuclear operating company will allow " lessons learned" to be shared promptly, efficiently, and consistently among the units.
L L:
-(5) 'Certain.non-nur, lear support functions will become m
specialized and focused on the requirements of the System's' nuclear units and will thereby be more effective.
NLSRPT88051701 - 33
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- 34.-
( 6)
Bringing'the nuclear units in the System under the
. management of one company will provide a broader base and more competitive environment for upper management candidates who are specialized in nuclear power generation.
Further,-E01, in its role as a system-wide.
operating company, should provide an environment in which all employees cont #..nue to be motivated towaro high performance.
E01, with its expanded responsibilities, will also provide greater opportunity for career progression and thus greater opportunity to retain valued employees.
More specifically, as a result of this consolidation salary structures, career path policies and human resource procedures will be consistent at each nuclear facility operated by E01.
C.
Analysis The following discussion provides a specific analysis of the proposed change against the three standards delineated in 10 C.F.R. 6 50.92 and demonstrates that the proposed change involves no significant hazards consideration:
1.
The proposed change will not increase the probability or consequences of any accident previously evaluated.
The technical qualifications of E01 will be at least NLSRPT88051701 - 34
9 i.
5
, equivalent to those of System Energy presently.
Personnel qualifications will remain the same-as those l-L discussedfin the. Technical Specifications and'the UFSAR.
1 The employees.of System Energy, LP&L and AP&L presently I
engaged in.the operation of Grand Gulf Unit 1 Waterford.3, AN0 1 and AN0'2 will become-employees of E01.
The organizational structure of E01 will provide for clear management control and effective lines'of authority-and communication among the organizational units involved in the management, operation, and technical l support of the facility.
As'a' result of the proposed amendment, there will not be physical changes to the facility, and all Limiting Conditions for Operation, Limiting Safety, System Settings,.and Safety Limits specified in the Technical Specifications will remain unchanged.
With the exception of administrative changes to reflect the role of E01, the quality assurance program, the emergency plan, security plan, and training program are unaffected.
Operating agreements will ensure continued compliance with GDC 17 as well as E01 control over all activities within the exclusion area.
Therefore, the proposed changes will not increase the probability or consequences of any accident previously evaluated.
NLSRPT88051701 - 35
. E 2..
The proposed amendment will not create the possibility of a-new or different kind of accident from any accident previously evaluated.
The design and design bases of Grand Gulf Unit I remain the same.
Therefore, the current plant safety analyses remain complete and accurate in addressing the licensing basis events and analyzing plant response and consequences.
The Limiting Conditions for Operation Limiting Safety System Settings, and Safety Limits are not affected by the proposed amendment.
With the exception of
-administrative changes to reflect the role of E01, plant procedures are unaffected.
As such, the plant conditions for which the design basis accident analyses.
have been performed are still valid.
Therefore, the
_ proposed amendment cannot create the possibility of a new or different kind of accident than previously
. evaluated.
3.
The proposed amendment will not involve a reduction in a margin of safety.
Plant safety margins are established through Limiting Conditions for Operation, Limiting j
Safety System Settings, and Safety Limits specified in l'
the Technical Specifications.
Since there will be no change to the physical design or operation of the plant, j
there will be no change to any of these margins.
The proposed amendment therefore will not involve a I
reduction in a margin of safety.
NLSRPT88051701 - 36
\\
D.
Conclusion l-Based upon the analysis provided herein, the proposed-l ll amendment will not increas.. the-probability or consequences of an 1:
l
. accident previously evaluated, create the possibility of a new or L
different kind of accident from any accident previously evaluated, or involve a reduction in.a margin of safety.
Therefore, the proposed. amendment meets the requirements of 10 C.F.R. 50.92(c) and does not involve a'significant hazards consideration nor an-unreviewed safety question.
NLSRPT88051701 - 37
r,-r pg
. ca ~
I..
g ENDORSEMENT-AND CONSENT MP&L, present1y'a'co-licensee,-hereby endorses and consents Lto this application filed under oath or affirmation by
_(Later) and the proposed assumption of operating and licensing responsibilities for Grand Gulf Unit 1 by E01 as described above.
(Later) i NLSRPT88051701 - 38
o
- ENDORSEMENT AND CONSENT System Energy, presently a co-licensee, hereby endorses and consents to this application filed under oath or affirmation by W.
T.
Cottle, Vice President, Nuclear Operations of System Energy and the proposed assumption of operating and licensing responsibilities for Grand Gulf Unit I by E01 as described above.
l
~
J saph U,.
B1ount Vi e President
.e 'al & External Affairs stem Energy Resources, Inc.
-NLSRPT88051701 - 39
-;s.;
. 40 -
- ENDORSEMENT AND CONSENT SMEPA, presentlyLa'co-licensee, hereby endorses and
. consents'to this application filed'under oath or affirmation by (Later)-
and the proposed
. assumption.of. operating and1 licensing responsibilities for Grand Gulf Unit-1.by'E01 as' described above.
(Later)
NLSRPT88051701 - 40 2 x __ _ _ __.
.S.
4.;, :.
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PROPOSED ENTERGY.0PERATIONS, INC.
ORGANIZATION CHART BOARD OF DIRECTORS L
CEO & PRESIDENT' m
t i
HUMAN ACCOUNTING EXECUTIVE LEGAL &
NUCLEAR-RESOURCES &
VICE PRESIDENT-EXTERNAL ASSURANCE &
! ADMINISTRATION TREASURER
& CHIEF AFFAIRS FUEL OPERATING PROCUREMENT OFFICER l
ENGINEERING OPERATIONS GRAND GULF AN0 WATERFORD 3 SUPPORT OPERATIONS OPERATIONS OPERATIONS
' NOTE: Quality organizations for each plant have access to President & CEO and Executive Vice President and C00 on matters related to Quality, i
NLSRPT88051701 - 41
p
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. J b SSISSIPPI POWER & LIGHT COMPANY o
t SYSTEM ENERGY RESOURCES, INC.
' SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION
=
=
DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 ISst4.MCd obk FACILITY OPERATING LICENSE
&thedto
\\icanse a-m<9persdidgp(, foy)
+
ggy.
l License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
The b?f::ti:r f:r 'f:::::
A.
" !:d by Mississippi Power & Li Company (MP&L), for itself and Middle South Energy. Inc., (ght now renamedSystemEnergyResources,Inc.(SERI))andSouh Mississippi Electric Power Association (hereinafter referred to as the licensees) complies with the standards an requi re'-
coded /d ments of the Atcmic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I, g4 and all required notifications to other agencies or bodies have been duly made; w
i B.
Construction of the Grand Gulf Nuclear Station, Unit 1 (the facility), has been substantially completed in conformity with Construction Pemit No. CPPR-118 and the application, as amended,
?
the provisions of the Act, and the regulations of the Comission; C.
The facility will operate in confomity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D.
below);
D.
There is reasonable assurance:
(i)thattheactivitiesauthorized by this operating license can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below);
E. ?!y:t:r En:r;y 9 :rre::. !=. (SERI)* is technically qualified M?P to engage in the activities authorized by this operating license
.h*MO Muo dS 3. Tog in accordance with the Commission's regulations set forth in 10 CFR Chapter I; ged/~/or-S HM is authorized to actg:F ftreli and for SMEPA and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
Amendment No. 27 l
7 L
__.____._____m-m.______
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'F.
The licensees have satisfied the applicable provisions of 10 CF!t Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;-
4
~GL The is'suance of this license will not'be' inimical to the comon
. defense and security or to the health'and safety of the public; q-H.~
After weighing the environmental, economic, technical, and ~
other benefits 2cffthe facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating. License No. NPF-29.. subject to. the conditions,
.for p,rotection of the environment set forth in the. Environmental
' Protection Plan' attached as' Appendix B, is in accordance with
.10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied;;and I.
' The receipt, possession, and use of source, by-product and special nuclear material as authorized by this license will be in
,' 40.~ and. 70.accordance-with the Comission's regulations in 10 CFR Pa 2.-
' Based'on the. foregoing findings regarding this facility and. pursuant to Commission'0rder CLI-84-19, dated October 25, 1984 License NPF-13.-
gj #
7' as amended, is superseded by this Facility Operating License NPF-29 10 which is hereby. issued to ee ississippi Power & Light Company,-
l 1-System Energy Resources 'Inc., and South Mississippi Electric Power iation to read as follows:
4 A.
This ifcense applies to the Grand Gulf Nuclear Station (GGNS),.
Unit 1, a: boiling water nuclear reactor and associated equipment L
(the facility), owned by System Energy Resources Inc., and South
[fg/grhgpc,'
~
' Mississippi Electric Power Association and operated by Sy:tr
" r;; S:::r ::. Ire. The facility is located in Claiborne l
3 County, Mississippi, and is described in the licensees' " Final
. Safety Analysis Report," as supplemented and amended, and in the licensees' Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, g-the Comission hereby licenses:
T Q
' ors,1hc.h (1) Sy b 5:r gy "::: r:::, In:. (EE"!) pursuant to Section 103
)
of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this license;.
(2) System Energy Resources, Inc., and South Mississippi Electric Power Association to possess the facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this license; Amendment No. 27, l
,.i
~
~
- (
(3) 49E*f, pursuant to the Act.and 10 CFR part 70, to receive, possess and use any any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;_
~
EOJ (4)AMS pursuant to the Act and :10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
, pursuant to the Act and 10 CFR Parts 30, 40, and 70,_to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
('
(7) (a) SERI is authorized to transfer up to 15 percent of its 90.0%
ownership share in Grand Gulf Nuclear Station, Unit 1 (GGNS
' Unit 1), to certain equity investors identified in the submissions of October 31, 1988 and November 11, 1988, and at the same time to lease back from such purchasers such interest sold in the facility.
The term of the lease is for approximately 26 years subject to a right of renewal.
Such sale and leaseback transactions are subject to the condition that lessors and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over (i) GGNS Unit 1, (ii) power or energy produced by GGNS Unit 1, or (iii) the licensees of GGNS Unit 1.
Further, any rights acquired under this authorization may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the Commission's regulations.
For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently amended,.are fully applicable to the lessors and any successors in interest to those lessors, as long as the license for GGNS Unit I remains in effect.
SF-OL - 3 Amendment No. 54 l
___.______.______.____n__.___-__u._.
g.
,y l
- 3a -
(b). SERI is required to notify the NRC in writing prior ~ to l'
any change in (i) the terms or conditions of any new or existing sale or lease agreements executed as part of the above authorized financial transactions, (ii).the GGNS Unit 1. operating agreement, (iii) the existing.
property insurance coverage for GGNS Unit 1 that would-materially alter the representations and conditions set forth in'the staff's' Safety Evaluation. Report u
dated December 19,:1988 attached to Amendment No. 54.
In addition, SERI is required to notify the NRC of.any action by a. lessor.or other. successor in interest to-SERI.that may have an effect on the operation of the-
= facility.
u" C..
The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth
'in 10 CFR Chapter I and is subject to all applicable provisions
.of the Act and to the rules, regulations, and orders-of the c
Commission new or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level BOI gSE4f is authorized to operate the facility at reactor core power-levels not in excess of 3833 megawatts thennal (100%
power) in accordance' with the' conditions. specified herein.
(2) ' Technical Specifications The Technical. Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, i
as revised through Amendment No. '60 are hereby incorporated into this license.
shall operate the facility in accordance with the Tectnical Specifications and the Environmental Protection Plan.
C 5
5 fckrgy &9 erd oN Xoc
/,
NLSSF-OL - 4 Amendment No. 60)
O E
(3) Antitrust Conditions MP&L and SERI shall comply ith the antitrust conditions delineated in Appendix C.
is au~ thorized to transfer its/
. rights to-possess, to use and to operate the facility to q provided however, that until further authorization of the Com-mission, MP&L and SERI.shall continue to be responsible for compliance with the obligations imposed on the licensees in go y these antitrust conditions, and provided further that #. ret h accepts the right to possess, use and operate the facility subject to the outcome of the pending separate antitrust review of the' antitrust consideraHaae of this tran<fer.
' %Ws5Aw Eccqdts de edht~t passeas,%e (kes /, &
(4) Ind(w....nt verification of Staff Performance and Other Piant Act'vities (Section 13.4, SER, 55tR 92) 80.[
(a)j$6A4-shall establish a subcommittee of the Corporate Safety Review Comittee to review and evaluate the:
(i) Status and readiness of the plant and systems needed
- to support intended modes of operation and/or testing; (ii)Readinessofpersonnel.toconductintendedoperation and testing; s
(iii)Moraleandattitudesofplantpersonnelthathavea bearing on safe plant operation; (iv)Pastperformanceinplantoperationsandadherence to procedures and administrative controls; L
(v) Changes in current organization with regard to experience and qualifications of plant management and supervisory personnel since the last evaluation; (vi)ResultsandeffectivenessofthePlantSafetyReview Committee (PSRC),
(vii) Status of plant as compared to other BWR startups based on the subcommittee's knowledge and experience.
Reviews shall be conducted prior to exceeding 50 percent of full power and within 30 days following completion of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run. The subcommittee shall be composed of a minimum of three professionals not employees of 6544-with experience which will be responsive to the concerns /,
presented above.
In conducting these evaluations, the Amendment No. 27).___
l
i i
5 p
subconnittee shall conduct interviews of representatives
'of all levels of plant staff management. The subcommittee shall report directly to the Chairman of the Corporate Safety Review Connittee and, in turn,y shall submit the report of these reviews to NRC.
gf (b)' The Plant Safety Review Connittee shall review all Unit 1 Preoperational Testing and System Demonstration activities performed concurrently 'with the Unit
- Startup Test Program to assure that the' activity will not affect the safe per-formance of,the portion of the Unit 1 Startup Program being perforined. The review shall address, as a minimum, system interaction.. span of control, staffing, procedures, security and health physics, with respect to performance of the activities concurrent with the portion of the Unit 1 Startup Program being performed.
(5) Deferred Preoprerational Deficiencies EOZ
/6&M-shall~ satisfactorily resolve those deficiencies which were
' deferred from the preoperational testing program on a schedule that shall assure that the capability of a system required to be operable by Technical Specification is not degraded.
6): Soil Structure Interaction (Section 3.7.1, SER, SSER
)
(
g; Prior.to startup following the first-refueling outage,ASEM shall l
complete structural modifications, if' required, as a rle uit of the NRC staff's completion of its review of MP&L* responses.
(7) Seismic Instrumentation (Section 3.7.4, SER, SSER #2)
' Prior to startup following the first refueling outage, the installation of triaxial strong motion accelerometers on reactor supports shall'be completed.
(8) MasonryWalls(Section3.8.3,SER,SSER#2) foZ Prior to startup following the first refueling outage,A&&A4-shall I
complete structural modifications, if required, as a result of
)
the NRC staff's completion of its review of the MP&L.respante_ to IE Bulletin 80-11.
j ggg g
gfL
- The original license authoriled Mississippi Power & Light Company (MP&L) to operate the facility.T Consequently, there are certain historical n
references to MP&L in this license.
p/ SEfLK /k phh? f oks 2s OfhD L
y Amendment No. 27, l
a
_ _ _ _ _ _ _ = _ - _ _ _ _
b
g 6
(9)' Dynamic Testina (Section 3.9.2, SER,' SSER'#2, SSER #4, SSER fS) shall conduct vibrational measurement and inspection pro-l orams during preoperational and. initial startup testing in
.accordance with the guidelines of R.G. 1.20. " Comprehensive
. Vibration Assessment Procram for Reactor Internals During Pre-operational and Initial Startup Testing," for prototype reactors.
An evaluation report demonstrating satisfactory results shall be provided to the NRC for review and approval no later than 6 months after completion of the startup test program.
(10) Dynamic Qualification (3.10. SER, SSER #1, SSER f2, SSER #4, 55ER #5)
(a) Prior to startup following the first refueling outage.
l
~
. shall complete any modifications or replacement of equipment found necessary as a result of the fatigue evaluation. In 8
Ine interim 366M shall document the occurrence of every l
safety relief valve actuation into the suppression pool; the associated cumulative damage factors shall be calculated typical. representative equipment and kept up-to-date; and GERf shall report to NRC any malfunction of equipment l
. that occurs due to any safety relief valve discharge.
(b) shall perfom an in-situ test of the Hi h Pressure l
I
-Core Spray (HPCS) service water pump and eva uate the effects of flow induced vibration on the HPCS service water pump. This evaluation shall be provided to the NRC for review and_acoroval. Prior to startup following the first refueling outageT, GEM shall. complete all modifications as I
a result of the NRt staff's review of the test results and evaluation.
EW
\\
(c)
Prior to actual use in fuel handling operations, @in-vessel shall l
qualify the fuel-handling and auxiliary platfom, rack, and storage container for defective fuel.
(11) Environmental Qualification (Section 3.11, SER; SSER #1; Appendix H, 55ER f2; 55ER fS)
Prior to March 31,198$
shall environmentally qualify all l
i electrical equipment as required by 10 CFR 50.49.
(12) Surve111ance of Control Blade (Section 4.2.3.14, SER)
)
~
Within 30 days after plant startup following the first refueling
% sha 1 comply with items 1, 2 and 3 of Bulletin No.
I j
Eof outage @d submit a written response to NRC on item 3.
79-26 an i
1 j
Amendment No. 27 l
3
f 7
(13) Core Stability Analysis and Prohibition of Natural Circulation j
I (Section 4.4.1, SER)
(a) Prior to startup following the first refueling outage,/ pee l
l shall submit a new core stability analysis for operation beyond cycle 1.
(b) Natural circulation shall be prohibited as an operating mode.
(14)LoosePartsMonitorino(Section4.4.1,SER) foI*
Prior to startup following the first refueling outage,AHet-l shall submit an evaluation of the Loose Parts Monitoring System to address conformance to R.G. 1.133, Rev.'1, dated May 1981.
(15) Scram Discharoe Volume (Sections 4.6, SER)
EDZ Prior to startup following the first refueling outage, l
shall incorporate the following additional modification /\\ SERT ns into the scram discharge volume system:
9 (i) Redundant vent and drain valves, and (ii) Diverse and redundant scram instrumentation for each instrumented volume, including both delta pressure sensors and float sensors.
(16)ContainmentPurae(Section6.2.4,SSER#5)
EDI Prior to startup following the first refueling outage,ASEM shall provide for NRC review a reevaluation of'the need to use the con-tainment purge mode of the containment cooling system. This study should include, but is not limited to, data gathered during the first fuel cycle related to airborne activity level (ALARA),
nv r=11 enntainnent air anality and personnel access to contain-ment. Basedontheabovecitedstticy,)pE#tshallproposethe gg purge criteria to be used for the remainder of the plant life.
(17) Containment Pressure Boundary (Section 6.2.8, SER)
Etr Prior to startup following the first refueling outage,AGERt shall replace the feedwater check valve disc with a disc made from a suitable material.
(18) Pressure Interlocks on Valves Interfacing at Low and Hich Pressure (Section 6.3.4 SSER #2)
Prior to startup following the first refueling outage, the licensee shall implement isolation protection against overpressurization of the low pressure emergency core cooling systems (RHR/LPCI and LPCS) at the high and low pressure interface containing a check valvt and a closed motor-operated valve.
Amendment No. 27 l
3
w u (19) IE Information Notice 79-22, Qualification of Control System
-(Section 7.6.C, 5ER, 55ER F2)
Prior. to startup following the first refueling outage,ASE4+ shall complete any design changes found necessary as a resul't' of this review.
(20) Standby Service Water System (Section 9.2.1 SER, SSER #2)
(Deleted)
(21) Spent Fuel Pool Ventilation Systen (Section 9.4.2, SER, SSER #2)-
If spent irradiated fuel is placed in the spent fuel pool prior to installation and operability of the safety related backup fuel pool cooling pump room coolers, the plant shall be placed in shutdown condition and remain shutdown with the RHR system dedicated to the fuel pool cooling mode.
(22)RemoteShutdownPanel(Section9.5.4.1,SER,SSERv2)01 2
Prior to startup following the first refueling outage, AGE +f shall install electrical isolation switches between the control room and the Division I remote shutdown panel.
(23) Fire Protection Program (Section 9.5.9, SER) 26 gER+ shall maintain in effect and fully implement all provisions of the approved Fire Protection Plan.
In addition,
"% shall maintain the fire protection program to meet the l
intent of Appendix R to 10 CFR Part 50, except that an oil Ear c 11ection system for the reactor coolant pump is not required.
I l
SF-OL - 8 Amendment No. 34 l
3
.__ n - -
a g
4 _
- 9' (24) Interplant ' Communication Systems (Section 9.6.1.2, SER, SSER #2,
-55ER #4, 55ER f5)
Tests of the communication systems used to mitigate the con-sequences of-an event and attain a safe plant shutdown shall be completed during preoperational and startup tests. An evaluation of the test results shall be provided for NRC review within 90 days after test. completion. Any system modifications found necessary as a result of NRC review shall be completed prior to startup following the first refueling outage.
(25)'ReliabilityofDiesel-Generators (Sections 8.3.1, 9.6.3 through 9.6.7, 5ER, 55ER f2,-55ER f4, 55ER #6)
(a) Prior to startup following the first refueling outage, a heavy duty turbocharger gear drive assembly shall be installed on all EMD diesel-generators.
o fC.Z (b)j p 5M shall. comply with TDI emergency diesel generator require-l ments specified in Attachment 2 to this license.
l (26) Turbine Disc -Inteority (Section 10.2.1, SER, SSER #1)
E0Z A4EM~ shall ultrasonically inspect-the bores and keyways of the low I
pressure turbine discs for indications of cracking prior to exceeding gs 50,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of operation. All unacceptable indications and their dispositions shall be reported prior to startup for the next cycle of operation..These-inspections shall. continue on a 50,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> interval a
until:the potential ~for turbine disc cracking has been assessed and an acceptable alternate inspection schedule has been established.
(27) Circulating Water System (Section 10.4.5, SER) 4 E0Z i
A SERT shall not fill the Unit 2 circulating water system (including I
the natural draft cooling tower basin) until Unit 1 flooding concerns related to this system are resolved to the satisfaction of the NRC staff.
l (28) Advisor to the Vice President shall have on its nuclear operations staff, one or more corporate l
management officials or advisors (who may be either permanent employees or contracted consultants) who have substantial commercial nuclear power plant operating management experience and who will advise on all J
l decisions affecting safe operation of the plant. This requirement shall be in effect until the plant has accumulated at least 6 months at power levels above 90% of full power.
l Amendment No. 27 l
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(29). Operating Shift Advisor (Section 13.1.2, SER)
-]
At least one individual on each operating shift shall have substantive previous BWR operating experience, including startup and shutdown of a BWR and under conditions that one might expect to.
encounter during the initial startup and power escalation at the Grand Gulf plant. This. individual is not recuired to be licensed on r-r Grand Gulf Unit I and need not be ap employee, but as a minimum
~
l-shall be retained on a contract basis.to act as a consultant or' advisor to the GGNS shift crew. Such an experienced person shall be assigned to each operating shift until the plant achieves and demonstrates full power operation.
(30) Training Instructors (Section 13.2, SER)
[ DELETED]
(31) Initial Test Program (Section 14, SER) 4E E shall conduct the ding initial test program (set forth in Section 14 of,E"!':-Final Safety Analysis Report, as f
amended) without making any major modifications of this program unless such modifications have been identified and have received-prior NRC approval. Major modifications are defined as: EGZh (a) Elimination of any test identified in Section 14 of/rSE W 5 Final Safety Analysis Report, as amended, as being essential; (b) Modification of test objectives, methou, or accestance criteria AnalysisReport,asamended,asbeingessentialginalSafetyf for any test identified in Section 14 of 45%%
(c) Performance of any test at a power level different from that described in the program; and (d) Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized powerlevel).
i SF-OLI-10 Amendment No. 51, I
s ;.
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Operation of the plant in the partial feedwater heating. mode for L
the purpose of extending the normal fuel cycle shall be prohibited until analyses which justify that operation are provided to and approved by the NRC staff.
.(33)NUREG-0737 Conditions (Section22.2) shall complete the following conditions to the satisfaction of the NRC. These conditions reference the appropriate items in' Section 22.2, "TMI Action Plan Requirements for Applicants for Operating Licenses", in the Safety Evaluation Report and Supple-ments 1, 2, 3, 4, and 5 NUREG-0831.
(a) Control Room Desian Review (I.D.1, SER; Appendix E, SSER #2, 55ER f4, 55ER #5)
__207 Prior to startup following the first refueling outage, %
~
shall demonstrate the ability to maintain an " effective temperature" condition of 85'F or less in the remote shut-down panel (RSP) room for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with an ambient outdoor temperature of at least 95'F.
1 (b) Trainino Durino Low-Power Testino (I.G.1, SER)
EQZ~
Prior to restart following the first refueling outage, SERfA shall complete the additional training and testing related to TNI Action Plan I.G.1 as described in Section 2.3 of the MP&L submittal dated April 3, 1986.
(c) Post.AccidentSamp11no(II.B.3,SER,SSER#1,SSERf4, 55ER f5)
E01
- Prior to startup following the first refueling outage, SEMA shall incorporate the additional requirements into the procedure for relating raclionuclide gaseous and ionic species to estimate core damage as discussed in Section II.B.3.1 of SSER #4.
(d) H drocen Control (Section II.B.7,.SER, SSER #2, SSER #3,
- 4, 55ER #5)
E0Z
)
(1) During the first cycle of operation.f9Ett shall i
i maintain a suitable procram of analysis and testino of the installed hydrogen ignition system. M 60Z shall submit to the NRC quarterly reports on th C t
status of their research programs.
1 Amendment No. 27) l
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'g SW (a)/19tM shall amend its research program on hydrogen I
control measures to include, but not be limited to, the following items:
1)
Perfom containment sensitivity analysis to detemine the adequacy of the hydrogen control system for a spectrum of degraded core accidents s
including the determination of accident sequences P
for which equipment survivability is assured; 2)
Research to investigate the conditions leading to-
.and consequences resulting from hydrogen combus-tion in the wetwell and containment. Testino shall be performed in a larger scale facility such as the one-quarter scale test facility proposed by MP&L; 3)
Research to investigate the conditions leading to and consequences resulting from hydrogen combustion in the drywell; 4)
Confirmatory tests on thermal response of sel'ected equipment exposed to hydrogen burns.
fdf (b)jl 9ERf shall perform feasibility studies to examine the options for enhancino equipment survivability for essential equipment located in the vicinity of the suppression pool or other regions subjected to severe
^
environments. The options to be studied in such feasibility studies shall include thermal shielding, additional cooling, and relocation of essential
.gpipment.
e I
(2)
(a)/SEei shall complete its research program on hydrogen control to show that the' hydrogen control system will perform its intended function in a manner that provides adequate safety margins. This research program shall be completed on a schedule which reflects the require-I ments of 10 CFR 50.44.
(b) If it is determined that plant modifications are required to obtain NRC approval that an adequate hydrogen control system for Grand Gulf is installed, then thes e a.Sfications shall be completed on a l
schedule whkh. approved by the NRC.
l; (e) Instrumentation for Detection of Inadeouate Core Coolino (II.F.2, SER, 55ER #2) fez l
h A-4EQt shall submit a report addressing the analysis performed by the BWR Owners' Group regarding additional instrumentation relative to inadequate core cooling and shall implement the Amendment No. 27,
- f 4[
f staff's~ requirements after the completion of the staff's review of this report.. These modifications shall be completed on a schedule acceptable to the staff.
'(f). Modification of Automatic Depressurization System Logic -
g
-Feasibi h ty for Increased Diversity for Some Event Sequences l
(II.K.3.18, SER, SSER, #2, SSER #4) eof Prior to startup following the first refueling outage, GER){
shall provide, for NRC review, justification for the timer delay setting's, revisions to the emergency procedures covering-the use of the manual inhibit switch, proposed Technical Specification surveillance procedures for the timer and switch, and shall implement alternative logic modification (Option 4) of the automatic depressurization system.
(g) Qualification of ADS Accumulators (II.K.3.28, SSER #5)
EoZ Prior to startup following the first refueling outage, et#ta shall perform an. integrated leak test on the ADS air system, perform sampling to establish instrument air quality, provide instrumentation to monitor ADS air receiver pressure, establish suit:ble surveillance procedures for the ADS air system and providt proposed changes to the Technical Specifications associated wdh the surveillance procedures.
(34) SRV Test Program (Section A-39, Appendix C, SER, SSER #1, SSER #2)
During Cycle 1, an inplan SRV test program sha. I be carried out to confirm that thm containment building response to SRV loads is acceptable.
ResJits of these tests shall be provided to NRC no later than four aonths after test completion.
(35) Post-LOCA Vacuum Breaker Position Indicators EOZ Prior to startup following the first refueling outage A6Ett shall install position indicators with redundant indication and alarm in the control room for the check valves associated with the drywell post-LOCA vacuum breakers.
(36) Emergency Response Facilities (Generic Letter 82-33, NUREG-0737 Supplement 1, SSER #5) for A 6ftr.shall complete the emergency response capabilities, as required l
by Attachment 1, as revised through Amendment No. 53 to this license.
(37) Evaluation of Licensee's Technical Specification Problem Sheets (Section 16.3, SSER #6)
EOZ Prior to startup following the first refueling outage p shall implement the following modifications:
SF-OL - 13 Amendment No. 53, l
?
l.4.I 14 k.
.(a) Include an emergency overrin of the test mode of the _
Division'3 HPCS diesel generator to permit response to emergency signals and to reture the control of the diesel generator to the emeroency standby mode.
(Item No. 333, T.S.4.8.1.1'.2.d.12.b)
.(b). Provide' the second level undervoltage protection for.-
Divisian 3 power supply (Item No ' 373, T.S. Table 3.3.3-2).
(c)
Incorporate a bypass' or coincident logic in all Division 1 and 2 diesel generator protective trips, except for trips on diesel engine overspeed and generator differential current (Item No. 808, T.S. 4.8.1.1.2.d.16.d).
(38) Control Room Leak Rate (Section 6.2.6, SSER #6)
' idZ AdlEM shall operate Grand Gulf Unit 1 with an. allowable control I
room leak. rate not to exceed 590 cfm. Upon restart of construc-tion of Unit 2 control room, will be pemitted to operate at l
a leak rate of 760 cfm as ted in SSER No. 6.
(39)TemporarySecondaryContai Boundary Chance For a' period of time not to exceed 144 cumulative hours, the provisions of Specification'3/4.6.6.1 may be applied to the rial-k road bay' area including the' exterior railroad bay door on the-auxiliary building in lieu of the present secondary containment boundaries that isolate'the railroad bay area. While the rail-road bay. area is being used as a secondary containment boundary, the railroad bay door may be opened for the purpose of moving trucks. in and out provided:'the four hour limitation in ACTION a
'of Technical Specification 3.6.6.1 is reduced to one hour. A i
fire watch shall be' established in the railroad bay area while
~
the door is being used as a secondary containment boundary.
I (40) Temporary Ultimate Heat Sink Chance With the plant in OPERATIONAL condition 4. SSW cooling tower basin A may be considered OPERABLE in acecrdance with Technical Specification 3.7.1.3 with less than a 30 day supply of water (without makeup) during the time that SSW basin B is drained to i
replace its associated service water pump provided:
(a) SSW basin A water level is maintained greater than or equal to 87".
(b) At least two sources of water (other than normal makeup with one source not fiependent on offsite power) are available for makeup to SSW basin A.
This license condition may remain in effect until plant startup following the outage scheduled for fall 1985.
Amendment No. 27, l
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D.:.Th'e' facility required exemptions from certain requirements of
~
-Appendices A and'J to 10 CFR Part 50 and from certain requirements of
[
10 CFR Part 100.. These include:
(a) exemption from General' Design Criterion 17 of Appendix A until startup following the first' refueling outage, for (1) the' emergency override of the test mode for the
, Division 3-diesel engine, (2) the second level undervoltage protection for the Division ~ 3 ' diesel engine, and (3) the generator ground over 31 current trip. function for the Division 1 and=2 diesel generators i
(Section 8.3.1 of'SSER #7) and (b) exemption.from the requirements'of-1
' Paragraph 'III.D.2(b)(ii) of Appendix J:for the containment airlock testing following normal door opening when containment integrity is not required (Section 6.2.6 of SSER #7). These exemptions are authorized by law and will'not endanger life or property or the common defense and 4
security;and are otherwise in the public interest.
In addition, by exemption' dated December 20, 1986, the Commission exempted licensees from 10 CFRjl00.11(a)(1), insofar as it incorporates the definition of -
exclusion area in 10 CFR 100.3(a), until April 30, 1987 regarding
- demonstration of authority to control all activities within the
' exclusion area (safety evaluation accompanying Amendment No. 27 to License.(NPF-29). -This exemption is authorized by. law, and will not present an undue risk to the public health and safety, and is consistent with'the common defense and security.
In addition, special circumstances'havesbeen found justifying the exemption. Therefore, these exemptions'are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent
- authorized herein, in conformity with the application, as amended, the
- provision of the Act and the rules and regulations of the Commission.
E.
The. licensee shall fully implement and maintain in effect all p'rovisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency _ plans including amendments made pursuant to provisions of the Miscellaneous Amendments
-and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 F
and 27822) and to the authority of 10'CFR 50.90 and 10 CFR 50.54(p).
~
d The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Grand Gulf Nuclear Station Physical Security Plan," with revisions submitted through September 1, 1987;
" Grand Gulf Nuclear Station Guard Training and Qualification Plan,"
'with revisions submitted through March 10, 1987; and " Grand Gulf Nuclear Station Safeguards Contingency Plan," with revisions submitted through August 25, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
JDZ F. /jSERF shall report any) violations of the requirements contained inSec twenty-four (24) hours.
Initial notification shall be made in accordance with the provisions of 10 CFR 50.72 with written follow-up in accordance with the procedures described in 10 CFR 50.73(b), (c),
and(e).
Amendment No. 44 SF-OL 15'
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ss 16 f
G.
The licensees shall have and maintain financial protection of such type and in such amounts as the Comission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
This license is' effective as of the date of issuance and shall expire at midnight on June 16, 2022.
FOR THE NUCLEAR REGULATORY COMMISSION R
/
W rold R. Denton, Director Office of. Nuclear Reactor Regulation Attachments:
- 1.
2.. Appendix A - Technical Specifications (NUREG-0934) 3.
Appendix B - Environmental Protection Plan 4.
Appendix C. Antitrust Conditions Date of-Issuance: November 1, 1984 O
4
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18 NOVEMBER 1,1984 p,-SE4E-shall complete the following requirements on the schedule noted below:
Emergency Response Facilities (Generic Letter 82-33, NUREG-0737 Supplement 1, 55ER #5)
KOr A 6E*F shall implement the specific items below, in the manner described in MP&L letter (AECM-83/0232) dat'ed April 15, 1983, as modified in MP&L letter (AECM-83/0486) dated August 22, 1983, no later than the following specified dates:
(a) Safety Parameter Display System (SPDS)
(1) Submit a safety analysis and implementation July 1985 plan to the NRC (2) SPDS fully operational and operator trained Prior to startup following first refueling outage, (b) Detailed Control Room Design Review (DCRDR) g (1) Submit a program plan to the NRC December 1984 (2) Submit a summary report to the NRC including July 1986 a proposed schedule for implementation (c) Regulatory Guide 1.97 - Application to Emergency Response Facilities (1) Submit k. report to the NRC describing how the February 1985 -
requirements of Supplement 1 to NUREG-0737 have been or will be met.
(2) Implement (installation or upgrade)
Prior to startup requirements of L G. 1.97 with excaotion following first of flux monitoring and coolant lei:.; monitoring.
refueling outage.
i (3) Implement (insta11atioh or upgrade)
Prior to startup requirements of R.G.1.97 for coolant level following second monitoring.
refueling outage.
(4) Implement (installation or upgrade)
Prior to startup requirements of R.G.1.97 for flux monitoring.
following fourth refueling outage (d) Upgrade Emergency Operating Procedures (EOP's)
~
(1) Submit a Procedures Generation Package to the April 1985 NRC.
Amendment No. 53 l
3 lL-____-______-_--__
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(2) ~ Implement the upgraded E0P's Prior to startup following the first refueling outage (e)' Emergency Response Facilities (1)
Technical Support Center fully functional Prior to startup with exception of Regulatory Suide 1.9'/
following the i
implementation first refueling outage (2)
Operational Support Center fully functional Prior to startup with exception of Regulatory Guide 1.97 following the implementation first refueling outage (3)
Emergency Operations Facility fully Prior to startup functional with exception of Regulatory following the Guide 1.97 implementation first refueling
(
outage 4
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i Transamerica Delaval Inc. (TDI) Diesel Generator 4
Maintenance and Surveillance Requirements (NUREG-1216.'Auoust 1986) l '.
Maintenance and Surveillance Program shall implement and maintain in effect the provisions of the main-l tenance and surveillance program for the TDI emergency diesel generators at GGNS Unit 1 as identified in the MP&L letter dated July 18, 1986 (AECM-86/0172) and as approved in the staff's Safety Evaluation Report attached to the NRC letter dated December 9,1986, subject to the provisions of paragraphs 2 and 3 below.
2.
Chances-Ed.2;
/l4E*imaymakechangestotheapprovedmaintenanceandsurveillance l
program without prior approval of the Commission provided the changes do not adversely affect the operability or reliability of the diesel generators or involve changes in the Phase 1 Surveillance requirements of
(
paragraph 3 below or otherwise change license conditions or Technical Specifications or result in,an unreviewed safety question as defined in g
-C 10 CFR 50.59. ASEM shall maintain in auditable form, a current record of l
all such changes, including an analysis of the effects of the change on
. diesel generator operability and reliability, cnd shall make such_ records available to NRC inspectors upon request. All changes to the program shall be. reported annually to the Director of the Office of Nuclear Reactor Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).
-3.
Phase 1 Component Surveillance Requirements
'l b shall comply with the following requirements:
3.1 Connectino Rods Connecting rod assemblies shall be subjected to the following inspections at each major engine overhaul *:
a.
The surfaces of the rack teeth shall be inspected for signs of fretting.
If fretting has occurred, it shall be subject to an engineering w aluation for appropriate corrective action.
The frequency of the major engine overhauls referred to in these requirements shall be consistent with Section IV.I.
" Overhaul Frequency" in Revision 2 of' Appendix II of the Design Review / Quality Revalidation report which was transmitted by MP&L letter dated July 18, 1986.
i Amendmenttio.2h
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b.
All-' connecting-rod bolts shall be lubricated in accordance with theLengine manufacturer's Instructions and torqued to the speci-
-fications; of the manufacturer. The lengths of the two pairs of bolts above theicrankpin shall be measured ultrasonically pre and post-tensioning.
c.
The lengths'of the two pair of bolts above the crankpin shall be measured ultrasonically prior to detensioning and disassembly of the bolts. If bolt tension 1sLless than'an' equivalent of-4
'2400 ft-lbs, the cause shall-be determined, appropriate corrective action shall be' taken, and the interval between -
checks of bolt tension'shall be re-evaluated.-
m
'd.
All connecting-rod bolts shall be visually inspected for thread-damage (e.g., galling)..and the two pairs of connecting rod -
-bolts above the crankpin shall. be inspected by magnetic particle testing (MT) to verify the continued absence of cracking. 'All washers used-with the bolts shall be. examined visually for signs of galling or cracking, and replaced 'if damaged.-
e.
A visual-inspection shal.1 be performed of accessible external-surfaces of the link rod box to verify the absence of any signs of service' induced distress.
m f.. - All of 'the bolt holes in the link rod box shall.be inspected.
~
for thread damage (e.g., galling) or other signs-of abnormalities.
I '
In. addition, the bolt holes subject to the highest stresses (i.e.,
the pair immediately above the crankpin) shall be examined with
- an appropriate nondestructive method to verify the continued
- absence of cracking. Any. Indications shall be recorded for-engineering evaluation and appropriate corrective. action.
g.
If the diesel generators:are operated in excess of 5740 KW steady state, allEconnecting rods shall be. disassembled and inspected at an interval of approximately 5 years coincident with the end
'of a fuel cycle, except that connecting rod disassembly and-
- inspection is not required for limited post maintenance testing
,4 over 5740 KW for the purpose of seating new piston rings as described in~ the MP&L letter dated December 6,1985'(AECM-85/0395).
3.2 Cylinder Blocks a.
Cylinder blocks shall be inspected for " ligament" cracks,
" stud-to-stud" cracks and " stud-to-end" cracks as defined in a report by Failure Analysis Associates. Inc. (FaAA) entitled,
" Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report no. FaAA-84-9-11.1) dated December 1984.**
(Note that the FaAA report specifies Transmitted to. H. R. Denton, NRC from C. L. Ray, Jr,, TDI Owners Group,
- by letter dated December 11, 1984.
)
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s additional inspections to be performed for blocks with "known" or " assumed" ligament cracks). The inspection intervals (i.e.,
frequency) ~shall not exceed the intervals calculated using the
-cumulative damage index model in the subject FaAA report. In I
addition inspection method shall be consistent with or.
equivalent to those identified in the subject FaAA report.
b.
In addition to inspections specified in the aforementioned FaAA report, blocks with "known" or " assumed" ligament cracks (as defined in the FaAA report) shall be inspected at each refueling outaoe to determine whether or not cracks have initiated on the top surface exposed by the removal-of two or more cylinder heads. This process shall be repeated over several refueling outages until the entire block" top has been inspected. Liquid-penetrant testing or a similarly sensitive nondestructive testing. technique shall be used to detect. cracking, and eddy current shall be'used as appropriate to determine the depth of
.any cracks discovered.
c..
'If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or
" stud-to-end" cracks, this condition shall be reported promptly to:the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed disposition and/or corrective actions L.-
have been approved by the NRC staff.
3.3 Cylinder Heads The following air roll test shall be performed as specified below, except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems A.C. Sources":
The engines shall be rolled over with the airstart. system and with the cylinder stopcocks open prior to each planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also (L
be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown..-(In the event an engine is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24-hour periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service.) The origin of any water detected in the cylinder must be detennined and any cylinder head which leaks due to a crack shall be replaced. The above air roll test may be discon-tinued following the first refueling outage subject to the following conditions:
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a.
". All cylinder heads are Grou'p III heads (i.e. cast after September 1980.)
b.-
Quality revalidation inspections, as identified in the GGNS Design Review / Quality Revalidation Report Revision 2, have L
been completed for all cylinder heads.
1 p.
Group III heads continue to demonstrate favorable leakage c.
performance. This should be confirmed with TDI. prior to deleting air-roll tests.
3.4 Turbocharoers.
Periodic inspections of the turbocharger shall include the following:
a.
'The turbocharger thrust bearings shall be visually inspected for k'
excessive wear after 40 non-prelubed starts since the previous visual inspection.
- b.
Turbocharger rotor axial clearance shall be measured at each-refueling outage to verify compliance with TDI/Elliott specifications..In addition, thrust bearing measurements shall
' be compared with measurements taken previously to detennine a need for further inspection or corrective action.
1 i
c.
Spectrographic and ferrographic engine oil analysis shall be performed quarterly to provide early evidence of bearing
' degradation. Particular attention.shall be' paid to copper level 'and particulate size which could signify thrust bearing degradation.
d; -The nozzle ring components and inlet guide vanes shall be visually inspected at each refueling outage for missing parts or parts showing distress.
If such are noted, the entire ring assembly shall be replaced.
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November 1, 1984 APPENDIX C ANTITRUST CONDITIONS OPERATING LICENSE NO. MPF.29 MP&L and SERI. shall comply with the followino antitrust conditions:
I.
DEFINITIONS E
(a) " Western Mississippi Area" means the counties of: Walthall, Lawrence Jefferson Davis, Covington, Simpson, Smith, Scott, Leake, Attala, Choctaw, Montgomery, Grenada Yalobusha, Panola, Tate. DeSoto, Pike, Amite, Wilkinson, Adams, Franklin, Lincoln, Copiah, Jefferson, Claiborne Hinds, Rankin.; Madison Yazoo.
Warren,- !ssaquena, Sharkey, Humphreys. Holmes, Carroll, Leflore, Sunflower, Washington, Bolivar. Tallahatchie, Quitman, Coahoma, and Tunica. An entity shall be deemed to be in the " Western Mississippi Area" if it has electric power generation, transmis-sfon, or distribution facilities located in whole or in part in the above described area.
t.
(b) "8vik Power" means the electric power, and any attendant energy, supplied or made available at transmission or subtransmission voltage by one entity. to another.
(c) " Entity" means a person, a private or public corporation, a municipality, a cooperative, an association, a joint stock i
association or business trust owning, operating or proposing to 1
own or operate equipment or facilities for the generation, trans-mission or distribution of electricity, provided that, except for municipalities or rural electric cooperatives, " entity" is restricted to those which are or will be public utilities under the laws of the state in which the entity transacts or will transact business or under the Federal Power Act, and are or will be providing electric service under a contract or rate schadule on file with and subject to the regulation of a state regulatory commission or the Federal Power Commission.
(d)
" Cost" means.any operating and maintenance expenses involved together with any ownership costs which are reasonably allocable to the transaction consistent with power pooling practices (whereapplicable). No value shall be included for loss of revenues from sale of poser at wholesale or retail by one party to a customer which another party might.otherwise serve. Cost i
shall include a reasonable return on Licensees' investment. The sale of a portion of the capacity of a generating unit shall be upon the basis of a rate that will recover to the seller the pro rata part of the fixed costs and operating and maintenance Amendment No. 27
4 3,
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- expenses of the unit, provid'ad that,'in circumstances in.which licensees and one or more entities in the Western Mississippi Area take an undivided interest in a unit in fee, construction costs'and operation and maintenance expenses shall be paid pro rata.
II.
INTERCONNECTIONS (a) Licensees. shall interconnect with and coordinate reserves by means of the sa'e and purchase of emergency and/or scheduled ~
. maintenance bulk power with any entity (ies) in the Western Mississippi Area engaging in or proposing to engage in electric bulk power supply on tenns that will provide for Licensees' costsinconnectiontherewithandallowtheotherparty(ies) full access to the benefits of reserve coordination.
'(b) Emergency service and/or s'cheduled maintenance service to be provided by each party shall be furnished to the fullest extent available from the supplying party and desired by the party in need. Licenseesandeachparty(ies)shallprovidetotheother emergency service and/or scheduled maintenance service if and
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when available from its own generation and from generation of others to the extent'it can do so without impairing service to its customers including other electric systems to whom it has fim commitments.
(c) Licensees and the other party (ies) to a reserve sharing arrange-l ment shall from time to time jointly establish the minimum reserves to be-installed and/or provided under contractual arrangements as necessary to maintain in total a reserve margin sufficient to provide adequate reliability of power supply to the interconnected systems of the parties. If Licensees plan gg their reserve margin on a pooled basis with other Middle South3 System companies, the reserves jointly established hereunder shall be on the same basis. Unless otherwise agreed upon, minimum reserves shall be calculated as a percentage of estimated peak load responsibility. No party to the arrangement shall be required to maintain greater reserves than the per-centage of its estimated peak load responsibility which results from the aforesaid calculation, provided that, if the reserve requirements of Licensees are increased over the amount Licensees would be required to maintain without such interconnection, then the other party (ies) shall be required to carry or provide for as its (their) reserves the full amount in kilowatts or such increase.
b (d) The parties to such a reserve sharing arrangement shall provide such amounts of ready reserve capacity as may be adequate to avoid the imposition of unreasonable AmNm4fAh.
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- demands on the other in meeting the normal contingencies of operating its system. However, in no circumstances shall the ready reser 4 Muirement exceed the installed reserve require-ment.
(e)
Interconnections will not be limited to low voltages when higher voltages are available from licensees' installed facilities in '
the area where interconnection is desired, when the proposed arrangement is found to be technically and economically feasible.
Control and telemetering facilities shall be provided as required,
for safety and prudent operation of the interconnected systems.
E (f) Interconnection and coordination agreements shall not embody any restrictive provisions pertaining to intersystem coordination.
Good industry practice as developed in the area from time to time (if non-restrictive) will satisfy this provision.
III. POWER TRANSACTIONS Licensees will sell bulk power at their costs to or purchase bulk power from any other entity (ies) in the Western Mississippi Area engaging in
.i or proposing to engage in generation of electric power when such
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transactions would serve to reduce the overall costs of new bulk power supply for themselves or for the other' party (ies) to the transaction.
~
This refers specifically to the opportunity to coordinate in the planning of new generation, transmission and related facilities. This provision shall not be construed to. require Licensees to purchase or sell bulk power if they find such purchase or. sale infeasible or their costs in connection with such purchase or tale would exceed their benefit therefrom.
IV. PARTICIPATION IN OWNERSHIP (a) Licensees and any successor in title shall offer an opportunity to participate in the Grand Gulf Nuclear Units and any other nuclear generating unit (s) which they or either of them, may construct, own and operate in the State of Mississippi, severally or jointly, during the term of the instant license, or any extension or renewal thereof, to any entity (ies) in the Western Mississippi Area by either a reasonable ownership interest in such unit (s), or by a contractual right to purchase a reasonable portion of the output of such unit (s) at the cost thereof if the entity (ies) so elects.
In connection with such access, licensees will also offer transmission service as may be required for delivery of such power to such entity (ies) on a basis that will fully compensate licensees for their cost.
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.(bk_' In the event that during the term of the instant license, or any
-extension or renewal thereof, licensees obtain participation in the ownership of or. rights to a portion of the output of one or
- more nuclear generating units constructed.. owned and operaued by any affiliate er subsidiary of the Middle South /ttiMtit: 1ystem other than licensees, or' by any successor in title to the Grand Gulf Nuclear Units.. licensees shall exert their best efforts to obtain participation in such nuclear unit (s) by any entity (ies) in the Western Mississippi Area requesting such participation on terms no less favorable than the terms of Itcensees' participa-u
. tion therein.-
V.
TRANSMISSION SERVICES (a) Licensees ~ shall facilitate the exchange of bulk power by trans-mission over its transmission facilities between or among two or more entities in the Western Mississippi Area with which it is interconnected; and between any och entity (ies) and any such entity (ies). engeging in bulk power supply outside the Western Mississippi Area between whose facilities Licensees' transmission lines and other transmission lines would form a continuous electrical path, provided that (1) permission to utilize such other transmission lines has been obtained, and (2) the arrange-ments reasonably can be accommodated from a functional and tech-nical standpoint. Such transmission shall be on terms that fully compensate Licensees for their cost. Any entity (ies) requesting such transmission arrangements shall give reasonable advance notice of its (their) schedule and requirements.
(The foregoing applies to any entity (ies) to which Licensees may be interconnected in the future as well ai those to which they are nowinterconnected.)
(b) - Licensees shall include in their planning and construction pro-gram sufficient transmission capacit as required for the trans-actions referred to in subpara a) of this paragraph, provided that any entity (ies) graph in the Western Mississippi Area give Licensees sufficient advance notice as may be necessary to accomodateits(their)requirementsfromafunctionalandtech-nical standpoint and that such entity (ies) fully compensates Licensees for their cost. Licensees shall not be required to
- construct transmission facilities which will be of no demonstrable present or future benefit to Licensees.
VI. POWER FOR RESALE Licensees will sell power for resale to any entity (ies) in the Western Mississippi Area now engaging in or proposing to engage in retail h
distribution of electric power.
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"tII. REGttLATORY PROVISIONS The foregoing conditions shall be implemented in a manner consistent 1
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with the provisions of the Federal Power Act and the Mississippi Public Utilities Act of 1956 and all rates, charges or practices in connecticn therewith are to be subject to the approval of regulatory agencies having jurisdiction over them.
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(3)'AntitrustConditions~
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MP&L and SERI.shall comply with the antitrust conditions
. delineated in Appendix C.
is authorized to transfer its
_ rights to possess, to use and to operate the facility to provided however, that until further authorization of the Com-mission, MP&L.and SERI.shall continue to be responsible.for-compliance with the obligations imposed on the licensees in g y o'
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these antitrust conditions, and provided further that 49R h accepts the right to possess, use and operate the facility subject to the outcome of the pending separate antitrust review of_ the antitrust considera+4aae of this tran<fer.
$50f3FAI * "& >96 e t4VW P osa ens Me facs lo &
Ind(upenuent verification of Staff Performance and Other Pignt (4)
Act' vitics (Section 13.4, 5ER, 55ER #2) 8 42 [
(a) ASEA 4-shall establish a subcommittee of the Corporate Safety.
.l Review Committee to review and evaluate the:
(i) Status'and readiness of'the plant and systems needed ~
to support interided modes of operation and/or testing; (ii) Readiness of personnel to conduct intended operation-
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and testing; (iii) Morale and attitudes of plant personnel that have a bearing on safe plant operation;
'(iv)Pastperformanceinplantoperationsandadherence to procedures and administrative controls; (v) Changes in current organization with regard to experience and qualifications of plant management and supervisory personnel since the last evaluation; (vi)ResultsandeffectivenessofthePlantSafetyReview Committee (PSRC),
(vii) Status of plant as compared to other BWR startups based on the subcommittee's knowledge and experience.
Reviews shall be conducted prior to exceeding 50 percent of full power and within 30 days following completion of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run. The subcommittee shall be composed of a minimum of three professionals not employees of SGA4 with experience which will be responsive to the concerns %
presented above.
In conducting these evaluations, the Amendment No. 27, _
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.NL'88/10 N
j ADMINISTRATIVE CONTROLS 5.5.2 SAFETY REYTEV ComITTEE (Sac)
FUNCTION 6.5.2.1 The stC shall function to provide independent review and audit of designated activities in the areas of:
a.
. nuclear. power plant operations b.
nuclear engineering c.
cheafstry and radiocheatstry d.
metallurgy e.
instrumentation and control f.'
radiological safety
- g. -
mechanical and electrical engineering h.
quality assurance practices COMPO$fTION
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6.5.2.2 0.; "" :.t:". k :r;::: :' 'J.;.
W e n:
Vice President, Nuclear Operations Member:
Vice President, Nuclear Engineering & 5 Member:
tor, Nuclear Plant Engineeri 3
Member:
Site GGN5 L
Maeber:
' Director, Qua s
6,fudyInc..y o'%
Member:
Designated nta Systaa services, Inc.
1 4
Member:
GGN5 Manager Member:
tar ' Nuclear Licensing Member-Manager,, Radiological and Environmental se r:
Manager, Operational Analysis l
@sertM l
kTwo or more additional voting seabers shall be consultants to.,..-.....
(fnsert IDM; Reactor Safessards letter. Mark to Palladino dated O
- , S
- . consistent with the recosnendations of the Advisory Committee r
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"The SAC members shall hold a Bachelor's degree in an engineering or physical '
science field or equivalent experience and a minism of five years of technical expeHence of which a ninfaus of three years shall be in one or more of the
@ sir [C] disciplines of 5.5.2.la through h.
In the aggregate, the seabership of the comalttee shall provide specific practical exper< ence in the majority of the L
disciplines of 5.5.2.la through h.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
l AmenNentNo.42,,,,,,,,
GRAND CULF-UNIT 1 f-9 L
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i.88/10
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'[I I'nsert A.
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The SRC: shall be composed of a. Chairman'and nine voting members.
I Insert B-
'The Chairman and members.shall meet the qualifications below.
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A6CM-84/yk NL 88/10.
b Insert C The SRC Chatrinan shall hold a Bachelor!s degree in an engineering or physical science field or an equivalent and a minimum of six years of professional level managerial exMrience in the power field. In addition, the Chairman shall have tie necessary overall nuclear background to determine when to call consultants and contractors for dealing with,
complex problems beyond the scope of * - '
a--
expertise.
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entergy sp 4 4s,7nc,
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h by the aerial surveys, and walking patrols will be directed to the problem e
areas to' evaluate the extent of the problem to be corrected.
)
t The Erosion Control Inspection Program shall begin upon commencement of normal transmission line inspection procedures.
Semi-annual surveys shall continue until stabilization of soil and vegetation (i.e., ground cover establishment) is achieved.
A summary of_ the field inspection program and any procedures implemented to control abnormal erosion conditions associated with transmission line main-tenance activities shall be reported in the Annual Environmental Operation Report in accordance with Subsection 5.4.1.
Field logs indicating locations of erosion damage and measures taken to re,ctify erosion problem areas and estimation of the time to achieve effective stabilization will be maintained and available for inspection for a period of five years.
Results reported shall contain information encompassing but not limited to inspection date, estimated size of erosion problem area, probable caue of erosion, type of stabilization program, and date of effective stabilization, as appropriate.
(
4.2.2 Coolino Tower Drift Procram Seven sampling sites will be utilized to. measure cooling tower drift-deposition.
At least two of the sampling sites will have dup 1'icate sampling devices. Six of the. seven sampling sites will be located in areas where maximum salt deposition is predicted.
These a es were extrapolated from the 8echtet Salt Depu ition Model developed for the Final Environmental Report.
The weenth sampling site will be a control site located south of Raymond, Mississippi.
1 Fallout samples will be collected using buckets with a known volume of deionized water in each.
The buckets will be located four to six feet above the ground, fitted with bird rings, and covered with fine mesh screens to exclude leaves and insects.
The samples will be collected on a quarterly basis and analyzed for calcium, magnesium, sodium, iron, phosphates, nitrates, chloride, fluorides, sulfates, and total dissolved solids.
These parameters were selected because past analyses have shown them to be prevalent in the cooling water source water.
The results of these analyses will be correlated with local rainfall data and
'.s 4-2 Amendment No. 42 7,_.
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APPENDIX 8 TO FACILITY LICENSE NO. NPF-29 GRAND GULF NUCLEAR STATION
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I DOCKET N0. 50-416 ENVIRONMENTAL PROTECTION PLAN OCTOBER 1984 is 9
t Amendment No. 27,
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