ML20244E242

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Forwards Final Draft Low Power License NPF-56,reflecting Comments Received to Date
ML20244E242
Person / Time
Site: Seabrook, 05000000
Issue date: 08/22/1986
From: Novak T
Office of Nuclear Reactor Regulation
To: Bernero R, Rossi C, Speis T
Office of Nuclear Reactor Regulation
Shared Package
ML20235T530 List: ... further results
References
FOIA-87-51 NUDOCS 8609090569
Download: ML20244E242 (23)
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UNITED STATES J

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NUCLEAR REGULATORY COMMISSION

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.M[L q ut MEMORANDUM FOR:

Themis P. Speis, Director, DSRO Charles E. Rossi, AD/PWR-A Robert M. Bernero, Director

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Division of BWR I.icensing Frank J. Miraglia Director, Division of PWR licensing-B

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Edward S. Christenbury, Director & Chief gow-Counsel, OGC t

7 Edward L. Jordan Director DEPER, IE W

l William T. Russell, Director, DFFS Robert F. Burnett, Director, DS, NMS$

William Kane, Director Division of Reactor Projects, Region I G. Wayne Kerr, Director, SP Richard E. Cunningham, Director f

Division of Fuel Cycle & Material Safety, NMSS FROM:

Thomas M. Novak, Acting Director PWR Project Directorate #5 Division of PWR licensing-A

SUBJECT:

FINAL. DRAFT SEABROOK STATION UNIT 1 f

LOW POWER LICENSE A copy of the Final Draft of the low Power license for the Seabrook Station, l'r't I with attachne**s is provided es an enclosura. This draft license b!s I

tse w modi'ic: 1: refint s'i en rt; rmi erd tr - ycur suf f to dcte.

A draf t of Attachment I to the license is requested from Region 1.

3 Flease previda ccmrets and cenc""reece to tt.e Seeberek r~i"? Farecer.

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homas M.

vak, Acting Director Division of PWR t.icensing-A l

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PUBt.IC SERVICE COMPANY OF NEW FAMPSHIRE, ET At..*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO.1 l

1 FACILITY OPERATING LICENSE License No. NPF-56 I

1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for license filed by the Public Service Company of New Pampshire (PSNH), as agent and representative of the utilities listed below (and hereafter the utilities listed below including PSNH collectively referred to as licensees) complies with the

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standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 i

CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;

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B.

Construction of the Seabrook Station, Urcit No.1 (the facility) has I

been substantially completed in conformity with Construction Permit No. CPPR-135 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 l

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?f 9 A-a-- t he *^ c.il a ti on: c' the Cmissiw, (except as eiegted from cor..piiance in Sectior. 2.s belcw);

D.

There is reasonable assurance:

(11 that the activities authorized b ~ i s :., e t i r '..:ce n e r te centerer sit t.

renvH'm t r.ccitn r : a.:ftts c'

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- r- ;c'.i;{:'es*ii' be conducted it. et-pliance rith the Cmis? ion's r plc;;cns se'.

ferth in 10 CFR Chapter I, (except as exempted from compliance in Section 2.0 below):

  • Public Service Company of New Hampshire is authorized to 'act as agent for the: Bangor Fydro-Electric Company, Canal Electric Company, Central Maine Power Company, Central Yemont Public Service Corporation Connecticut light and Power Company, Fitchburg Gas & Light Company, Hudson light & Power Company Maine Public Service Corporation, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal lighting Plant, the United Illuminating Company, and Yermont Electric Generation and Transmission Cooperative, Inc., and has exclusive resp 6nsibility and control over the l

physical construction, operation and' maintenance of the facility.

DRAFT

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E.

PSNP is technically Qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; l

F.

The licensees have satisfied the applicable provisions of 10 CFR 140

" Financial Protection Requirements and Indemnity Agreements" of the Comission's regulations; G.

The issuance of this license will not be inimical to the comon de-fense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical and other bene-fits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-56, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR 51 of the Comission's regulations and all applicable requirements have been satisfied; and I.

The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this licente will be in accordance with the Comission's regulations in 10 CFR 30, 40 and 70.

1

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2.

Based on the foregoing findings regarding this facility. Facility Operating License No. NPF-56 is hereby issued to Public Service Company of Ne-

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Hampshire et al. (the licensees) to read as follows:

A.

This license applies to the Seabrook Station, Unit 1. (the facility) a crusurizec wtor erh *r rcc:to-and essociated ecc%r; cred by the licensees. The facility is located in Seabrook Township.

Rockingham County, New Hampshire on the southeastern coast of the State of New Hampshire and is described in the licensees' " Final

.Y e f t. 6 : 1s N r - ', es s" r.lemerte: ar d evn:'e:' ar.d ir the i v rsec: ' Eni rc,nx nt/I &cra., et v.: Ww:c-: ne c,eric:.

B.

Sul, ject to the conditions and requirements incorporated i erein, the Comission hereby licenses; (1)

PSNH pursuant to Section 103 of the Act and 10 CFR 50, to possess, use and operate the facility at the- @signated location in Rockingham County, New Hampshire in accordance with the procedures and limitations set forth in this license; (2)

The licensees, to possess the facility at the designated location in Rockingham County, New Fampshire in accordance with the procedures and limitations set forth in this license; MAET

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. (3)

PSNH, pursuant to the Act and 10 CFR 70, to receive, possess i

and use at any time special nuclear material as reactor fuel, in accordance with limitations herein and in accordance with the limitations for storage and amounts recuired for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)

a. No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks or reactor vessel at any one time.
b. PSNH shall maintain edge-to-edge distance of 12 inches:

1.

Between the above two fuel assemblies, 2.

Between fuel assemblies (out of storage) and the shipping container array or reactor vessel, and 3.

Between fuel assemblies (out of storage) and the storage rack arrays.

l (5)

No more than 60 loaded shipping containers shall be allowed onsite at any one time.

(6)

No shipping container shall be outside for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

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from time of receipt onsite.

(7)

New fuel assemblies may be stored in the new fuel storage vault subject to the following conditions:

The maximum U-235 enrichment shall be 3.55 wL a.

b.

The r9% nc-ber of fuel asse:.blies that shall t< t:cred i

in the r.ev ft;t stcrage crea s ell be 90.

The fuel assemblies shall be stored dry in a checkerboard c.

pattern.

d.

The Rorctor Er::ineeriar Dea *rtnet !>.?ervire" or e:rheir-t tcilif w d cc:,

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(-. 1.i s. ' ssse :,.

lecztion a* tar insertion int:

t'- O n crc: storage ic:aticn in accoroance with a prepared written procedure approved by the Station Manager.

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(8)

PSNH is hereby exempted from the provisions of 10 CFR Section 70.24 insofar as this section applies to materials held under this license.

I (9)

PSNH, pursuant to the Act and 10 CFR 30, 40 and 70, to re-ceive, 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;

  1. n IIRAFT

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~ (10) PSNH, pursuant to the Act and 10 CFR 30, 40 and 70, to re-ceive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical fonn, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and l

(11) PSNH, pursuant to the Act and 10 CFR 30, 40 and 70, to pos-sess, but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility.

C.

This 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 Commission now or hereafter in effect; and i

is subject to the additional conditions specified or incorporated below:

d (1)

Maximum Power level PSNH is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thennal (100% rated power 1 in accordance with the conditions specified herein.

Pending Conrnission approval of issuance of 100% rated power license, this license is restricted to power levels not to

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exceed 5 percent of rated power (170 megawatts thermal). The items identified in Attachment I to this license shall be completed as specified. is hereby incorporated into this license.

(2)

Technical Specifications and Environmental Protection Plan 1he Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated inte this 11 :". 5 -

";blic Service (ccc ? v c' % ~7 shire r.h.7 oprett 19 1:.i ntf ir acet-c:rce wi n tne ;tevnal becifications and the Environntental Protection Flar..

(3)

Inservice Inspection Program (Section 5.2.4, 6.6.3, SER, 55ER 3, 55ER 4 55ER 5)*

PSNH shall submit the inservice inspection ptqgram which confonns to the ASME code in effect 12 months prior to.the date of this license, in accordance with 10 CFR Section 50.55a(g)(4), for NRC staff review and approval within six months from the date of this license.

(4)

Radiation Data Management System (Section 7.5.2.2 SER, SSER 51 Qualified non-fuse dependent isolation devices shall be installed and shall be operati,onal before stertup after the first refueling outage.

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DRAFT

' (5)

Accident Monitoring Instrumentation, TMI Action Plan Item II.F.1 (Section 11.5.2, 55ER 2 and 55ER5)

Before startup following the first refueling outage, PSNH shall demonstrate that the iodine / particulate sampling system is operable and will perfonn its intended function.

I (6)

Emergency Preparedness (Section 13.3, SER, SSER 4)

In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the

,l provisions of 10 CFR Section 50.54 (sl(2) will apply.

(7)

Initial Test Program (Section 14. SER)

Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR Section 50.59 shall be reported in accordance with Section 50.59(b) within one month of such change, b

(8) leakage Reduction Measurement Program (Section 15.9.15, SER, 55ER 51 Before proceeding above 5% of rated power, PSNH shall submit the results of leak rate measurements which demonstrate that its leakage reduction program has been successfully implemented.

(9)

Safety Fara.eter Lisplay System (Section 18, SER, 55ER 4, SSER 51 1

Before restart fellcwine the first refueline outace, PSNH s r.-

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.' a n se y f. 1980 er.c Arrit 2,1980, enc as modified ti :ne staff's wdit findirgs) that is acceptable to the NRC.

i Before proceeding above 5% of rated power, PSNH shall have installed staff approved qualified isolation, devices between the RYllS and SPDS.

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I D.

pSNH is exempted from the Section !!!.D.2(b)(ii) containment airlock testing requirements of Appendix J to 10 CFR 50, due to the special circumstance described in Section 6.2.6 of SER Supplement 5 authorized by 10 CFR Section 50.12(a)(2)(iii). This exemption authorized by law, will not present an undue risk to the public he61th and safety and will not be inimical to the common defense and security of the public. The exemption is hereby granted pursuant to 10 CFR Section 50.12 (51 FR 25279 July 11, 1986).

With the granting of this exemption, the facility will operate, to the extent authorized herein, in confortnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Consnission.

A partial exemption from those portions of General Design Criteria 4 of Appendix A to 10 CFR 50 (which require protection of structures, systems and components important to safety against dynamic effects associated with postulated primary coolant system pipe breaks) was granted on November 22, 1985, for a period ending with the completion of the second refueling outage for Seabrook Station, Unit 1 or the adoption of the proposed rulemaking for modification of GDC-4 whichever occurs first. Effective May 12,1986, GDC-4 has been modified to exclude from the design basis the protectien of structures, systems and components against dynamic effects associated with postulated pipe ruptures of primary coolant system loop piping in 2

pressurized water reactors (51 FR 12502 April 11, 1986).

E.

PSNH shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and 3

safeguards contingency plans, previously approved by*the Commission and all amendments and revisions to such plans made pursuant to the a,mHty of M UR Section M.53 cnd 10 CG. ~utier. cD.5'(pl. De plans, which contain Safeguards Information protected uncer 10 CIR Section 73.21, are entitled:

"Seabrook Station Physical Security Plan", with revisions sub-itted through June 16, 1986, "Seebrook L stirn ic;urity Ired ri-

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E2; ted. d -.,> S u.i.w 356 ;.e.t Cont.ingency Flar", with rension submitted inrough hovember 30,1si.

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F.

PSNP shall imolement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, the Fire Protection Program report, and the Fire Protection of Safe Shutdown Capability report for the facility, as supplemented and amended, and as approved in,the Safety Evaluation Report, dated March 1983 and Supplement 4, dated May 1986 and Supplement 5, dated June 1986, subject to the following provision:

PSNH may make changes to the approved fire protection program l

without prior approval of the Comission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G.

Except as otherwise provided in the Technical Specification or Environ-mental Protection Plan, PSNH shall report any violations of the requirements contained in Section 2.C of this license in the following manner:

initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR Part 50.73(b), (c) and (e).

H.

The licensees shall have and maintain financial protection of such type y

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.

1 I.

This license is effective as of the date of issuanci and shall expire at Midnight on

, 2026.

FOR TFE N'F.WJ REGULATORY COW CION Farold R. Denton, Director Office of Nuclear Reactor Regulation j

Attachments / Appendices:

1. - Work Items to be Completed 2.

Appendix A - Technical Specifications (NUREG-1207) l 3.

Appendix B - Environmental Protection Plan

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Date of Issuance:

l DRAFT

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ATTACHMENT 1 TO NPF Il0RK ITEMS TO BE COMPLETED To be provided by Region I.

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L__________________.._

NUREG-1207 Technical Specifications Seabrook Station, l

Unit 1 Docket No. 50-443 Appendix "A" to License No. NPF-56 1

1 Issued by the Ue Nucbs: Regulatory Commission Office of Nucl car Re:.ctcr f,eguia.io, SEPTEMBER 1986 g.. a r cy,o,

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DRAFT APPENDIX B l

TO FACIt.ITY OPERATING t.! CENSE NO. NPF-56 SEABROOK STATION, UNIT 1 PUBt.!C SERVICE COMPANY OF NEW FAMPSHIRE DOCKET NO. 50-443 ENVIRONMENTAL. PROTECTION Pt.AN (NONRADI0t.0GICAl.)

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i DRAFT SEABROOK STATION, UNIT NO. 1 ENVIRONMENTAL PROTECTION PLAN (NONRA0!OLOGICA1.)

TABLE OF CONTENTS i

Section Page 1.0 Objectives of the Environmental Protection Plan.............

1-1 2.0 Envi ronmental Protection Is sues.............................

2-1 3.0 Consistency Requirements.................................... 3-1 3.1 Plant Design and Operation.................................. 3-1 3.2 Reporting Related to the NPDES Permit and State Certification...................................'......

3-3 5.2 U.n.ges F.equircd for Cup'ience with OtF.c-r Environmental Regulations.............................. 3-3

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la 1 4.1 Unusual or Important Environmental Events................... 4-1 4.2 Environmental Monitoring.................................... 4-1 5.0 Admi n i s tra ti ve Proce du re s................................... 5-1 5.1 Re v i ew a nd Aud i t...................................... L....

5-1 5.2 Records Retention........................................... 5-1 5.3 Changes in Environmental Protection Plan.................... 5-2 5.4 Pl a nt Reportin g Requi rement s................................ 5-2 nRAFT ii

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DRhfT 1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of non-radiological environmental values during operation of the nuclear facility.

The principal objectives of the EPP are as follows:

(1) Verify that the facility is operated in an environmentally acceptable manner, as established by the Final Environmental Statement - Operating Licensing Stage (FES-OL) and other NRC environmental impact assessments.

(2) Coordinate NRC requirements and maintain consistency with other Federal,

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State and local requirements for environmental protection.

l (3)

Keep MC infomed of the environment' ef'ects c' fecility construction

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and operation of actions taken to control those effects.

i Environmental concerns identified in the FES-OL which relate to water quality matters are regulated by way of the licensee's NPDES permit.

9 1-1 l1 RAFT

DRAFT 2.0 Environmental Protection Issues In the FES-Ot. (NUREG-0895) dated December,1982, the staff considered the l

environmental impacts associated with the operation of Seabrook Station, Unit No. 1.

No aquatic / water quality, terrestrial, or noise issues were l

identified.

Aquatic matters are addressed by the effluent limitations and monitoring i

l requirements contained in NPDES Permit No. NP0020338 issued by the U. S.

Environmental Protection Agency (Region II on July 26, 1985. The NRC will rely on the U.S.E.P.A and the NPDES Pennit for regulation of matters involving water quality and aquatic biota.

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2-1 0DAET

DRAFT 3.0 Consistency Requirements i

3.1 Plant Design and Operation l

l The licensee may make changes in station design or operation or perforin tests or experiments affecting the environment provided such activities do not in-i volve an unreviewed environmental question and do not involve a change in the

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l EPP*.

Changes in station design or operation or perforinance of tests or ex-s periments which do not affect the environment are not subject to the require-ments of this EPP. Activities governed by Section 3.3 are not subject to the requirements of this Section.

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Before engaging in additional construction or operational ac'tivities which r.ay significar.tly effe:t the environmer t, tne licensee shall prepare and re-cord an environmental evaluation of such activity. Activities are excluded fr-tr.15 recaire er.1 if z1! reeserab!r e nr.radiMef t cr vi cw-ul r'f t::s l

are confined to the onsite areas previously disturbeo curing site preparation and plant construction. When the evaluation indicates that such activity in-volves an unreviewed environmental question, the licensee shall provide a 1

This provision does not relieve the licensee of the requirements of 10 CFR 50.59.

3-1 s

MAFT

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DRAFT written evaluation of such activity and obtain prior NRC approval. When such activity involves a change in the EPP, such activity and change to the EPP j

1 may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3 of this EPP.

l 1

A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question it concerns:

(11 a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and ticensing Board; or (21 a significant change in effluents or power level; or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact.

l The li:enset shall n. air.tain records of chenges ir. icciiity design or operation and of tests and experiments carried out pursuant to this Subsection.

These re c c-d: sti l < r.c i rts ten e sale:.

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mination that the change, test, or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0.

The licensee shall in-clude as part of the Annual Environmental Operating Report lper Subsection

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5.4.1) brief descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.

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l DRAFT 3.2 Reporting Related to the NPDES Permit and State Certification Changes to, or renewals of, the NPDES Permits cr the State certification shall be reported to the NRC within 30 days following the date Ga change or rene al is approved.

If a pennit or certification in part or in its entirety, is ap-pealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

The licensee shall notify the NRC of changes to the effective NPDES Permit proposed by the licensee by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency. The licensee shall provide the NRC a copy of the application for renewal of the NPDES Pennit at the same time the application is submitted to the permitting agency.

3.3 Changes Reovired for Compliance with Other Environmental Regulations l

Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, State, and local environmental regulations are not subject to the requirements of Section 3.1.

DRATT

DRAFT l

4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events l

Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report per Subsection 5.4.2.

The following are examples: excessive bird impaction events, onsite plant or animal disease outbreaks; mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973; fish kills; increase in nuisance organisms or conditions; and l

1 unanticipated or emergency discharge of waste water or chemical substances.

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i No routine monitoring programs are required to implement th'is condition.

s 4.2 Environmental M:nitoring 4.2.1 q ut. tic mon toring The certifications and permits required under the Clean Water Act provide mechanisms for protecting water quality and, indirectly, aquatic biota. The NRC will rely on the decisions made by the U. S. Environmental Protection Agenc/ and the State of New Fampshire under the authority of the Clean Water Act, for any requirements for aquatic monitoring.

4-1 B

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DRAFT 4.2.2 Terrestrial Monitoring Terrestrial monitoring is not required.

4.2.3 Noise Monitoring Noise monitioring is not required O

DRAFT

4 DRAFT 5.0 Administrative Procedures 5.1 Review and Audit The licensee shall provide for review and audit of compliance with the EPP.

The audits shall be conducted independently of the individual or groups responsible for performing the specific activity. A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.

b i

i 5.2 Records Retention Records and logs relative to the environmental aspects of station operation sr.all be w.fe e-n reuir:ed in a tranne-convenient f-review and ir.pt:S These records and logs shall be r.ade available to hRC on request.

1 Records of modifications to station structures, systems and.* components deter-l mined to potentially affect the continued protection of the environment shall l

l be retained for the life of the station. All other records, data and logs re-l lating to this EPP shall be retained for five years or, where applicable, in i

accordance with the requirements of other agencies.

nDAsT

l DRAFT 5.3 Changes in Environmental Protection Plan Requests for changes in the EPP shall include an assessment of the environmental impact of the proposed change and a supporting justification.

Implementation of 3

such changes in the EPP shall not commence prior to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision

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j to the EPP.

5.4 Plant Reporting Requirements 5.4.1 Routine Reports

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An Annual Environmental Operating Report describing implementation of this EPP for the previous year shall be submitted to the NRC prior td May 1 of each year. The perie:i cf tr.e first rc;crt shall h;ir vi h the dete of issuar.ce of the operating license, and the initial report shall be submitted prior to May I c' ne 3e.r fel'owirq issuanct c f tt4-c rere 4; li:< me.

The report shall include summaries and analyses of the results of the environ-mental protection activities required by Subsection 4.2 (iffany) of this EPP for the report period, including a comparison with related preoperational studies, operational controls (as appropriate), and previous nonradiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.

If, harmful effects or evidence of trends toward irreversible damage to the environment are observed, the

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DRAFT e

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licensee shall provide a detailed analysis of the data and a proposed course i

of mitigating action.

1 l

The Annual Environmental Operating Report shall also include:

(1) A list of EPP noncompliance and the corrective actions taken to remedy i

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them.

l (2) A list of all changes in station design or operation, tests, and experi-ments made in accordance with Subsection 3.1 which involved a potentially significant unreviewed environmental question.

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(3) A list of nonroutine reports submitted in accordance with Subsection 5.4.2.

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l In the evert ttn tore res;?ts are r.:t as.ilable by the report cee dats, the report shall be submitted noting and explaining the missing results.

The miss-ing resvits snr.'. L'c st5:1-ted e s t,.-t is p :sibit tr a sa:ri u u y n;cr.,

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l 5.4.2 Nonroutine Reports

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l A written report shall be submitted to the NRC within 30 days of occurrence of a nonroutine event. The report shall:

(a) describe, analyze, and evaluate the event including extent and magnitude of the impact, and plant operating l

5-3 nDAET

b characteristics; (b) describe the probable cause of the event. (c) indicate the 1

action taken to correct the reported event; (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences in.

volving similar components or systems; and (e) indicate the agencies notified and their preliminary responses.

I Events reportable under this subsection which also require reports to other federal, State or local agencies shall be reported in accordance with those re-porting requirements in lieu of the requirements of this Subsection. The NRC shall be provided with a copy of such report at the same time it is submitted 4

to the other agency.

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5-4 npAFT

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