ML20136C196

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Requests 15 Minutes to Present Stated Issues to NRC During 970204 Meeting on Myaps
ML20136C196
Person / Time
Site: Maine Yankee
Issue date: 01/09/1997
From: Blanch P
AFFILIATION NOT ASSIGNED
To: Zwolinski J
NRC (Affiliation Not Assigned)
Shared Package
ML20136C110 List: ... further results
References
NUDOCS 9703110309
Download: ML20136C196 (5)


Text

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I From PAUL BLANCH <PMBLANCH91x.netcom.com>

To:

WND2.WNP3(jaz)

Date:

1/9/97 12:00pm i

subject MY Commission meeting

]

1 Friends:

~

The Commission contacted me yesterday and gave me about one hour to = submit this request. Looks good for the meeting.

l 1/8/97 L

Dr. Andrew Bates' USNRC Office of the Secretary Washington DC'20555-0001 FAK; 301 415-1672 l

Subject:

Commission Meeting on Maine Yankee l

l

Dear Dr. Bates:

It is my understanding the Commission will be conducting a

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meeting on =

Maine Yankee on February 4, 1997. I have been actively supporting j

= many of the concerned residents and their_ questions regarding-the = safety of the plant.

I have been communicating with the NRC Staff related to some of these = safety issues. These issues are discussed in my attached position = paper regarding the NRC=B9s ISAT report of October 7, 1996. These = issues have been forwarded to the Staff and I have yet to receive any = meaningful response.

My additional cor.cern is the NRC position that:

Commission adjudicatory decisions are clear that compliance

with the Commission regulations is essential to a determination of = adequate protection of the public health and safety under the Atomic

Energy Act."

The memorandum refers to Section 185 of the Atomic Energy that =

provides that Operating Licenses are issued "upon finding that the = facility authorized has been constructed and will operate in = conformity with... the rules and regulations of the Commission." =

(Emphasis added.)

The ISAT report is clear in that the plant has not been verified

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to = be in compliance =B3 with Commission regulations =B2 therefore the = minimum safety requirements have not been i

satisfied. Until a complete = verification of compli.ance is i

4.

9703110309 970306 l

PDR ORG NRRA PDR vs I

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conducted, nuclear safety can not be = assured.

i The ISAT report states: =B3 Maine Yankee was in general I

conformance = with its licensing-basis although significant items of = non-conformance were identified. =B2 This appears to be =

acknowledgment that.the plant is not in compliance with Commission =

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-Regulations. The Staff and the Commission then concluded =

B3 performance at Maine Yankee was considered adequate for

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operation.=B2 It mystifies me as to how this determination was l

made = with the_ apparent admission of regulatory non-conformance.

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l Given these questions and other issues related to the safe 1

l operation = of Maine Yankee, I respectively request 15 minutes to L

present these = issues.to the Commission during the' meeting of 1

February 4,1997. I = will be speaking on my behalf and on behalf of many of the concerned = local residents in the vicinity of the Maine Yankee plant, j

I look forward to your favorable response.

Sincerely,

. Paul M. Blanch-l 135 Hyde Rd.

West Hartford CT.

06117 860-236-0326 COMMENTS ON MAINE YANKEE ISAT REPORT DATED OCTOBER 7, 1996 In her letter dated October 7, 1996 Dr. Jackson stated to Mr.

Charles =

D.

Frizzle =B3The purpose of the ISA was to determine whether Maine =

Yankee was in conformity with its design and licensing bases;=B2 Dr. =

Jackson completely avoided addressing this objective.

The simple

= answer is that the plant is not in compliance with =B3its design and = licensing bases.=B2 This conclusion is supported by the content of = the very ISAT report attached to this letter.

It appears the tone of the report is different from anything I have.= ever.seen come out of the NRC.

They refuse to even attempt to = directly address the issue of compliance with the regulations and use = words-such-as:

=B3These tests may have shown some degree of = cavitation and an_ uncertain, but likely l

very small, margin.

These = limiting conditions would exist only l

in the low probability. event of = a large break LOCA.=B2 What does this actually mean?

To me it means that both the NRC l

and = the licensee don =B9t know if the ECCS system will operate even at =

2440 Mwt.

They state that these systems will not likely function

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i a

e at =

l 2700 MW~but they fail to address the issue if they will operate at =

l 2440MW. ~ This appears to be int'entional deception of the' general j

= public and.the State of Maine.

Throughout the' document they use the words:

B3These limiting

j conditions would exist only in~the low probability event of a large'= break LOCA.=B2 A large break LOCA is'part of the design basis and = the ECCS systems must function for this design basis event.

This is = like saying I don =B9t need seat belts, air bags

- of brakes because the = probability of needing them is very low.

i -

On page =B3v=B2 the NRC states: =B2 Maine Yankee was in general =

conformance with its licensing-basis although SIGNIFICANT ITEMS j

OF =

NON-CONFORMANCE WERE IDENTIFIED [ emphasis added).=B2 Translated this = means the licensee is not in compliance w!th the j

requirements.

On page =B3vii=B2 the NRC states: =B3there is a lack of a e

questioning = culture which has resulted in the failure to identify or promptly = correct significant problems in areas perceived by management to be = of low safety significance.=B2

- What are these significant problems = and why does_the NRC allow I

them to operate?

i j

On page 19 of the report the NRC states:

=B3The ISA team 4-reviewed = this information and concluded that these heat i

exchangers could be = considered operable at the higher thermal 1

J values resulting from plant = operation at 2700 Mwt.=B2 1

The NRC has no authority to determine if a component is operable.

l The licensee has a formal process outlined in Generic Letter 91-18 = and if the operability of a system, structure or i

i component (SSC=B9s) = is in question, the licensee MUST make a formal determination of = operability.

The NRC did this in the j

past and got burned and = admitted to me they do not have this i

authority.

This issue was = discussed in an NRC Inspector General =B9s report transmitted to me on =

j July 11, 1994.

At the top of page 20 the NRC again conducts operability =

determinations in violation of their own statutory authority.

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On page 21 they state: =B3WO 96-01785-00, completed August 9,

1996,

=

j-(SCCW), did not demonstrate whether these valves would perform their = safety related function.=B2 Why is the plant operating i

1.

if it can=B9t = be shown that safety systems are operable?

Page 23

=B3The ISA team did not consider the licensee's j

position = that the 345 kV system back-feed operation, completed 1

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,-T e

- -. - - - < - - - - - - =,

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within six = hours, was an acceptable basis for compliance with l

the FSAR and Maine =

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' Yankee Design Criterion 39.=B2 This is an open acknowledgment that = the plant is not in compliance with the design basis l

therefore not in = compliance with the regulations.

l Page 29 =B3The ISA team found that the licensee was not meeting 10 =

CFR 50.49 requirements in that there were certain electrical =

components that were not qualified for their expected environment

= following a design basis event.=B2 With this one statement the l

NRC = admits the plant is in violation of the; regulations.

Page 30: =B3a walkdown on July 24, 1996, of reactor containment that = revealed 30 components outside of Maine Yankee's design basis.=B2

'These are only examples but the very clear message is that the-plant = is not in compliance with the design basis and not in compliance with = the regulations and the NRC lets them continue to operate.

In my opinion,_given the fact'that a token audit uncovered many areas = of non-compliance, Maine Yankee should not be operating this plant = until they complete a review as required by last week =B9s 50.54 f = letter from the NRC.

They are breaking the l

law and the NRC is = helping them.

.I could continue and' cite many other examples but it is very l

clear to = me that the NRC did not want to ask the difficult questions because = the knew the correct answer would result in a plant shutdown for not = being in compliance with the regulations.

I have recently reviewed the NRC. report on Connecticut Yankee.

=

Comparing the two reports, the information contained in the MY report = is every bit-as condemning as the'CY report.

Some'of the same = deficiencies, such as the NPSH for the containment recirculation = pumps, were identified at both plants.

The difference is the =

=B3 spin =B2 put on the MY report.

From my perspective, the NRC is again covering their own incompetence = and embarrassment created by UCS=B9s disclosure of falsified LOCA = codes and the NRC=B9s Inspector General =B9s Event Inquiry dated May =

8,-1996.

Maine Yankee, with all the deficiencies identified in the'=

l ISAT' report, should conduct a complete design review before the plant = is allowed to continue operation.

It is clear from this-report, the = plant in non-compliance with both the design and licensing bases. The = conclusion of =B3(C]onsidered adequate for operation =B2 is totally = unsupported by any objective evidence and is contradicted by the = report itself.

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' Sincerely, Paul M. Blanch-135 Hyde Rd.

West Hartford CT.

06117 860-236-0326 Paul M. Blanch Energy Consultant l

135 Hyde Rd.

West Hartford CT 06117 Tel: 860-236-0326 Fax:-860-232-9350

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